text:
Communication and industrial accidents
As, Sicco van
This paper deals with the influence of organizational communication on safety. Accidents are actually caused by individual mistakes. However the underlying causes of accidents are often organizational. As a link between these two levels - the organizational failures and mistakes - I suggest the concept of role distance, which emphasizes the organizational characteristics. The general hypothesis is that communication failures are a main cause of role distance and accident-proneness within orga...
Communication and industrial accidents
As, Sicco van
This paper deals with the influence of organizational communication on safety. Accidents are actually caused by individual mistakes. However the underlying causes of accidents are often organizational. As a link between these two levels - the organizational failures and mistakes - I suggest the conc
Authority structure and industrial accidents
As, Sicco van
This paper deals with the influence of organizational characteristics on safety. Accidents are actually caused by individual mistakes. However the underlying causes of accidents are often organizational. The general hypothesis is that the authority structure is a main cause of accident-proneness wit
Authority structure and industrial accidents
As, Sicco van
This paper deals with the influence of organizational characteristics on safety. Accidents are actually caused by individual mistakes. However the underlying causes of accidents are often organizational. The general hypothesis is that the authority structure is a main cause of accident-proneness within organizations. On one side, the most obvious model for a safe organization would be the ideal-typical bureaucracy. On the other side, potential problems are little flexibility and control is ba...
Nuclear industry after the Fukushima accident
International Nuclear Information System (INIS)
This special dossier about the situation of nuclear industry two years after the Fukushima accident comprises 15 contributions dealing with: the nuclear industry two years after the Fukushima accident (Bernard Salha); a low-carbon electricity at a reasonable cost (Christophe Behar); nuclear engineering has to gain even more efficiency (Thomas Branche); how to dispose off the most radioactive wastes (Marie-Claude Dupuis, Thibaud Labalette); ensuring the continuation for more than 40 years onward (Denis Gasquet); developing and investing in the future (Philippe Knoche); more than just signing contracts (Dominique Lagarde); immersed power plants, an innovative concept (Bernard Planchais); R and D as a source of innovation for safety and performances (Jean-Pierre West); dismantlement, a very long term market (Jerome Stubler, Bruno Lancia); a reference industrial model (Herve Machenaud); recruiting and training (Andre Einaudi); a diversity of modern reactors and a world market in rebirth (Philippe Anglaret); an industrial revolution is necessary (Yves Brachet); contracts adapted to sensible works (Philippe Bonnave)
Occupational Accidents: A Perspective of Pakistan Construction Industry
Directory of Open Access Journals (Sweden)
Tauha Hussain Ali
Full Text Available It has been observed that the construction industry is one of the notorious industry having higher rate of fatalities and injuries. Resulting in higher financial losses and work hour losses, which are normally faced by this industry due to occuptional accidents. Construction industry has the highest occupational accidents rate recorded throughout the world after agriculture industry. The construction work site is often a busy place having an incredibly high account of activities taking place, where everyone is moving in frenzy having particular task assigned. In such an environment, occupational accidents do occur. This paper gives information about different types of occupational accidents & their causes in the construction industry of Pakistan. A survey has been carried out to identify the types of occupational accidents often occur at construction site. The impact of each occupational accident has also been identified. The input from the different stakeholders involved on the work site was analyzed using RIW (Relative Importance Weight method. The findings of this research show that ?fall from elevation, electrocution from building power and snake bite? are the frequent occupational accidents occur within the work site where as ?fall from elevation, struck by, snake bite and electrocution from faulty tool? are the occupational accident with high impact within the construction industry of Pakistan. The results also shows the final ranking of the accidents based on higher frequency and higher impact. Poor Management, Human Element and Poor Site Condition are found as the root causes leading to such occupational accidents. Hence, this paper
Occupational accidents: a perspective of pakistan construction industry
International Nuclear Information System (INIS)
It has been observed that the construction industry is one of the notorious industry having higher rate of facilities and injuries. Resulting in higher financial losses and work hour losses, which are normally faced by this industry due to occupational accidents. Construction industry has the highest occupational accidents rate recorded throughout the world after agriculture industry. The construction work site is often a busy place having an incredibly high account of activities taking place, where everyone is moving in frenzy having particular task assigned. In such an environment, occupational accidents do occur. This paper gives information about different types of occupational accidents and their causes in the construction industry of Pakistan. A survey has been carried out to identify the types of occupational accidents often occur at construction site. The impact of each occupational accident has also been identified. The input from the different stakeholders involved on the work site was analyzed using RIW (Relative Importance Weight) method. The findings of this research show that fall from elevation, electrocution from building power and snake bite are the frequent occupational accidents occur within the work site where as fall from elevation, struck by, snake bite and electrocution from faulty tool are the occupational accident with high impact within the construction industry of Pakistan. The results also shows the final ranking of the accidents based on higher frequency and higher impact. Poor Management, Human Element and Poor Site Condition are found as the root causes leading to such occupational accidents. Hence, this paper identify that what type of occupational accidents occur at the work place in construction industry of pakistan, in order to develop the corrective actions which should be adequate enough to prevent the re-occurrence of such accidents at work site. (author)
Industrial accidents in nuclear power plants
International Nuclear Information System (INIS)
In 12 nuclear power plants in the Federal Republic of Germany with a total of 3678 employees, 25 notifiable company personnel accidents and 46 notifiable outside personnel accidents were reported for an 18-month period. (orig./HP)
A methodology for radiological accidents analysis in industrial gamma radiography
International Nuclear Information System (INIS)
A critical review of 34 published severe radiological accidents in industrial gamma radiography, that happened in 15 countries, from 1960 to 1988, was performed. The most frequent causes, consequences and dose estimation methods were analysed, aiming to stablish better procedures of radiation safety and accidents analysis. The objective of this work is to elaborate a radiological accidents analysis methodology in industrial gamma radiography. The suggested methodology will enable professionals to determine the true causes of the event and to estimate the dose with a good certainty. The technical analytical tree, recommended by International Atomic Energy Agency to perform radiation protection and nuclear safety programs, was adopted in the elaboration of the suggested methodology. The viability of the use of the Electron Gamma Shower 4 Computer Code System to calculate the absorbed dose in radiological accidents in industrial gamma radiography, mainly at sup(192)Ir radioactive source handling situations was also studied. (author)
Accidents in the construction industry in the Netherlands: An analysis of accident reports using Storybuilder
International Nuclear Information System (INIS)
As part of an ongoing effort by the Ministry of Social Affairs and Employment of the Netherlands, a research project is being undertaken to construct a causal model for occupational risk. This model should provide quantitative insight into the causes and consequences of occupational accidents. One of the components of the model is a tool to systematically classify and analyse reports of past accidents. This tool 'Storybuilder' was described in earlier papers. In this paper, Storybuilder is used to analyse the causes of accidents reported in the database of the Dutch Labour Inspectorate involving people working in the construction industry. Conclusions are drawn on measures to reduce the accident probability. Some of these conclusions are contrary to common beliefs in the industry
Comparison of Commonly Used Accident Analysis Techniques for Manufacturing Industries
Directory of Open Access Journals (Sweden)
Full Text Available The adverse consequences of major accident events have led to development of accident analysis techniques to investigate thoroughly the accidents. However, each technique has its own advantages and shortcomings,which make it very difficult to find a single technique being capable of analyzing all types of accidents. Therefore, the comparison of accident analysis techniques would help finding out their capabilities in different circumstances to choose the most one. In this research, the techniques CBA and AABF were compared with Tripod β in order to determine the superior technique for analysis of major accidents in manufacturing industries. At first step, the comparison criteria were developed using Delphi Method. Afterwards, the relative importance of each criterion was qualitatively determined and the qualitative values were then converted to the quantitative values applying Fuzzy triangular numbers. Finally, the TOPSIS was used to prioritize the techniques in terms of the preset criteria. The results of the study showed that Tripod β is superior to the CBA and AABF. It is highly recommended to compare all available accident analysis techniques based on proper criteria in order to select the best one whereas improper choice of accident analysis techniques may lead to misguided results.
Tokai Mura accident and future of nuclear industry
International Nuclear Information System (INIS)
After Chernobyl, human error once again triggered the world's worst nuclear accident at the Tokai Mura nuclear plant. Although there was only one fatal casualty, the accident could be a big blow to the nuclear industry and would scarcely help the nuclear lobby to promote nuclear energy. It would rather lead to the usual calls from nuclear opponents and anti-nuclear organisations for the world to give up nuclear power. The accident has forced Japanese authorities to cutback and to consider dropping the plants to build 16-20 nuclear power plants by March 2011. However, one should think that by year 2050, the world's energy demand will have doubled: when fossil fuels, particularly oil and gas reserves, run short, is there any other energy source that can meet this target beside replacing 442 nuclear power stations currently in operation. Environmental impacts related to the use of fossil fuels should also be not ignored. (author)
Accidents in Malaysian construction industry: statistical data and court cases.
Chong, Heap Yih; Low, Thuan Siang
Safety and health issues remain critical to the construction industry due to its working environment and the complexity of working practises. This research attempts to adopt 2 research approaches using statistical data and court cases to address and identify the causes and behavior underlying construction safety and health issues in Malaysia. Factual data on the period of 2000-2009 were retrieved to identify the causes and agents that contributed to health issues. Moreover, court cases were tabulated and analyzed to identify legal patterns of parties involved in construction site accidents. Approaches of this research produced consistent results and highlighted a significant reduction in the rate of accidents per construction project in Malaysia. PMID:25189753
Equipment failures and their contribution to industrial incidents and accidents in the manufacturing industry.
Bourassa, Dominic; Gauthier, François; Abdul-Nour, Georges
Accidental events in manufacturing industries can be caused by many factors, including work methods, lack of training, equipment design, maintenance and reliability. This study is aimed at determining the contribution of failures of commonly used industrial equipment, such as machines, tools and material handling equipment, to the chain of causality of industrial accidents and incidents. Based on a case study which aimed at the analysis of an existing pulp and paper company's accident database, this paper examines the number, type and gravity of the failures involved in these events and their causes. Results from this study show that equipment failures had a major effect on the number and severity of accidents accounted for in the database: 272 out of 773 accidental events were related to equipment failure, where 13 of them had direct human consequences. Failures that contributed directly or indirectly to these events are analyzed. PMID:26652772
Equipment failures and their contribution to industrial incidents and accidents in the manufacturing industry.
Bourassa, Dominic; Gauthier, François; Abdul-Nour, Georges
Accidental events in manufacturing industries can be caused by many factors, including work methods, lack of training, equipment design, maintenance and reliability. This study is aimed at determining the contribution of failures of commonly used industrial equipment, such as machines, tools and material handling equipment, to the chain of causality of industrial accidents and incidents. Based on a case study which aimed at the analysis of an existing pulp and paper company's accident database, this paper examines the number, type and gravity of the failures involved in these events and their causes. Results from this study show that equipment failures had a major effect on the number and severity of accidents accounted for in the database: 272 out of 773 accidental events were related to equipment failure, where 13 of them had direct human consequences. Failures that contributed directly or indirectly to these events are analyzed.
Economic development and traffic accident mortality in the industrialized world, 1962-1990
E.F. van Beeck (Ed); G.J.J.M. Borsboom (Gerard); J.P. Mackenbach (Johan)
textabstractBACKGROUND: We examined the association between prosperity and traffic accident mortality in the industrialized world in a long-term perspective. METHODS: We calculated traffic accident mortality, traffic mobility and the fatal injury rate of 21 industrializ
The Role Of Industrial Safety Measures In Combating Occupational Hazards And Accidents In India
Sharmistha Bhattacharjee
The presence of occupational hazards and industrial accidents de-motivates the worker to contribute their best to the organization. The participation of workers in the workplace which promises safety and security fosters teamwork, quality of product high productivity and a good communication between management and the industrial workers. For combating occupational hazards and accidents in an industrial site, safety is necessary and a challenging issue in an industrial environment. S...
Deterrence theory and labelling of industrial accidents as white-collar crime in Bangladesh apparel industry: An epistemological standpoint
Muhammad Faisol Chowdhury
This paper aims to label industrial accidents as white-collar crime in Bangladesh apparel industry, where occupational health and safety provisions are mostly brushed aside by the factory owners. The study incorporates theory and evidence from over 92 sources from the of criminology, legal systems, occupational health and safety systems, and industrial accidents. The study observes a severe leniency and negligence among the factory owners in advocation and adaptation of these provisions which...
[1894-1906: new ideas and practice against industrial accidents in Italy].
Porro, A; Franchini, A F; Lorusso, L; Falconi, B
In October 1894 was held in Milan the III Congrés International des Accidents du Travail et des Assurances Sociales. 747 delegates participated, coming from 16 nations. In this Congress the theme of a special medical assistance in the industrial accidents was approached for the first time in Italy. In March, 1895 also the Milanese trade union office dealt him with the matter, organizing a specific congress. The trade union movement realized the necessity to approach the problem of industrial accidents. 170 delegates participated to the Congress. The 1895 Congress also represented the occasion for the dawning feminist movement to come into contact with the working class. In 1896 the Association for the Medical Assistance in the Industrial Accidents in Milan was founded. The Association started up a clinical institute. At the end of the XIXth century, with prevention and therapeutic interventions the problem of industrial accidents was faced.
Level of work accidents in the woodworking industry plants in the Opole Silesia region
Directory of Open Access Journals (Sweden)
Kornelia Polek-Duraj
Full Text Available The article presents a short characteristic of woodworking industry with the consideration of work accidents level in the chosen plants of woodworking industry in the Opole Silesia region. Moreover, it indicates the most frequent causes of work accidents and occupational risks. On the basis of the conducted analysis it can be assumed that the level of work accidents occurring in the woodworking industry is still very high, and the elementary cause of it, are inappropriate behaviour of workers and obsolete machines in use.
Pattern extraction for high-risk accidents in the construction industry: a data-mining approach.
Amiri, Mehran; Ardeshir, Abdollah; Fazel Zarandi, Mohammad Hossein; Soltanaghaei, Elahe
Accidents involving falls and falling objects (group I) are highly frequent accidents in the construction industry. While being hit by a vehicle, electric shock, collapse in the excavation and fire or explosion accidents (group II) are much less frequent, they make up a considerable proportion of severe accidents. In this study, multiple-correspondence analysis, decision tree, ensembles of decision tree and association rules methods are employed to analyse a database of construction accidents throughout Iran between 2007 and 2011. The findings indicate that in group I, there is a significant correspondence among these variables: time of accident, place of accident, body part affected, final consequence of accident and lost workdays. Moreover, the frequency of accidents in the night shift is less than others, and the frequency of injury to the head, back, spine and limbs are more. In group II, the variables time of accident and body part affected are mostly related and the frequency of accidents among married and older workers is more than single and young workers. There was a higher frequency in the evening, night shifts and weekends. The results of this study are totally in line with the previous research. PMID:25997167
Deterrence theory and labelling of industrial accidents as white-collar crime in Bangladesh apparel industry: An epistemological standpoint
Directory of Open Access Journals (Sweden)
Muhammad Faisol Chowdhury
Full Text Available This paper aims to label industrial accidents as white-collar crime in Bangladesh apparel industry, where occupational health and safety provisions are mostly brushed aside by the factory owners. The study incorporates theory and evidence from over 92 sources from the of criminology, legal systems, occupational health and safety systems, and industrial accidents. The study observes a severe leniency and negligence among the factory owners in advocation and adaptation of these provisions which can be labelled as white-collar crime.
Communicating worst-case scenarios: neighbors' views of industrial accident management.
Johnson, Branden B; Chess, Caron
The prospect of industrial accidents motivated the U.S. Congress to require in the Clean Air Act of 1990 that manufacturing facilities develop Risk Management Plans (RMP) to submit to the U.S. Environmental Protection Agency (USEPA) by July 1999. Industry worried that the requirement to communicate to the public a "worst-case scenario" would arouse unnecessary and counterproductive fears among industry neighbors. We report here the results of focus groups and surveys with such neighbors, focusing particularly upon their reactions to messages about a hypothetical worst-case scenario and management of these risks by industry, government, and other parties. Our findings confirmed our hypotheses that citizens would be skeptical of the competence and trustworthiness of these managers and that this stance would color their views of industrial-facility accident risks. People with job ties to industry or who saw industrial benefits to the community as exceeding its risks had more positive views of industrial risks, but still expressed great concern about the risk and doubt about accident management. Notwithstanding these reactions, overall respondents welcomed this and other related information, which they wanted their local industries to supply. Respondents were not more reassured by additional text describing management of accidents by government and industry. However, respondents did react very positively to the concept of community oversight to review plant safety. Claims about the firm's moral obligation or financial self-interest in preventing accidents were also received positively. Further research on innovative communication and management of accident risks is warranted by these results, even before recent terrorist attacks made this topic more salient. PMID:12926575
Who pays the costs of industrial accidents like Three Mile Island
International Nuclear Information System (INIS)
The accident at Three Mile Island (TMI) nuclear unit 2 generating plant in Pennsylvania provides a case study on how losses resulting from large industrial accidents are allocated in society. TMI demonstrated that industry regulation, no matter how pervasive, can fail to prevent social harm, and that there are often costs beyond personal injuries and property damage. Although the Price-Anderson Act compensated the public, other insurance was inadequate to cover the losses of shareholders and ratepayers. When the $300 million property insurance proved inadequate, the industry raised property damage insurance to $1 billion and replacement power insurance to $250 million
The accident evolution and barrier model applied to incident analysis in the processing industries
International Nuclear Information System (INIS)
This study presents a model for how accidents develop and how the accident evolution can be arrested. The model describes the interaction between the technical and human-organizational systems which may lead to an accident. The framework provided by the model may be used in predictive safety analyses as well as in post-hoc incident analyses. To illustrate this, the model is applied on an incident reported by the nuclear industry of Sweden. In general, application of the model will indicate where safety can be improved and raises questions about issues such as the cost, feasibility and effectiveness of different ways of increasing safety. (author). 15 refs, 2 figs
Cascading events triggering industrial accidents: quantitative assessment of NaTech and domino scenarios
Necci, Amos
The so called cascading events, which lead to high-impact low-frequency scenarios are rising concern worldwide. A chain of events result in a major industrial accident with dreadful (and often unpredicted) consequences. Cascading events can be the result of the realization of an external threat, like a terrorist attack a natural disaster or of "domino effect". During domino events the escalation of a primary accident is driven by the propagation of the primary event to nearby units, causin...
Fatal accidents analysis in Peruvian mining industry; Analisis de accidentes fatales en la industria minera peruana
Energy Technology Data Exchange (ETDEWEB)
Candia, R. C.; Hennies, W. T.; Azevedo, R. c.; Almeida, I.G.; Soto, J. F.
Although reductions in the tax of injuries and accidents have been observed in recent years, Mining is still one of the highest risks industries. The basic causes for occurrence of fatalities can be attributed to unsafe conditions and unsafe acts. In this scene is necessary to identify safety problems and to aim the effective solutions. On the other hand, the developing countries dependence on primary industries as mining is evident. In the Peruvian economy, approximately 16% of the GNP and more than 50% of the exportations are due to the mining sector, detaching its competitive position in the worldwide mining. This paper presents fatal accidents analysis in the Peruvian mining industry, having as basis the register of occurred fatal accidents since year 2000 until 2007, identifying the main types of accidents occurred. The source of primary information is the General Mining Direction (DGM) of the Peruvian Mining and Energy Ministry (MEM). The majority of victims belongs to tertiary contractor companies that render services for mine companies. The results of the analysis show also that the majority of accidents happened in the underground mines, and that it is necessary to propose effective solutions to manage risks, aiming at reducing the fatal accidents taxes. (Author)
Investigation Effect of Biorhythm on Work-Related Accidents in The Metal Industry (A Short Report
Directory of Open Access Journals (Sweden)
Ehsanollah Habibi
Full Text Available Biorhythm is one of the newest subjects in the field of cognition of mental ergonomics which can be very effective in reduction of work-related accidents or mistakes with no apparent reason. With evaluating Biorhythm individuals can intervention action to reduce job accidents carried out. Thus, the aim of this study was to determine the relationship Biorhythm and work-related accidents in the metal industry. This research is a cross-sectional and analytical-descriptive in the metal industrial Isfahan city of 120 work-related accidents during 2015. The required information was collected from available documents in HSE unit of the company biorhythm charts were drawn based on a date of accidents and participants birthdays, using natural Biorhythm Software V3.02 Conduct. Finally، the data were analyzed using spss version 20 and descriptive statistics.This study showed that the frequency of accidents in critical days and negative section of physical cycle was more than expected. Also the frequency of accidents in critical days and negative section of emotional and intellectual cycles was less than expected. Most type of injury, including cuts to 35.8 percent and the lowest type of injury was torsion with 5 percent. Most limb injury, hands and fingers with 51.7 percent and the lowest limb injury were back at 2.5 percent. Accidents outbreak in physical cycles was 38.3 percent. These 120 accidents in additionally were causing 120 loss of working days in effect accident. Most percent of loss of working days were for 20 to 30 days with of 39.2 percent. Most percent of loss of working days were for 20 to 30 days with of 39.2 percent. Due to the physical nature of the work activities in the metal industry can be stated that the study showed that in physical work activities, frequency of accidents in critical days and negative section of physical cycle in which the person is not physically ready to do the job was more than expected. Therefore, by training
Key factors contributing to accident severity rate in construction industry in Iran: a regression modelling approach.
Soltanzadeh, Ahmad; Mohammadfam, Iraj; Moghimbeigi, Abbas; Ghiasvand, Reza
Construction industry involves the highest risk of occupational accidents and bodily injuries, which range from mild to very severe. The aim of this cross-sectional study was to identify the factors associated with accident severity rate (ASR) in the largest Iranian construction companies based on data about 500 occupational accidents recorded from 2009 to 2013. We also gathered data on safety and health risk management and training systems. Data were analysed using Pearson's chi-squared coefficient and multiple regression analysis. Median ASR (and the interquartile range) was 107.50 (57.24- 381.25). Fourteen of the 24 studied factors stood out as most affecting construction accident severity (psafety and health risk management system to reduce ASR. PMID:27092639
Economic consequences of major accidents in the industrial plants: The case of a nuclear power plant
International Nuclear Information System (INIS)
These last years, newspapers head-lines have reported various accidents (Mexico City, Bhopal, Chernobyl, ...) which have drawn attention to the fact that the major technological risk is now a reality and that, undoubtedly, industrial decision-makers ought to integrate it into their preoccupations. In addition to the sometimes considerable human problems such accidents engender, their economic consequences may be such that they become significant on a national or even international scale. The aim of the present paper is to analyse these economic effects by using the particular context of a nuclear power plant. The author has deliberately limited his subject to the consequences of a major accident, that is to say a sudden event, theoretically unforeseen and beyond man's control. The qualification major means an accident of which the consequences extend far beyond the industrial plant itself. The direct and indirect economic consequences are analysed from the responsibility point of view as well as from the national and international community's point of view. A paragraph explains how the coverage of the costs can rely on the cooperation of a number of parties: responsible company, state, insurers, customers, etc. The study is broadly based on the experience resulting from the two major accidents which happened in the nuclear industry these last years (Three Mile Island in 1979 and Chernobyl in 1986) and makes use of more theoretical considerations, for example in the field of the economic evaluation of human life. (author). 58 refs, 2 figs, 12 tabs
Can we use near-miss reports for accident prevention? A study in the oil and gas industry in Denmark
Rasmussen, H.B.; Drupsteen, L.; Dyreborg, J.
Background: The oil and gas industry in the Danish sector of the North Sea has always focused on reducing work-related accidents. Over the years, accident rates have been reduced, and near-miss reporting has gained in importance, because it allows the industry to learn from experience and prevent fu
Mining industry accident, injuries, employment and production data are given between the years 1931-2001. In 1983, the U.S. Congress limited the Mine Safety and Health Administration's (MSHA) enforcement activities over surface mining and milling of stone, clay, feldspar, colloid...
Estimating the continuous risk of accidents occuring in the mining industry in South Africa
Directory of Open Access Journals (Sweden)
Van den Honert, Andrew Francis
Full Text Available This study contributes to the on-going efforts to improve occupational safety in the mining industry by creating a model capable of predicting the continuous risk of occupational accidents occurring. Contributing factors were identified and their sensitivity quantified. The approach included using an Artificial Neural Network (ANN to identify patterns between the input attributes and to predict the continuous risk of accidents occurring. The predictive Artificial Neural Network (ANN model used in this research was created, trained, and validated in the form of a case study with data from a platinum mine near Rustenburg in South Africa. This resulted in meaningful correlation between the predicted continuous risk and actual accidents.
Psychophysiological and other factors affecting human performance in accident prevention and investigation. [Comparison of aviation with other industries
Energy Technology Data Exchange (ETDEWEB)
Klinestiver, L.R.
Psychophysiological factors are not uncommon terms in the aviation incident/accident investigation sequence where human error is involved. It is highly suspect that the same psychophysiological factors may also exist in the industrial arena where operator personnel function; but, there is little evidence in literature indicating how management and subordinates cope with these factors to prevent or reduce accidents. It is apparent that human factors psychophysological training is quite evident in the aviation industry. However, while the industrial arena appears to analyze psychophysiological factors in accident investigations, there is little evidence that established training programs exist for supervisors and operator personnel.
Emergency Response System for Pollution Accidents in Chemical Industrial Parks, China
Weili Duan; Bin He
In addition to property damage and loss of lives, environment pollution, such as water pollution and air pollution caused by accidents in chemical industrial parks (CIPs) is a significant issue in China. An emergency response system (ERS) was therefore planned to properly and proactively cope with safety incidents including fire and explosions occurring in the CIPs in this study. Using a scenario analysis, the stages of emergency response were divided into three levels, after introducing the ...
Occupational accidents and affecting factors of metal industry in a factory in Ankara
Directory of Open Access Journals (Sweden)
Mustafa N. Ilhan
Full Text Available Abstract Objective:According to the statistics of the Social Security Institution, 18672 occupational accidents occurred in the metal industry in 2008 in Turkey. Whereas 78 of these accidents resulted in death, 252 people became permanently incapable of working. In 2008, 369677 working days were lost as a result of occupational accidents. Evaluating the reasons for and the results of accidents in the metal industry and contributing to the development of recommendations for prevention in accordance with the information obtained. Method: The study was conducted with 201 of 210 workers working in heavy metal manufacturing and construction in the building company between April 2008 and June 2008. Results: The frequency of occupational accidents among the metal workers was 22% between January 2007 and June 2008. The reasons for the workers' accidents are listed as; insufficient use of personal protective equipment (44%, carelessness (37%, and personal reasons, not to be taken of security measures at machines and looms/ unsuitable machines (both 17%.Conclusion: The study demonstrates that the accidents mostly occur because of failure to use of personal protective equipment, insufficient vocational training. Key Words: Occupational, accident, metal industry, preventionAnkara'da bir metal sanayi fabrikasında iş kazaları ve etkileyen faktörler Özet Amaç: 2008 yılında Sosyal Güvenlik Kurumu'nun verilerine göre metal sanayisinde 18672 iş kazası meydana gelmiş ve 369677 işgünü kaybı olmuştur. Bu kazalardan 78 tanesi ölümle sonuçlanırken, 252 kişi kalıcı olarak işgöremez hale gelmiştir. Metal sanayisinde meydana gelen kazaların sebep ve sonuçlarını inceleyerek, elde edilen bilgiler doğrultusunda kazaların önlenmesine yönelik tavsiyelerin geliştirilmesi amaçlanmıştır. Yöntem: Araştırma, Ankara'da faaliyet gösteren ağır metal imalat, konstrüksiyon ve inşaat sanayi şirketinde 2008 Nisan-2008 Haziran d
Statistical Analysis of Sino-U.S. Coal Mining Industry Accidents
Guiling Wei
Both China and the United States are large countries in coal production and consumption, however, the safety conditions of coal mining production in China are much worse than that of the U.S.. Although the Chinese Administration of Coal Mine Safety improved safety measures to tighten control on coal mining industry, the number of accidents, death toll and fatality rate per million tons were much higher than those of the U.S. in recent years. Based on the statistical analysis of Sino-U.S. coal...
Finding occupational accident patterns in the extractive industry using a systematic data mining approach
International Nuclear Information System (INIS)
This paper deals with occupational accident patterns of in the Portuguese Extractive Industry. It constitutes a significant advance with relation to a previous study made in 2008, both in terms of methodology and extended knowledge on the patterns' details. This work uses more recent data (2005–2007) and this time the identification of the "typical accident" shifts from a bivariate, to a multivariate pattern, for characterising more accurately the accident mechanisms. Instead of crossing only two variables (Deviation x Contact), the new methodology developed here uses data mining techniques to associate nine variables, through their categories, and to quantify the statistical cohesion of each pattern. The results confirmed the "typical accident" of the 2008 study, but went much further: it reveals three statistically significant patterns (the top-3 categories in frequency); moreover, each pattern includes now more variables (4–5 categories) and indicates their statistical cohesion. This approach allowed a more accurate vision of the reality, which is fundamental for risk management. The methodology is best suited for large groups, such as national Authorities, Insurers or Corporate Groups, to assist them planning target-oriented safety strategies. Not least importantly, researchers can apply the same algorithm to other study areas, as it is not restricted to accidents, neither to safety.
Evaluation of hazards from industrial activity near nuclear power plants. Study of typical accidents
International Nuclear Information System (INIS)
The design and dimensioning of nuclear power plant structures necessitate the evaluation of risks due to industrial activity. Among these risks, those due to the storage or transport of dangerous products merit special attention. They result, inter alia, in the explosion of flammable gas clouds. Such clouds can drift before igniting and, once alight, the resulting pressure wave can cause serious damage, even at a distance. A methodology both deterministic and probabilistic enabling this risk to be quantified has therefore been developed. It is based in part on an analysis of the statistics of actual accidents that have occurred. After briefly recalling the probabilistic model, the typical accidents selected are described and for three usual cases (storage under pressure, rail tank cars and road units) the main characteristics of the rupture are explicited. The deterministic models that have been worked out to calculate the consequences of such an accident: flow rate at the bursting point, evaporation, drift and atmospheric dispersion of the cloud formed, explosion of this cloud, are then described. At the present time the overpressure wave is quantified against a TNT equivalent of the explosive mixture. Some data are given as examples for three commonly employed hydrocarbons (butane, propane, propylene)
SisRadiologia: a new software tool for analysis of radiological accidents and incidents in industrial radiography
Energy Technology Data Exchange (ETDEWEB)
Lima, Camila M. Araujo; Silva, Francisco C.A. da, E-mail: firstname.lastname@example.com, E-mail: email@example.com [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Araujo, Rilton A., E-mail: firstname.lastname@example.com [Maxim Industrial Assessoria TI, Rio de Janeiro, RJ (Brazil)
According to the International Atomic Energy Agency (IAEA), many efforts have been made by Member states, aiming a better control of radioactive sources. Accidents mostly happened in practices named as high radiological risk and classified by IAEA in categories 1 and 2, being highlighted those related to radiotherapy, large irradiators and industrial radiography. Worldwide, more than 40 radiological accidents have been recorded in the industrial radiography. Worldwide, more than 40 radiological accidents have been recorded in the industrial radiography area, involving 37 workers, 110 members of the public and 12 fatalities. Records display 5 severe radiological accidents in industrial radiography activities in Brazil, in which 7 workers and 19 members of the public were involved. Such events led to hands and fingers radiodermatitis, but to no death occurrence. The purpose of this study is to present a computational program that allows the data acquisition and recording in the company, in such a way to ease a further detailed analysis of radiological event, besides providing the learning cornerstones aiming the avoidance of future occurrences. After one year of the 'Industrial SisRadiologia' computational program application - and mostly based upon the workshop about Analysis and Dose Calculation of Radiological Accidents in Industrial Radiography (Workshop sobre Analise e Calculo de dose de acidentes Radiologicos em Radiografia Industrial - IRD 2012), in which several Radiation Protection officers took part - it can be concluded that the computational program is a powerful tool to data acquisition, as well as, to accidents and incidents events recording and surveying in Industrial Radiography. The program proved to be efficient in the report elaboration to the Brazilian Regulatory Authority, and very useful in workers training to fix the lessons learned from radiological events.
Accident investigation practices in Europe--main responses from a recent study of accidents in industry and transport
International Nuclear Information System (INIS)
Europe has during recent years been shocked by disasters from natural events and technical breakdowns. The consequences have been comprehensive, measured by lost lives, injuries, and material and environmental damage. ESReDA wanted in 2000 - by setting up a special expert group on accident investigation - to clarify the state of art of accident investigation practices and to map the use of thoroughly accident investigation in order to learn lessons from past disasters and prevent new ones. The scope was to cover three sectors in the society: transport, production processes and storage of hazardous materials, and energy production. The main method used was a questionnaire, which was sent in 2001 to about 150 organisations. About 50 replies were analysed. The replies showed great variations but also similarities, among others in definition of accident and incident, the objectives of the investigation team, criteria used to start an investigation, the status of the investigation organisation, the flow of information, the composition of the investigation team, and the use of internal or international procedures or rules. Several methods (in total 14 different methods were mentioned) were used for carrying out accident /incident investigations. Most of the respondents were willing to co-operate in one or another way with ESReDA. Although there are important biases in the material, the results from questionnaire are important inputs to the future work of ESReDA Expert group in this field. 3 safety approaches have been identified
A strategy to the development of a human error analysis method for accident management in nuclear power plants using industrial accident dynamics
International Nuclear Information System (INIS)
This technical report describes the early progress of he establishment of a human error analysis method as a part of a human reliability analysis(HRA) method for the assessment of the human error potential in a given accident management strategy. At first, we review the shortages and limitations of the existing HRA methods through an example application. In order to enhance the bias to the quantitative aspect of the HRA method, we focused to the qualitative aspect, i.e., human error analysis(HEA), during the proposition of a strategy to the new method. For the establishment of a new HEA method, we discuss the basic theories and approaches to the human error in industry, and propose three basic requirements that should be maintained as pre-requisites for HEA method in practice. Finally, we test IAD(Industrial Accident Dynamics) which has been widely utilized in industrial fields, in order to know whether IAD can be so easily modified and extended to the nuclear power plant applications. We try to apply IAD to the same example case and develop new taxonomy of the performance shaping factors in accident management and their influence matrix, which could enhance the IAD method as an HEA method. (author). 33 refs., 17 tabs., 20 figs
Can Emotional Intelligence be Used as a Tool to Control Occupational Accidents?Case Study in an Iranian Industry
Mohammad Khandan; Alireza Koohpaei
Nowadays, in order to attain safety at workplaces, we must consider two factors: ethical adolescence and emotional intelligence. Emotional intelligence helps people to learn about regulations, experiences and revelation of emotions. This study aimed to survey the relationship between emotional intelligence (EI) with occupational accident in a publication industry, in 2014. In a cross-sectional study, all operational employees (n=98) working at a publication industry were included. Demographic...
A Study of The Relationship Between The Components of The Five-Factor Model of Personality and The Occurrence of Occupational Accidents in Industry Workers
Directory of Open Access Journals (Sweden)
Ehsanollah Habibi
Full Text Available Accidents are among the most important problems of both the developed and the developing countries. Individual factors and personality traits are the primary causes of human errors and contribute to accidents. The present study aims to investigate the relationship between the components of the five-factor model of personality and the occurrence of occupational accidents in industrial workers. The independent T-test indicated that there is a meaningful relationship between the personality traits and accident proneness. In the two groups of industry workers injured in occupational accidents and industry workers without any occupational accidents, there is a significant relationship between personality traits, neuroticism (p=0.001, openness to experience (p=0.001, extraversion (p=0.024 and conscientiousness (p=0.021. Nonetheless, concerning the personality trait of agreeableness (p = 0.09, the group of workers with accidents did not differ significantly from the workers without any accidents. The results showed that there is a direct and significant relationship between accident proneness and the personality traits of neuroticism and openness to experience. Furthermore, there is a meaningful but inverse correlation between accident proneness and the personality traits of extraversion and conscientiousness, while there was no relationship between accident proneness and the personality trait of agreeableness.
Emergency Response System for Pollution Accidents in Chemical Industrial Parks, China.
Duan, Weili; He, Bin
In addition to property damage and loss of lives, environment pollution, such as water pollution and air pollution caused by accidents in chemical industrial parks (CIPs) is a significant issue in China. An emergency response system (ERS) was therefore planned to properly and proactively cope with safety incidents including fire and explosions occurring in the CIPs in this study. Using a scenario analysis, the stages of emergency response were divided into three levels, after introducing the domino effect, and fundamental requirements of ERS design were confirmed. The framework of ERS was composed mainly of a monitoring system, an emergency command center, an action system, and a supporting system. On this basis, six main emergency rescue steps containing alarm receipt, emergency evaluation, launched corresponding emergency plans, emergency rescue actions, emergency recovery, and result evaluation and feedback were determined. Finally, an example from the XiaoHu Chemical Industrial Park (XHCIP) was presented to check on the integrality, reliability, and maneuverability of the ERS, and the result of the first emergency drill with this ERS indicated that the developed ERS can reduce delays, improve usage efficiency of resources, and raise emergency rescue efficiency.
Emergency Response System for Pollution Accidents in Chemical Industrial Parks, China
Directory of Open Access Journals (Sweden)
Weili Duan
Full Text Available In addition to property damage and loss of lives, environment pollution, such as water pollution and air pollution caused by accidents in chemical industrial parks (CIPs is a significant issue in China. An emergency response system (ERS was therefore planned to properly and proactively cope with safety incidents including fire and explosions occurring in the CIPs in this study. Using a scenario analysis, the stages of emergency response were divided into three levels, after introducing the domino effect, and fundamental requirements of ERS design were confirmed. The framework of ERS was composed mainly of a monitoring system, an emergency command center, an action system, and a supporting system. On this basis, six main emergency rescue steps containing alarm receipt, emergency evaluation, launched corresponding emergency plans, emergency rescue actions, emergency recovery, and result evaluation and feedback were determined. Finally, an example from the XiaoHu Chemical Industrial Park (XHCIP was presented to check on the integrality, reliability, and maneuverability of the ERS, and the result of the first emergency drill with this ERS indicated that the developed ERS can reduce delays, improve usage efficiency of resources, and raise emergency rescue efficiency.
Can Emotional Intelligence be Used as a Tool to Control Occupational Accidents?Case Study in an Iranian Industry
Directory of Open Access Journals (Sweden)
Mohammad Khandan
Full Text Available Nowadays, in order to attain safety at workplaces, we must consider two factors: ethical adolescence and emotional intelligence. Emotional intelligence helps people to learn about regulations, experiences and revelation of emotions. This study aimed to survey the relationship between emotional intelligence (EI with occupational accident in a publication industry, in 2014. In a cross-sectional study, all operational employees (n=98 working at a publication industry were included. Demographics, Bradberry-Greaves questionnaires were tools for gathering data. Occupational accidents were self-reported and then checked against documents in the organization. Statistical analysis such as T-test, ANOVA and Pearson correlation was used for data evaluation by SPSS V20. All workers were men and range of age was reported to be 24-61 with Mean 122.13±15.68. Also, 21.2% of personnel have experienced occupational accidents (0-5 cases. Also, Mean EI test score was calculated to be 122.13±15.68. There was no significant relationship between emotional intelligence scores among workers with and without accidents (p>0.05.Conditions in the view of emotional intelligence were suitable, but continuous improvement for total consideration and circumstances would be vital. Training program preparation free from workers of different educational levels is recommended. The company must provide a program that can afford workers the opportunity to review errors and gain cognitive systems in order to work with the improved conditions.
1945-1985-40 years of Nuclear Industry: an overview of important radiation accidents
International Nuclear Information System (INIS)
Approximately 180 radiation accidents which occurred in the world during the period 1945-1985 are summarized. The necessity of the availability of a database specifically oriented toward researchers interested in studying the different radiation accidents reported is emphasized. (M.A.C.)
Emergency planning and preparedness for accidents involving radioactive materials used in medicine, industry, research and teaching
International Nuclear Information System (INIS)
This Safety Series book should be considered as a technical guide aimed at the users of radioactive materials and the appropriate local and national authorities. It does not represent a single solution to the problems involved but rather draws the outlines of the plans and procedures that have to be developed in order to mitigate the consequences of an accident, should one occur. The preparation of local and national plans should follow the technical recommendations provided in this publication, with due consideration given to local factors which might vary from country to country (e.g. governmental systems, local legislation, quantities of radioactive materials involved). Several types of accidents are described, together with their possible radiological consequences. The basic principles of the protective measures that should be applied are discussed, and the principles of emergency planning and the measures needed to maintain preparedness for an operational response to an accident are outlined
Job stress, mental health, and accidents among offshore workers in the oil and gas extraction industries.
Cooper, C L; Sutherland, V J
Psychosocial and occupational stressors among 194 male employees on drilling rig and production platform installations in the United Kingdom and Dutch sectors of the North Sea were studied. Mental well-being and job satisfaction were also assessed, with attention to the incidence of accidents offshore. This occupational group were found to be much less satisfied with their jobs than their onshore counterparts. Although overall mental well-being compared favorably with that of the general population, levels of anxiety were significantly higher. Multivariate analysis showed "relationships at work and at home" to be a strong predictor of both job dissatisfaction and mental ill-health. Type A coronary-prone behavior was also found to be a significant predictor of reduced mental well-being and increased accident rates offshore.
Accident patterns and prevention measures for fatal occupational falls in the construction industry.
Chi, Chia-Fen; Chang, Tin-Chang; Ting, Hsin-I
Contributing factors to 621 occupational fatal falls have been identified with respect to the victim's individual factors, the fall site, company size, and cause of fall. Individual factors included age, gender, experience, and the use of personal protective equipment (PPE). Accident scenarios were derived from accident reports. Significant linkages were found between causes for the falls and accident events. Falls from scaffold staging were associated with a lack of complying scaffolds and bodily action. Falls through existing floor openings were associated with unguarded openings, inappropriate protections, or the removal of protections. Falls from building girders or other structural steel were associated with bodily actions and improper use of PPE. Falls from roof edges were associated with bodily actions and being pulled down by a hoist, object or tool. Falls through roof surfaces were associated with lack of complying scaffolds. Falls from ladders were associated with overexertion and unusual control and the use of unsafe ladders and tools. Falls down stairs or steps were associated with unguarded openings. Falls while jumping to a lower floor and falls through existing roof openings were associated with poor work practices. Primary and secondary prevention measures can be used to prevent falls or to mitigate the consequences of falls and are suggested for each type of accident. Primary prevention measures would include fixed barriers, such as handrails, guardrails, surface opening protections (hole coverings), crawling boards/planks, and strong roofing materials. Secondary protection measures would include travel restraint systems (safety belt), fall arrest systems (safety harness), and fall containment systems (safety nets).
Accident patterns and prevention measures for fatal occupational falls in the construction industry.
Chi, Chia-Fen; Chang, Tin-Chang; Ting, Hsin-I
Contributing factors to 621 occupational fatal falls have been identified with respect to the victim's individual factors, the fall site, company size, and cause of fall. Individual factors included age, gender, experience, and the use of personal protective equipment (PPE). Accident scenarios were derived from accident reports. Significant linkages were found between causes for the falls and accident events. Falls from scaffold staging were associated with a lack of complying scaffolds and bodily action. Falls through existing floor openings were associated with unguarded openings, inappropriate protections, or the removal of protections. Falls from building girders or other structural steel were associated with bodily actions and improper use of PPE. Falls from roof edges were associated with bodily actions and being pulled down by a hoist, object or tool. Falls through roof surfaces were associated with lack of complying scaffolds. Falls from ladders were associated with overexertion and unusual control and the use of unsafe ladders and tools. Falls down stairs or steps were associated with unguarded openings. Falls while jumping to a lower floor and falls through existing roof openings were associated with poor work practices. Primary and secondary prevention measures can be used to prevent falls or to mitigate the consequences of falls and are suggested for each type of accident. Primary prevention measures would include fixed barriers, such as handrails, guardrails, surface opening protections (hole coverings), crawling boards/planks, and strong roofing materials. Secondary protection measures would include travel restraint systems (safety belt), fall arrest systems (safety harness), and fall containment systems (safety nets). PMID:15892934
Nuclear industry and the management of accident risk in Europe: from the internalisation default to the coverage organization
International Nuclear Information System (INIS)
The production of nuclear energy creates environmental and sanitary risks among which the risk of nuclear accident. There is a twofold dimension in the management of such a risk: a preventive dimension and a compensatory one. Given its catastrophic and unpredictable character, the nuclear risk has always been managed in a specific way. In Europe, its management is unsatisfactory. The civil liability regime is beneficial to the nuclear industry as it leads to a lack of internalisation and thus to a limited coverage of potential damages. The financial cap of the nuclear operator's civil liability reduces his incentives for the prevention of accidents. By narrowing its liability, it also limits the burden tied to the coverage of the full potential damages. The organisation of the nuclear risk coverage was heavily conditioned by the civil liability regime and the financial cap it creates. Such an organisation is inefficient. The nuclear insurance market's financial capacity is not enough to compensate for all the potential victims of a major nuclear accident. Moreover, the functioning of this market is quite costly for the nuclear operator. While new electronuclear projects are being launched in Europe, the management of nuclear risks must be questioned in order to find better solutions to the necessity of internalising, preventing and compensating. Nuclear operators should be responsible for all the damages caused through an unlimited liability rule. The coverage of potential damages could also be improved by setting up a risk-sharing agreement at the European scale between operators. (author)
Analysis of human error in occupational accidents in the power plant industries using combining innovative FTA and meta-heuristic algorithms
Directory of Open Access Journals (Sweden)
M. Omidvari
Full Text Available Introduction: Occupational accidents are of the main issues in industries. It is necessary to identify the main root causes of accidents for their control. Several models have been proposed for determining the accidents root causes. FTA is one of the most widely used models which could graphically establish the root causes of accidents. The non-linear function is one of the main challenges in FTA compliance and in order to obtain the exact number, the meta-heuristic algorithms can be used. Material and Method: The present research was done in power plant industries in construction phase. In this study, a pattern for the analysis of human error in work-related accidents was provided by combination of neural network algorithms and FTA analytical model. Finally, using this pattern, the potential rate of all causes was determined. Result: The results showed that training, age, and non-compliance with safety principals in the workplace were the most important factors influencing human error in the occupational accident. Conclusion: According to the obtained results, it can be concluded that human errors can be greatly reduced by training, right choice of workers with regard to the type of occupations, and provision of appropriate safety conditions in the work place.
Accidents - Chernobyl accident; Accidents - accident de Tchernobyl
Energy Technology Data Exchange (ETDEWEB)
This file is devoted to the Chernobyl accident. It is divided in four parts. The first part concerns the accident itself and its technical management. The second part is relative to the radiation doses and the different contaminations. The third part reports the sanitary effects, the determinists ones and the stochastic ones. The fourth and last part relates the consequences for the other European countries with the case of France. Through the different parts a point is tackled with the measures taken after the accident by the other countries to manage an accident, the cooperation between the different countries and the groups of research and studies about the reactors safety, and also with the international medical cooperation, specially for the children, everything in relation with the Chernobyl accident. (N.C.)
The sector of agro-industrial production: Post-accident radiological consequences and the basic protective measures
International Nuclear Information System (INIS)
The accident at the Chernobyl nuclear power station led to fallout of radioactive substances on agricultural land. In this connection, the USSR State Agro-Industrial Committee, Gosagroprom, faced a number of tasks concerning evaluation of the radiological situation in the sector of agro-industrial production, organization of radiation monitoring of agricultural products and implementation of a series of agricultural ameliorative measures to reduce the radionuclide contamination of foodstuffs. The study of the radiological situation revealed a complex dynamics of the emergency release of radioactivity and inhomogeneous composition of the fallout on the contamination zone. Early autumn fallout of radionuclides caused aerial contamination of the leaves and stems of a number of agricultural crops - winter, natural and sown perennial grasses. The other types of plant were contaminated mainly through the soil and through wind lift. After deposition the bulk of the radionuclides were concentrated in the top soil. The availability of radionuclides for root assimilation depends on the proportion between the forms in which they occur in soils, which varies considerably in soils of different types. Application of amendments changes the transfer of radionuclides to agricultural crops. In animal husbandry two principal areas of activity are of the greatest interest: evaluation of the degree of contamination of products (first of all, milk and meat) and determination of the physiological condition of livestock in the immediate neighbourhood of the power station. An evaluation has been made of the organizational and agricultural ameliorative measures which were applied to ensure stable agro-industrial production in the contaminated area. (author). 1 fig., 9 tabs
Environmental justice: frequency and severity of US chemical industry accidents and the socioeconomic status of surrounding communities
Elliott, M.; Wang, Y.; Lowe, R; Kleindorfer, P
Study objectives: The Clean Air Act Amendments of 1990 requires that chemical facilities in the US with specified quantities of certain toxic or flammable chemicals file a five year history of accidents. This study considers the relation between the reported accidents and surrounding community characteristics.
Accidents - Chernobyl accident
International Nuclear Information System (INIS)
This file is devoted to the Chernobyl accident. It is divided in four parts. The first part concerns the accident itself and its technical management. The second part is relative to the radiation doses and the different contaminations. The third part reports the sanitary effects, the determinists ones and the stochastic ones. The fourth and last part relates the consequences for the other European countries with the case of France. Through the different parts a point is tackled with the measures taken after the accident by the other countries to manage an accident, the cooperation between the different countries and the groups of research and studies about the reactors safety, and also with the international medical cooperation, specially for the children, everything in relation with the Chernobyl accident. (N.C.)
The Chernobyl accident consequences
International Nuclear Information System (INIS)
Five teen years later, Tchernobyl remains the symbol of the greater industrial nuclear accident. To take stock on this accident, this paper proposes a chronology of the events and presents the opinion of many international and national organizations. It provides also web sites references concerning the environmental and sanitary consequences of the Tchernobyl accident, the economic actions and propositions for the nuclear safety improvement in the East Europe. (A.L.B.)
Organizational Learning from near Misses, Incidents, Accidents, and Fatalities: A Multiple Case Study of the USA Amusement Industry
Wall, Kathleen Horner
Accidents and fatalities at USA amusement parks are rare, yet when they do occur, they can injure, maim, and even kill. This dissertation sheds light on how three family-owned amusement parks learned and improved as organizations from their own and others' failure experience. Using a multiple case study design, 18 participants were interviewed.…
Effect of Occupational Health and Safety Management System on Work-Related Accident Rate and Differences of Occupational Health and Safety Management System Awareness between Managers in South Korea's Construction Industry
Yoon, Seok J.; Lin, Hsing K.; Chen, Gang; Yi, Shinjea; Choi, Jeawook; Rui, Zhenhua
Background The study was conducted to investigate the current status of the occupational health and safety management system (OHSMS) in the construction industry and the effect of OHSMS on accident rates. Differences of awareness levels on safety issues among site general managers and occupational health and safety (OHS) managers are identified through surveys. Methods The accident rates for the OHSMS-certified construction companies from 2006 to 2011, when the construction OHSMS became widel...
Giannattasio, E; Nencini, R; Nicolosi, N
After having carried out a historical review of industrial psychology with specific attention to the evolution of the concept of causality in accidents, the Authors formulate their work hypothesis from that research which take into highest consideration the executives' attitudes in the genesis of the accidents. As dogmatism appears to be one of the most negative of executives' attitudes, the Authors administered Rockeach's Scale to 130 intermediate executives from 6 industries in Latium and observed the frequency index for accidents and the morbidity index (absenteeism) of the 2149 workhand. The Authors assumed that to high degree of dogmatism on the executives' side should correspond o a higher level of accidents and absenteeism among the staff. The data processing revealed that, due to the type of machinery employed, three of the industries examined should be considered as High Risk Industrie (HRI), while the remaining three could be considered as Low Risk Industries (LRI): in fact, due to the different working conditions, a significant lower number of accidents occurred in last the three. A statistically significant correlation between the executives' dogmatism and the number of accidents among their workhand in the HRI has been noticed, while this has not been observed in the LRI. This confirms, as had already been pointed out by Gemelli in 1944, that some "objective conditions" are requested so that the accident may actually take place. On the other hand the morbidity index has not shown any difference related to the different kind of industries (HRI, LRI): in both cases statistically significant correlations were obtained between the executives' dogmatism and the staff's absenteeism. absenteeism.(ABSTRACT TRUNCATED AT 250 WORDS) PMID:3154344
Accident and emergency management
International Nuclear Information System (INIS)
There is an increasing potential for severe accidents as the industrial development tends towards large, centralised production units. In several industries this has led to the formation of large organisations which are prepared for accidents fighting and for emergency management. The functioning of these organisations critically depends upon efficient decision making and exchange of information. This project is aimed at securing and possibly improving the functionality and efficiency of the accident and emergency management by verifying, demonstrating, and validating the possible use of advanced information technology in the organisations mentioned above. With the nuclear industry in focus the project consists of five main activities: 1) The study and detailed analysis of accident and emergency scenarios based on records from incidents and rills in nuclear installations. 2) Development of a conceptual understanding of accident and emergency management with emphasis on distributed decision making, information flow, and control structure sthat are involved. 3) Development of a general experimental methodology for evaluating the effects of different kinds of decision aids and forms of organisation for emergency management systems with distributed decision making. 4) Development and test of a prototype system for a limited part of an accident and emergency organisation to demonstrate the potential use of computer and communication systems, data-base and knowledge base technology, and applications of expert systems and methods used in artificial intelligence. 5) Production of guidelines for the introduction of advanced information technology in the organisations based on evaluation and validation of the prototype system. (author)
Harmonic analysis of occupational-accident time-series as a part of the quantified risk evaluation in worksites: Application on electric power industry and construction sector
International Nuclear Information System (INIS)
The development of an integrated risk analysis scheme, which will combine a well-considered selection of widespread techniques, would enable the companies to achieve efficient results on risk assessment. In this study, we develop a methodological framework (as a part of the quantified risk evaluation), by incorporating a new technique, that is implemented by the harmonic-analysis of time-series of occupational-accidents (called as HATS). Our objective is therefore, twofold: (i) the development of a new risk assessment framework (HATS technique) and the subsequent application of HATS on the worksites of electric power industry and construction sector, and (ii) the enrichment of the harmonic-analysis theoretical background, as far as the significance-level of spectral peaks is concerned, with fully-completed practical tables, that they have been produced by using the scientific literature. In fact, we apply HATS on occupational-accident time-series, which were (a) observed in the worksites of the Greek Public electric Power Corporation (PPC) and the Greek construction-companies (GCCs), and (b) recorded in great statistical-databases of PPC, and IKA (the Greek Social Insurance Institute/Ministry of Health), respectively. The results of HATS were tested statistically by using Shimshoni's significance-test. Moreover, the results of the comparative time/frequency-domain analysis of the accident time-series in PPC (for 1993–2009) and GCCs (for 1999–2007), prove that they are characterized by the existence of a periodic factor which (a) constitutes a permanent feature for the dynamic behavior of PPC's and GCCs' OHSS (occupational health and safety system), and (b) could be taken into account by risk managers in risk assessment, i.e., immediate suppressive measures must be taken place to abolish the danger source which is originated from the quasi-periodic appearance of the most important hazard sources
Directory of Open Access Journals (Sweden)
Rajković Miloš B.
Full Text Available Sulfuric acid is an important industrial and strategic raw material, the production of which is developing on all continents, in many factories in the world and with an annual production of over 160 million tons. On the other hand, the production, transport and usage are very dangerous and demand measures of precaution because the consequences could be catastrophic, and not only at the local level where the accident would happen. Accidents that have been publicly recorded during the last eighteen years (from 1988 till the beginning of 2006 are analyzed in this paper. It is very alarming data that, according to all the recorded accidents, over 1.6 million tons of sulfuric acid were exuded. Although water transport is the safest (only 16.38% of the total amount of accidents in that way 98.88% of the total amount of sulfuric acid was exuded into the environment. Human factor was the common factor in all the accidents, whether there was enough control of the production process, of reservoirs or transportation tanks or the transport was done by inadequate (old tanks, or the accidents arose from human factor (inadequate speed, lock of caution etc. The fact is that huge energy, sacrifice and courage were involved in the recovery from accidents where rescue teams and fire brigades showed great courage to prevent real environmental catastrophes and very often they lost their lives during the events. So, the phrase that sulfuric acid is a real "environmental bomb" has become clearer.
Persistence of airline accidents.
Barros, Carlos Pestana; Faria, Joao Ricardo; Gil-Alana, Luis Alberiko
This paper expands on air travel accident research by examining the relationship between air travel accidents and airline traffic or volume in the period from 1927-2006. The theoretical model is based on a representative airline company that aims to maximise its profits, and it utilises a fractional integration approach in order to determine whether there is a persistent pattern over time with respect to air accidents and air traffic. Furthermore, the paper analyses how airline accidents are related to traffic using a fractional cointegration approach. It finds that airline accidents are persistent and that a (non-stationary) fractional cointegration relationship exists between total airline accidents and airline passengers, airline miles and airline revenues, with shocks that affect the long-run equilibrium disappearing in the very long term. Moreover, this relation is negative, which might be due to the fact that air travel is becoming safer and there is greater competition in the airline industry. Policy implications are derived for countering accident events, based on competition and regulation.
Radiological accidents: education for prevention and confrontation
International Nuclear Information System (INIS)
The purpose of this work is to train and inform on radiological accidents as a preventive measure to improve the people life quality. Radiological accidents are part of the events of technological origin which are composed of nuclear and radiological accidents. As a notable figure is determined that there have been 423 radiological accidents from 1944 to 2005 and among the causes prevail industrial accidents, by irradiations, medical accidents and of laboratories, among others. Latin American countries such as Argentina, Brazil, Mexico and Peru are some where most accidents have occurred by radioactivity. The radiological accidents can have sociological, environmental, economic, social and political consequences. In addition, there are scenarios of potential nuclear accidents and in them the potential human consequences. Also, the importance of the organization and planning in a nuclear emergency is highlighted. Finally, the experience that Cuba has lived on the subject of radiological accidents is described
International Nuclear Information System (INIS)
On 27 May 1986 the Norwegian government appointed an inter-ministerial committee of senior officials to prepare a report on experiences in connection with the Chernobyl accident. The present second part of the committee's report describes proposals for measures to prevent and deal with similar accidents in the future. The committee's evaluations and proposals are grouped into four main sections: Safety and risk at nuclear power plants; the Norwegian contingency organization for dealing with nuclear accidents; compensation issues; and international cooperation
Lind, M G; Wollin, S
Information concerning 520 bicycle accidents and their victims was obtained from medical records and the victims' replies to questionnaires. The analyzed aspects included risk of injury, completeness of accident registrations by police and in hospitals, types of injuries and influence of the cyclists' age and sex, alcohol, fatigue, hunger, haste, physical disability, purpose of cycling, wearing of protective helmet and other clothing, type and quality of road surface, site of accident (road junctions, separate cycle paths, etc.) and turning manoeuvres.
Manual for the classification and prioritization of risks due to major accidents in process and related industries
International Nuclear Information System (INIS)
This document presents, in fact, a third generation or ranking methods. The first generation, an inventory procedure, was developed by D. van den Brand for the province of South Holland and is only available in Dutch. The second generation was developed by TNO Environmental and Energy Research, Netherlands, on request and was mainly based on the ideas of D. van den Brand, representative of the governmental body in the Netherlands. This second generation guideline has been translated into several languages and is called The Guide to Hazardous Industrial Activities. The present document is the third generation; although using much of the same technical data, it has its own purpose and various important additions as well as a so-called step by step approach not used in earlier work. 10 figs, 20 tabs
Department of Homeland Security — Accident statistics available on the Coast Guard's website by state, year, and one variable to obtain tables and/or graphs. Data from reports has been loaded for...
International Nuclear Information System (INIS)
This study by the Steel Industry Safety and Health Commission was made within the context of the application by undertakings of the principles of accident and disease prevention previously adopted by the said Commission. It puts forward recommendations for the effective and gradual implementation of a programme of action on occupational health and safety in the various departments of an undertaking and in the undertaking as a whole. The methods proposed in this study are likely to be of interest to all undertakings in the metallurgical industry and other industrial sectors
Le Docteur Kiebel, chirurgien à Genève, est aussi un grand ami de sport et de temps en temps médecin des classes genevoises de ski et également médecin de l'équipe de hockey sur glace de Genève Servette. Il est bien qualifié pour nous parler d'accidents de sport et surtout d'accidents de ski.
化工事故处置中消防污水产生的原因及防控对策%Manage of Fire Waste Water in the Disposition of Chemical Industry Accident
Institute of Scientific and Technical Information of China (English)
If there is fire disaster or dangerous chemical leakage accident in chemical industry enterprise, harmful material often leaks. Water was used to dispose such accidents and it is easy to mix with leaking materials and products of chemical industry. This paper introduced the characteristics of fire waste water in chemical industry accident, and proposed the prevention and control measures to reduce the pollution of environment.% 化工企业一旦发生火灾或危险化学品泄漏事故,物料就会泄漏出来。消防部队在化工事故处置中都离不开水,这些水落地后极易与泄漏的化工原料、化工产品混合后形成消防污水。本文通过阐明化工事故处置中消防污水的特点,提出了消防污水的预防控制对策,以减少对环境中水体的污染。
加强电力行业安全管理减少安全事故发生%Strengthening Safety Management of Electric Power Industry to Reduce Safety Accidents
Institute of Scientific and Technical Information of China (English)
电力行业发展到今天,法律法规,规章制度,劳动纪律,技术规程,安全措施,已相当严密完善,但由于位于中心的"人"的失误造成事故仍时有发生,许多事故造成很惨痛的后果.事故的发生往往是猝不及防,有些事故不该发生,分析各种事故案例,发现大量事故都是由于事故责任人心存侥幸心理、冒险心理、麻痹心理,图快、图省事等原因造成违反规程,酿成惨祸.安全工作是一项只有起点没有终点的工作.安全事故的发生,与有关人员思想不重视、工作不落实、制度不坚持、责任不到位有很大关系.养成好的工作习惯,安全从点滴做起,从细节做起.%With the development of electric power industry, laws and regulations, rules and regulations, labor discipline, technical procedures, and safety measures have been sound. The accidents caused by human being mistake are increased, and many accidents are very disastrous. The accident is often sudden, and many accidents are avoidable. Through analyzing the accidents, the authors find that most of accidents are caused by the operator with fluke mind. Safety management work is constant. At last, the paper puts forward the measures such as developing good habit about work, be careful and serious about work.
Directory of Open Access Journals (Sweden)
Gloria Isabel Carvajal Peláez
Full Text Available Los accidentes laborales suponen importantes costos humanos y económicos para la empresa, el accidentado y la sociedad. Generalmente, representan una gran repercusión económica negativa para las empresas del sector de la construcción, las cuales soportan un costo mayor del que se refleja debido a la gran cantidad de variables ocultas que se desconocen. Dado que hasta ahora la evaluación de los costos generados por los accidentes laborales ha tenido lugar mediante el desarrollo de métodos muy dispares entre sí, y según Durán [1], no se ha hecho ningún tipo de evaluación económica que estime de manera exhaustiva el costo de los daños a la salud relacionados con el trabajo, en esta comunicación, se presenta mediante un modelo matemático de aplicación al sector de la construcción español, que el costo de los accidentes laborales es el consumo de recursos materiales y humanos derivados del aseguramiento, la prevención y los siniestros.Work-related accidents involve significant human and economic costs for the companies, people, and society. Said accidents usually represent a great negative economic impact for the construction industries, which support a higher cost than reflected due to the large amount of hidden variables are unknown. Until now, the evaluation of the costs generated by labor accidents has been based on the development of very different methods and, as Duran [1] has not made any kind of economic assessment that comprehensively considers the economic cost of damage to health associated with work, this paper present a mathematical model applicable to the Spain construction industry, that the cost of labor accidents, is the consumption of material and human resources derived from insurance, prevention and accidents.
Directory of Open Access Journals (Sweden)
R. B. Ward
Full Text Available Purpose: This author's experiences in investigating well over a hundred accident occurrences has led to questioning how such events can be managed - - - while immediately recognising that the idea of managing accidents is an oxymoron, we don't want to manage them, we don't want not to manage them, what we desire is not to have to manage not-them, that is, manage matters so they don't happen and then we don't have to manage the consequences.Design/methodology/approach: The research will begin by defining some common classes of accidents in manufacturing industry, with examples taken from cases investigated, and by working backwards (too late, of course show how those involved could have managed these sample events so they didn't happen, finishing with the question whether any of that can be applied to other situations.Findings: As shown that the management actions needed to prevent accidents are control of design and application of technology, and control and integration of people.Research limitations/implications: This paper has shown in some of the examples provided, management actions have been know to lead to accidents being committed by others, lower in the organization.Originality/value: Today's management activities involve, generally, the use of technology in many forms, varying from simple tools (such as knives to the use of heavy equipment, electric power, and explosives. Against these we commit, in control of those items, the comparatively frail human mind and body, which, again generally, does succeed in controlling these resources, with (another generality by appropriate management. However, sometimes the control slips and an accident occurs.
Exploratory analysis of Spanish energetic mining accidents.
Sanmiquel, Lluís; Freijo, Modesto; Rossell, Josep M
Using data on work accidents and annual mining statistics, the paper studies work-related accidents in the Spanish energetic mining sector in 1999-2008. The following 3 parameters are considered: age, experience and size of the mine (in number of workers) where the accident took place. The main objective of this paper is to show the relationship between different accident indicators: risk index (as an expression of the incidence), average duration index for the age and size of the mine variables (as a measure of the seriousness of an accident), and the gravity index for the various sizes of mines (which measures the seriousness of an accident, too). The conclusions of this study could be useful to develop suitable prevention policies that would contribute towards a decrease in work-related accidents in the Spanish energetic mining industry. PMID:22721539
International Nuclear Information System (INIS)
First, R.M.B.K type reactors are described. Then, safety problems are dealt with reactor control, behavior during transients, normal loss of power and behavior of the reactor in case of leak. A possible scenario of the accident of Tchernobyl is proposed: events before the explosion, possible initiators, possible scenario and events subsequent to the core meltdown (corium-concrete interaction, interaction with the groundwater table). An estimation of the source term is proposed first from the installation characteristics and the supposed scenario of the accident, and from the measurements in Europe; radiological consequences are also estimated. Radioactivity measurements (Europe, Scandinavia, Western Europe, France) are given in tables (meteorological maps and fallouts in Europe). Finally, a description of the site is given
There is no left turn to Point 1 from the customs, direction CERN. A terrible accident happened last week on the Route de Meyrin just outside Entrance B because traffic regulations were not respected. You are reminded that when travelling from the customs, direction CERN, turning left to Point 1 is forbidden. Access to Point 1 from the customs is only via entering CERN, going down to the roundabout and coming back up to the traffic lights at Entrance B
International Nuclear Information System (INIS)
Predicting the possible consequences of transportation accidents provides a severe challenge to an analyst who must make a judgment of the likely consequences of a release event at an unpredictable time and place. Since it is impractical to try to obtain detailed knowledge of the meteorology and terrain for every potential accident location on a route or to obtain accurate descriptions of population distributions or sensitive property to be protected (data which are more likely to be more readily available when one deals with fixed-site problems), he is constrained to make conservative assumptions in response to a demanding public audience. These conservative assumptions are frequently offset by very small source terms (relative to a fixed site) created when a transport vehicle is involved in an accident. For radioactive materials, which are the principal interest of the authors, only the most elementary models have been used for assessing the consequences of release of these materials in the transportation setting. Risk analysis and environmental impact statements frequently have used the Pasquill-Gifford/gaussian techniques for releases of short duration, which are both simple and easy to apply and require a minimum amount of detailed information. However, after deciding to use such a model, the problem of selecting what specific parameters to use in specific transportation situations still presents itself. Additional complications arise because source terms are not well characterized, release rates can be variable over short and long time periods, and mechanisms by which source aerosols become entrained in air are not always obvious. Some approaches that have been used to address these problems will be reviewed with emphasis on guidelines to avoid the Worst-Case Scenario Syndrome
International Nuclear Information System (INIS)
A peruvian man, victim of an important accidental irradiation arrived on the Saturday twenty ninth of may 1999 to the centre of treatment of serious burns at the Percy military hospital (Clamart -France). The accident spent on the twentieth of February 1999, on the site of a hydroelectric power plant, in construction at 300 km at the East of Lima. The victim has picked up an industrial source of iridium devoted to gamma-graphy operations and put it in his back pocket; of trousers. The workman has serious radiation burns. (N.C.)
The dominance of accidents caused by banalities
DEFF Research Database (Denmark)
Jørgensen, Kirsten
Most prevention analysis is focused on high risks, such as explosion, fire, lack of containment for chemicals, crashes in transportation systems, lack of oxygen, or chemical poisoning. In the industrial world, these kinds of risk still lead to incidents with huge consequences, albeit very seldom...... on accidents could reveal the kind of accidents we are talking about, where they happen, to whom, how, and what can be done about them. This would require a special registration system of the events leading up to the accident. The main results for the four most frequent types of accident will be described...
International Nuclear Information System (INIS)
This chapter of the environmental control report deals with the environmental impact of the industry in Austria. It gives a review of the structure and types of the industry, the legal framework and environmental policy of industrial relevance. The environmental situation of the industry in Austria is analyzed in detail, concerning air pollution (SO2, NOx, CO2, CO, CH4, N2O, NH3, Pb, Cd, Hg, dioxin, furans), waste water, waste management and deposit, energy and water consumption. The state of the art in respect of the IPPC-directives (European Integrated Pollution Prevention and Control Bureau) concerning the best available techniques of the different industry sectors is outlined. The application of European laws and regulations in the Austrian industry is described. (a.n.)
A Comparison of the Effects of the Chernobyl and Three Mile Island Nuclear Accidents on the U.S. Electric Utility Industry
AKTAR, İsmail
We examined the stock market reaction to two nuclear accidents, the Three Mile Island incident and the Chernobyl disaster. We were interested in determining whether the negative stock market reaction following these events was consistently related to the level of nuclear exposure by each firm and whether the negative reaction was reasonably linked to human safety concerns. Prior research has shown that following TMI, but anomalously not Chernobyl, firms with the more nuclear capacity experien...
Estimating the frequency of nuclear accidents
Raju, Suvrat
We used Bayesian methods to compare the predictions of probabilistic risk assessment -- the theoretical tool used by the nuclear industry to predict the frequency of nuclear accidents -- with empirical data. The existing record of accidents with some simplifying assumptions regarding their probability distribution is sufficient to rule out the validity of the industry's analyses at a very high confidence level. We show that this conclusion is robust against any reasonable assumed variation of...
Reactor accident-big impacts but small possibilities
International Nuclear Information System (INIS)
Accidents are an unfortunate incident that happened in our lives. The government provides facilities and programs to reduce accidents; people also take a variety of initiatives that accidents can be avoided, and every family and its members are constantly vigilant to protect against accidents. Some industries are relatively simple operations are recorded accidents is higher than other industries is more complex and sophisticated. Authors relate this fact with the accident that occurred in the area where the power generation plant according to author accidents in this area is very small and grouped as isolated cases. This article also commented on two major accidents in nuclear power generation are Chernobyl and Three Miles Island. Authors also hope that the progress of current and future technology can overcome this problem and then convince the public that nuclear energy is safe and low risk.
The Chernobyl accident consequences; Consequences de l'accident de Tchernobyl
Energy Technology Data Exchange (ETDEWEB)
Five teen years later, Tchernobyl remains the symbol of the greater industrial nuclear accident. To take stock on this accident, this paper proposes a chronology of the events and presents the opinion of many international and national organizations. It provides also web sites references concerning the environmental and sanitary consequences of the Tchernobyl accident, the economic actions and propositions for the nuclear safety improvement in the East Europe. (A.L.B.)
Accidents Preventive Practice for High-Rise Construction
Goh Kai Chen; Goh Hui Hwang; Omar Mohd Faizal; Toh Tien Choon; Mohd Zin Abdullah Asuhaimi
The demand of high-rise projects continues to grow due to the reducing of usable land area in Klang Valley, Malaysia. The rapidly development of high-rise projects has leaded to the rise of fatalities and accidents. An accident that happened in a construction site can cause serious physical injury. The accidents such as people falling from height and struck by falling object were the most frequent accidents happened in Malaysian construction industry. The continuous growth of high-rise buildi...
International Nuclear Information System (INIS)
This chapter discusses the role-plays by nuclear technology to enhance productivity in industry. Some of the techniques, Non-Destructive Testing (NDT) - x, gamma, electron and neutron radiography, nuclear gauges, materials characterization are discussed thoroughly
Corporate Cost of Occupational Accidents
DEFF Research Database (Denmark)
Rikhardsson, Pall M.; Impgaard, M.
for a company with 3.600 employees was estimated to approximately US$ 682.000. The paper includes an introduction regarding accident cost analysis in companies, a presentation of the SACA project methodology and the SACA method itself, a short overview of some of the results of the SACA project and a conclusion......The systematic accident cost analysis (SACA) project was carried out during 2001 by The Aarhus School of Business and PricewaterhouseCoopers Denmark with financial support from The Danish National Working Environment Authority. Its focused on developing and testing a method for evaluating...... occupational costs of companies for use by occupational health and safety professionals. The method was tested in nine Danish companies within three different industry sectors and the costs of 27 selected occupational accidents in these companies were calculated. One of the main conclusions is that the SACA...
Analysis of Fukushima Daiichi Accident Using HFACS
Energy Technology Data Exchange (ETDEWEB)
Mohamed, Saeed Almheiri [Korea Advanced Institue of Science and Technology, Daejeon (Korea, Republic of)
The shadow of Fukushima Daiichi nuclear power plant (NPP) accident is still too big and will last long. On the other hand, it could still teach us lots of lessons to better design and operate nuclear power plants. In this paper, we will be focusing on the Fukushima Daiichi accident, especially on human organizational factors. We will analyze the accident using Human Factors Analysis and Classification System (HFACS) in order to better understand the organizational climate of TEPCO{sup 1} and NISA{sup 2} that led to Fukushima Daiichi Accident. HFACS was developed for the U. S. aviation industry and has been used at many industries like the rail and mining industries. We found that the HFACS to be greatly beneficial in investigating the latent and organizational causes for the accident. The application results show that the causes of Fukushima Daiichi accident were spread out from sharp end (i.e. Unsafe Act) to blunt end (i. e. Organizational Influences). This means that the corresponding countermeasures should cover from front line staff to management. Thus, we managed to develop a better understanding on how to prevent similar errors or violations. The incident and near-miss have a lot of helpful information because it may show the actual and latent deficiencies of complex systems. We applied the HFACS into Fukushima Daiichi accident to better locate the causes related to both sharp and blunt ends of operation of NPP. In order to derive useful lessons from the accident analysis, the analyst should try to find the similarities not differences from the incident. It is imperative that whatever accident/incident analysis systems we use, we should fully utilize the disastrous Fukushima accident.
Energy Technology Data Exchange (ETDEWEB)
Bernstein, Lenny; Roy, Joyashree; Delhotal, K. Casey; Harnisch, Jochen; Matsuhashi, Ryuji; Price, Lynn; Tanaka, Kanako; Worrell, Ernst; Yamba, Francis; Fengqi, Zhou; de la Rue du Can, Stephane; Gielen, Dolf; Joosen, Suzanne; Konar, Manaswita; Matysek, Anna; Miner, Reid; Okazaki, Teruo; Sanders, Johan; Sheinbaum Parado, Claudia
This chapter addresses past, ongoing, and short (to 2010) and medium-term (to 2030) future actions that can be taken to mitigate GHG emissions from the manufacturing and process industries. Globally, and in most countries, CO{sub 2} accounts for more than 90% of CO{sub 2}-eq GHG emissions from the industrial sector (Price et al., 2006; US EPA, 2006b). These CO{sub 2} emissions arise from three sources: (1) the use of fossil fuels for energy, either directly by industry for heat and power generation or indirectly in the generation of purchased electricity and steam; (2) non-energy uses of fossil fuels in chemical processing and metal smelting; and (3) non-fossil fuel sources, for example cement and lime manufacture. Industrial processes also emit other GHGs, e.g.: (1) Nitrous oxide (N{sub 2}O) is emitted as a byproduct of adipic acid, nitric acid and caprolactam production; (2) HFC-23 is emitted as a byproduct of HCFC-22 production, a refrigerant, and also used in fluoroplastics manufacture; (3) Perfluorocarbons (PFCs) are emitted as byproducts of aluminium smelting and in semiconductor manufacture; (4) Sulphur hexafluoride (SF{sub 6}) is emitted in the manufacture, use and, decommissioning of gas insulated electrical switchgear, during the production of flat screen panels and semiconductors, from magnesium die casting and other industrial applications; (5) Methane (CH{sub 4}) is emitted as a byproduct of some chemical processes; and (6) CH{sub 4} and N{sub 2}O can be emitted by food industry waste streams. Many GHG emission mitigation options have been developed for the industrial sector. They fall into three categories: operating procedures, sector-wide technologies and process-specific technologies. A sampling of these options is discussed in Sections 7.2-7.4. The short- and medium-term potential for and cost of all classes of options are discussed in Section 7.5, barriers to the application of these options are addressed in Section 7.6 and the implication of
The importance of the treatment of the unsafe acts for the prevention of accidents in petrochemical industry; A importancia do tratamento dos atos inseguros para a prevencao de acidentes na industria petroquimica
Energy Technology Data Exchange (ETDEWEB)
Meneguetti, Alexander A.; Santos, Helio R.F.; Alevato, Hilda; Lima, Luciana S. [Dupont do Brasil S.A., Paulinia, SP (Brazil)
Due to the fact that, the workers' behavior is characterized by its complexity and diversity, this issue has been seen as a great 'black box' in discussions regarding the Management Systems of SHE. Associated with this issue other arises: How conscious people? How to engage them with the process? How to improve the risk control? How to motivate the prevention? Most of these responses are discussed in the Social and Human Sciences for many years. However, it is necessary to closer the technical-operational knowledge and the human aspects, applying in the organizations' daily work, to make the working environment more safe. The purpose of this study, therefore, is examining the possibility of reducing accidents through the identification and treatment of deviations (unsafe acts and unsafe conditions), cause the whole accident, be it serious or not, begins with a small deviation. It was used as a reference tool, the Behavior audit and it is based on field's observations, applied into a production unit of a large petrochemical industry in northern Brazil, during the years 2006 and 2007. (author)
Learning lessons from Natech accidents - the eNATECH accident database
Krausmann, Elisabeth; Girgin, Serkan
When natural hazards impact industrial facilities that house or process hazardous materials, fires, explosions and toxic releases can occur. This type of accident is commonly referred to as Natech accident. In order to prevent the recurrence of accidents or to better mitigate their consequences, lessons-learned type studies using available accident data are usually carried out. Through post-accident analysis, conclusions can be drawn on the most common damage and failure modes and hazmat release paths, particularly vulnerable storage and process equipment, and the hazardous materials most commonly involved in these types of accidents. These analyses also lend themselves to identifying technical and organisational risk-reduction measures that require improvement or are missing. Industrial accident databases are commonly used for retrieving sets of Natech accident case histories for further analysis. These databases contain accident data from the open literature, government authorities or in-company sources. The quality of reported information is not uniform and exhibits different levels of detail and accuracy. This is due to the difficulty of finding qualified information sources, especially in situations where accident reporting by the industry or by authorities is not compulsory, e.g. when spill quantities are below the reporting threshold. Data collection has then to rely on voluntary record keeping often by non-experts. The level of detail is particularly non-uniform for Natech accident data depending on whether the consequences of the Natech event were major or minor, and whether comprehensive information was available for reporting. In addition to the reporting bias towards high-consequence events, industrial accident databases frequently lack information on the severity of the triggering natural hazard, as well as on failure modes that led to the hazmat release. This makes it difficult to reconstruct the dynamics of the accident and renders the development of
高校学生顶岗实习工伤事故的法律责任问题探析%Analysis on Law Responsibility Problems of Internship Industrial Accident of University Students
Institute of Scientific and Technical Information of China (English)
That college students' personal injury accidents which occurs in internship work should be taken charge by whom is not determined, the main reason is that the special identity of the student is difficult to locate accurately. In judicial practice, most of them adopt "what students say", therefore, such industrial accidents do not suit to the labor law of Labor Law, Labor Con- tract Law and Regulations on Work Injury Insurance. In present General Principles of Civil Law and other laws and regulations, there are no specific requirements. Reasonable solution to the responsibility of such accidents at work, "what employees say" fit to current actual situation. The national legislative branch should complement and improve the relevant provisions of labor laws and regulations, clearly stipulate the internship work in personal injury accident liability assumed by the practice unit when the court accepts such cases, it should compare with the related judicial interpretatrion processing which employees suffer from a personal injury while they are engaged in employment activities.%高校学生顶岗实习工作中发生人身伤害事故由谁担责无从确定,主要是因为实习学生的特殊身份难以准确定位。目前司法实践中大都采纳"学生说",所以,此类工伤事故不适用《劳动法》、《劳动合同法》和《工伤保险条例》等劳动类法律法规,而现行的《民法通则》等法律法规也没有相应的具体规定。合理解决这类工伤事故的责任承担,"雇工说"比较切合目前的实际情形。国家立法部门应该补充和完善劳动法律法规的相关规定,明确规定顶岗实习工作中人身伤害事故的责任由实习单位承担,目前法院受理此类案件应当比照雇工从事雇佣活动中遭受人身损害的相关司法解释处理。
Empirical Study of the Use and Exploitation of TAPE- Accident Reporting and Monitoring Program in Elder Care in Kouvola (accident project)
Baez, Nina
Elder people accident prevention starts from systematic collection of accident information. Health care still lacks behind industries in accident reporting. Accident prevention is part of quality care which is expected by health care law (2010/1326). The thesis aimed to assess the views of health care workers at home care, assisted living, higher-level care, and nursing homes about the usability, usefulness, and exploitation of TAPE-accident reporting and monitoring system. The purpose is...
化工园区初始火灾爆炸引发连锁事故概率研究%Probability of the chain-fire accidents originated from the explosion in chemical industry parks
Institute of Scientific and Technical Information of China (English)
王洪德; 崔铁军
The paper is inclined to present a simulated model for predicting the probability of chain-fire accidents caused by the explosion in chemical industry parks based on the analysis of the fire and explosion liability of the oil tanks over there. Careful study of the Domino Effect of the accidents helps us to confirm that the main physical effects of the chain accidents taking place in such parks are the explosion of incontrollable vapor clouds and the pool fires. To make the problem clearer, we have drawn the curves of the shock-waves in relation with the accident distance and the heat radiation with the distance by using MATLAB technology. At the same time, we have also worked out the probability curve of the overpressure with the damage, and that of the heat radiation with the damage. The fitting of the two groups of curves has enabled us to establish the connection between the objective hazardous sources affected and the original hazardous sources themselves, which may in turn promote the building-up of the connection between the hazardous material sources with the original hazardous sources, that is, the probability matrixes, on the basis of which we have worked out the accident probabilities of the hazardous oil tanks in a given affected field of the fire and the explosion. In so doing, it is possible for us to deduce the likely chain effects and the probability of the accidents in advance, which enabled us to prepare essential preventive methods. The example analysis shows that the probability of the chain accidents can be affected by the physical and chemical properties of the hazardous material sources in the field, the geographical location and the solidness of the container of the material. Corresponding relationship of the accident probabilities has been established with the MATLAB. Differences of the correspondent relationship or the accident order may in turn lead to the difference of the probabilities of the chain accidents. The above considerations may
Radiation accidents and defence of population
International Nuclear Information System (INIS)
Full text: Development of nuclear physics, the fundamental and the applied researches in the field of radioactive insured wide possibility for application of radionuclides and ionizing radiation source in the different fields of national economy. Application of radionuclides in chemical, metallurgical, food industry, in agriculture and etc. Fields provide a large economic profit. It's hard to apprise significance of ionizing radiation source using in medicine for diagnostics and treatment of different disease. Nuclear power engineering and nuclear industry are developing intensively. At same time nuclear power, ionizing radiation sources incur potential treat for surroundings and health of population. As even that stage of protective measure development: there is no possibility of that happening of radiation accidents. A radiation accident qualifies as loss of ionizing radiation sources direction, which provoked by disrepair equipment, natural calamity or other causes which could bring to unplanned irradiation of population or radioactive pollution of surroundings. At present some following typical cases connected with radiation accident have been chosen: Contentious using or keeping of ionizing radiation source with breach of established requires; Loss, theft of ionizing radiation sources or radiation plants, instruments; Leaving the sources of ionizing radiation in the holes; Refusal radiation technic exploited in industry, medicine, SRI and etc; Disrepair in nuclear transport means of conveyance; Crashes and accidents at NPP and at other enterprises of nuclear industry. The radiation accidents according to character, degree and scales have been divided into two groups: Radiation accidents not connected with NPP; Accidents in the nuclear engineering and industry; The radiation accidents not connected with NPP according their consequence divide into 5 groups; accidents which do not come to irradiation of personal, persons from population (more PN-permissible norm
Regulatory perspective on accident management issues
International Nuclear Information System (INIS)
Effective response to reactor accidents requires a combination of emergency operations, technical support and emergency response. The NRC and industry have actively pursued programs to assure the adequacy of emergency operations and emergency response. These programs will continue to receive high priority. By contrast, the technical support function has received relatively little attention from NRC and the industry. The results from numerous PRA studies and the severe accident programs of NRC and the industry have yielded a wealth of insights on prevention and mitigation of severe accidents. The NRC intends to work with the industry to make these insights available to the technical support staffs through a combination of guidance, training and periodic drills
Numerical and experimental simulation of accident processes using KMS large-scale test facility under the program of training university students for nuclear power industry
International Nuclear Information System (INIS)
The KMS large-scale test facility is being constructed at NITI site and designed to model accident processes in VVER reactor plants and provide experimental data for safety analysis of both existing and future NPPs. The KMS phase I is at the completion stage. This is a containment model of 2000 m3 volume intended for experimentally simulating heat and mass transfers of steam-gas mixtures and aerosols inside containment. The KMS phase II will incorporate a reactor model (1:27 scale) and be used for analysing a number of events including primary and secondary LOCA. The KMS program for background training of university students in the nuclear field will include preparation and conduction of experiments, analysis of experiment data. The KMS program for background training of university students in nuclear will include: participation in the development and application of experiment procedures, preparation and carrying out experiments; carrying out pretest and post-test calculations with different computer codes; on-the-job training as operators of experiment scenarios; training of specialists in measurement and information acquisition technologies. (author)
Guidelines for planning interventions against external exposure in industrial area after a nuclear accident. Pt. 2. Calculation of doses using Monte Carlo method
International Nuclear Information System (INIS)
Countermeasures being different from the usual urban ones and largely applicable in industrial area are collected and evaluated in a separate report. The industrial area is defined here as such an area where productive and/or commercial activity is carried out. A good example is a supermarket or a factory. Based on the history of calculation models it is unambiguous that the Monte Carlo based simulation is the perspective to the dose assessment from external exposures in such a complex environment. A method of the calculation of doses from external exposures in urban-industrial environment is presented. Moreover, this report gives a summary about the time dependence of the source strengths relative to a reference surface and a short overview about the mechanical and chemical intervention techniques which can be applied in this area. Using a hypothetical scenario (a supermarket area contaminated by 137Cs) the details of an exemplary calculation are given directly addressing the dose and averted dose blocks of the templates of industrial countermeasures. In addition, a sensitivity analysis of the results is presented. (orig.)
Análise de acidentes fatais na mineração: o caso da mineração no Peru Analyzes of fatal accidents in the mining industry: the case of Peruvian mining
Directory of Open Access Journals (Sweden)
Renan Collantes Candia
Full Text Available A mineração é uma das atividades industriais que oferecem maior risco; embora nos últimos anos tenham-se percebido reduções na taxa de lesões e acidentes, o seu número e grau de severidade ainda são elevados. As causas fundamentais para as altas taxas de acidentes podem ser atribuídas às condições inseguras e os atos inseguros; nesse cenário, a identificação de problemas de segurança visando à proposta de soluções efetivas para gerenciar riscos faz-se necessária. Por outro lado, a dependência de países em desenvolvimento por indústrias primárias como a mineração é evidente. Na economia peruana, aproximadamente, 16 % do PIB e mais de 50 % das exportações referem-se a esta indústria, destacando sua posição competitiva na mineração mundial. Esse artigo analisa os acidentes fatais na mineração peruana, desde o ano 2000 até maio de 2008. A fonte de informação primária foi o registro de acidentes, disponibilizado pelo Ministério de Energia e Minas do Peru; identificando-se vários tipos de acidentes com destaque para aqueles provocados por queda de rochas em minas subterrâneas. A maioria das vitimas são trabalhadores de empresas terceirizadas prestadoras de serviços especializados. Os resultados mostram que a mineração subterrânea tem maiores riscos do que a de superfície.Mining is one of the indústrial activities that offers greater risks; although in recent years, reduction in the rate of injuries and accidents has been observed, the numbers and degree of severity are high. The basic causes for the high rates can be attributed to unsafe conditions and unsafe acts; in this instance, the identification of security problems aiming to propose effective solutions becomes necessary for risk management. On the other hand, the dependence of developing countries on primary industries such as mining is evident. In the Peruvian economy, approximately 16% of the GIP and more than 50% of the exportations are
Study of industry safety management
International Nuclear Information System (INIS)
This book deals with general remarks, industrial accidents, statistics of industrial accidents, unsafe actions, making machinery and facilities safe, safe activities, having working environment safe, survey of industrial accidents and analysis of causes, system of safety management and operations, safety management planning, safety education, human engineering such as human-machines system, system safety, and costs of disaster losses. It lastly adds individual protective equipment and working clothes including protect equipment for eyes, face, hands, arms and feet.
Guidelines for planning interventions against external exposure in industrial area after a nuclear accident. Pt. 1. A holistic approach of countermeasure application
International Nuclear Information System (INIS)
Following a large-scale release of radioactivity into the environment, different urban, industrial and rural environments may be contaminated for many years. Currently, there is limited systematic consideration of long-term management to ensure sustainability of areas contaminated by long-lived radionuclides. To sustain acceptable living and working conditions in such areas it is important to be able to construct robust, effective restoration strategies which address the many different types of environment, land use and ways of life. The overall objective of the STRATEGY project (directly addressing Key Action 2: Nuclear Fission - Off-site emergency management in the Fifth Framework Programme) is to establish a decision framework to enable the selection of robust and practicable remediation strategies for Member States, which enable the long-term sustainable management of contaminated areas. The special objectives of the work carried out by GSF - Radiation Protection Institute and presented in this report was to contribute to the different urban/industrial parts of the STRATEGY project. Countermeasures being different from the usual urban ones and largely applicable in industrial area are collected and evaluated. The industrial area is defined here as such an area where productive and/or commercial activity is carried out. A good example is a supermarket or a factory. In designing restoration strategies to ensure the long-term sustainability of large and varied contaminated areas, there is a requirement to adopt a more holistic approach rather than simply selecting cost-effective countermeasures. The potentially negative consequences of restoration must be fully considered. The implementation of a remediation strategy may lead to a reduced collective dose, but increased dose to those implementing the strategies. Countermeasures may themselves generate waste and the practical consideration of disposal options has to be addressed. There is also a requirement that the
Supervisor's accident investigation handbook
International Nuclear Information System (INIS)
This pamphlet was prepared by the Environmental Health and Safety Department (EH and S) of Lawrence Berkeley Laboratory (LBL) to provide LBL supervisors with a handy reference to LBL's accident investigation program. The publication supplements the Accident and Emergencies section of LBL's Regulations and Procedures Manual, Pub. 201. The present guide discusses only accidents that are to be investigated by the supervisor. These accidents are classified as Type C by the Department of Energy (DOE) and include most occupational injuries and illnesses, government motor-vehicle accidents, and property damages of less than $50,000
Framework for accident management
International Nuclear Information System (INIS)
Accident management is an essential element of the Nuclear Regulatory Commission (NRC) Integration Plan for the closure of severe accident issues. This element will consolidate the results from other key elements; such as the Individual Plant Examination (IPE), the Containment Performance Improvement, and the Severe Accident Research Programs, in a form that can be used to enhance the safety programs for nuclear power plants. The NRC is currently conducting an Accident Management Program that is intended to aid in defining the scope and attributes of an accident management program for nuclear power plants. The accident management plan will ensure that a plant specific program is developed and implemented to promote the most effective use of available utility resources (people and hardware) to prevent and mitigate severe accidents. Hardware changes or other plant modifications to reduce the frequency of severe accidents are not a central aim of this program. To accomplish the outlined objectives, the NRC has developed an accident management framework that is comprised of five elements: (1) accident management strategies, (2) training, (3) guidance and computational aids, (4) instrumentation, and (5) delineation of decision making responsibilities. A process for the development of an accident management program has been identified using these NRC framework elements
The Relationship of Occupational Safety and Security Environment, Attitude and Behavior with Industrial Injury Accident An Empirical Study%职业安全氛围、态度、行为与工伤事故关系的实证研究
Institute of Scientific and Technical Information of China (English)
宗莹; 路铭
Occupational safety atmosphere, attitude and behavior scale is closely related to the rate of industrial injury accidents. It can be integrated to reflect the basic situation of occupational safety management, be used to evaluate the effect of industrial injury prevention. Based on the data of industrial injury accidents in 2010-2012 in Zhongshan, we investigated the baseline data of occupational safety and security environment, attitude and behavior, analyzed the potential factors related to the occurrence of industrial injury accident, therefore to provide a basis for the establishment of industrial injury prevention strategies.%职业安全氛围、态度及行为量表与工伤事故率密切相关,能够综合反映企业职业安全管理的基本状况,并能用于工伤预防的效果评价。中山市人力资源和社会保障局运用2010-2012年工伤事故的基本数据,对职业安全氛围、态度及行为进行基线调查,分析工伤事故的前因性指标的基本状况,为制定工伤预防策略提供了依据。
Assessment of light water reactor accident management programs and experience
International Nuclear Information System (INIS)
The objective of this report is to provide an assessment of the current light water reactor experience regarding accident management programs and associated technology developments. This assessment for light water reactor (LWR) designs is provided as a resource and reference for the development of accident management capabilities for the production reactors at the Savannah River Site. The specific objectives of this assessment are as follows: 1. Perform a review of the NRC, utility, and industry (NUMARC, EPRI) accident management programs and implementation experience. 2. Provide an assessment of the problems and opportunities in developing an accident management program in conjunction or following the Individual Plant Examination process. 3. Review current NRC, utility, and industry technological developments in the areas of computational tools, severe accident predictive tools, diagnostic aids, and severe accident training and simulation
Assessment of light water reactor accident management programs and experience
Energy Technology Data Exchange (ETDEWEB)
Hammersley, R.J. [Fauske and Associates, Inc., Burr Ridge, IL (United States)
The objective of this report is to provide an assessment of the current light water reactor experience regarding accident management programs and associated technology developments. This assessment for light water reactor (LWR) designs is provided as a resource and reference for the development of accident management capabilities for the production reactors at the Savannah River Site. The specific objectives of this assessment are as follows: 1. Perform a review of the NRC, utility, and industry (NUMARC, EPRI) accident management programs and implementation experience. 2. Provide an assessment of the problems and opportunities in developing an accident management program in conjunction or following the Individual Plant Examination process. 3. Review current NRC, utility, and industry technological developments in the areas of computational tools, severe accident predictive tools, diagnostic aids, and severe accident training and simulation.
Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis
Energy Technology Data Exchange (ETDEWEB)
Farmer, Mitchell T. [Argonne National Lab. (ANL), Argonne, IL (United States); Bunt, R. [Southern Nuclear, Atlanta, GA (United States); Corradini, M. [Univ. of Wisconsin, Madison, WI (United States); Ellison, Paul B. [GE Power and Water, Duluth, GA (United States); Francis, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Gabor, John D. [Erin Engineering, Walnut Creek, CA (United States); Gauntt, R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Henry, C. [Fauske and Associates, Burr Ridge, IL (United States); Linthicum, R. [Exelon Corp., Chicago, IL (United States); Luangdilok, W. [Fauske and Associates, Burr Ridge, IL (United States); Lutz, R. [PWR Owners Group (PWROG); Paik, C. [Fauske and Associates, Burr Ridge, IL (United States); Plys, M. [Fauske and Associates, Burr Ridge, IL (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rempe, J. [Rempe and Associates LLC, Idaho Falls, ID (United States); Robb, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Wachowiak, R. [Electric Power Research Inst. (EPRI), Knovville, TN (United States)
The overall objective of this study was to conduct a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of light water reactor (LWR) severe accident research, and additionally augmented by insights obtained from the Fukushima accident. The ultimate benefit of this activity is that the results can be used to refine the Department of Energy's (DOE) Reactor Safety Technology (RST) research and development (R&D) program plan to address key knowledge gaps in severe accident phenomena and analyses that affect reactor safety and that are not currently being addressed by the industry or the Nuclear Regulatory Commission (NRC).
Framework for accident management
International Nuclear Information System (INIS)
A program is being conducted to establish those attributes of a severe accident management plan which are necessary to assure effective response to all credible severe accidents and to develop guidance for their incorporation in a plant's Accident Management Plan. This program is one part of the Accident Management Research Program being conducted by the U. S. Nuclear Regulatory Commission (NRC). The approach used in establishing attributes and developing guidance includes three steps. In the first step the general attributes of an accident management plan were identified based on: (1) the objectives established for the NRC accident management program, (2) the elements of an accident management framework identified by the NRC, and (3) a review of the processes used in developing the currently used approach for classifying and analyzing accidents. For the second step, a process was defined that uses the general attributes identified from the first step to develop an accident management plan. The third step applied the process defined in the second step at a nuclear power plant to refine and develop it into a benchmark accident management plan. Step one is completed, step two is underway and step three has not yet begun
Manual for the classification and prioritization of risks due to major accidents in process and related industries. Inter-Agency programme on the assessment and management of health and environmental risks from energy and other complex industrial systems
International Nuclear Information System (INIS)
The IAEA, the United Nations Environment Programme (UNEP), the United Nations Industrial Development Organization (UNIDO) and the World Health Organization (WHO) decided in 1986 to join forces in order to promote the use of integrated areas wide approaches to risk management. The Inter-Agency Programme brings together expertise in health, the environment, industry and energy, all vital for effective risk management. The purpose of the Inter-Agency Programme is to develop a broad approach to the identification, prioritization and minimization of industrial hazards in a given geographical area. This is one of a series of publications intended to be issued on behalf of the four participating UN organizations. This is the first revision of the original report, distributed in December 1993. The revision was undertaken in the light of experience with the original edition and was prompted by the wish to add the results of a practical case study and some new developments. 13 figs, 23 tabs
Planning for the Handling of Radiation Accidents
International Nuclear Information System (INIS)
The developing atomic energy programmes and the widespread use of radiation sources in medicine, agriculture, industry and research have had admirable safety records. Throughout the world the number of known accidents in which persons have been exposed to harmful am ounts of ionizing radiation is relatively small, and only a few deaths have occurred. Meticulous precautions are being taken to maintain this good record in all work with radiation sources and to keep the exposure of persons as low as practicable. In spite of all the precautions that are taken, accidents may occur and they may be accompanied by the injury or death of persons and damage to property. It is only prudent to take those steps that are practicable to prevent accidents and to plan in advance the emergency action that would limit the injuries and damage caused by those accidents that do occur. Emergency plans should be sufficiently broad to cover unforeseen or very improbable accidents as well as those that are considered credible. Some accidents may involve only the workers in an establishment, those working directly with the source and possibly their colleagues. Other accidents may have consequences, notably in the form of radioactive contamination of the environment, that affect the general public, possibly far from the site of the accident. The preparation of plans for dealing with radiation accidents is therefore obligatory both for the various authorities that are responsible for protecting the health and the food and water supplies of the public, and for the operator of an installation containing radiation sources.
46 CFR 28.900 - Post accident inspection.
... 46 Shipping 1 2010-10-01 2010-10-01 false Post accident inspection. 28.900 Section 28.900 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY UNINSPECTED VESSELS REQUIREMENTS FOR COMMERCIAL FISHING INDUSTRY VESSELS Aleutian Trade Act Vessels § 28.900 Post accident inspection. The requirements...
Laser accidents: Being Prepared
Energy Technology Data Exchange (ETDEWEB)
Barat, K
The goal of the Laser Safety Officer and any laser safety program is to prevent a laser accident from occurring, in particular an injury to a person's eyes. Most laser safety courses talk about laser accidents, causes, and types of injury. The purpose of this presentation is to present a plan for safety offices and users to follow in case of accident or injury from laser radiation.
Nuclear accidents and epidemiology
International Nuclear Information System (INIS)
A consultation on epidemiology related to the Chernobyl accident was held in Copenhagen in May 1987 as a basis for concerted action. This was followed by a joint IAEA/WHO workshop in Vienna, which reviewed appropriate methodologies for possible long-term effects of radiation following nuclear accidents. The reports of these two meetings are included in this volume, and cover the subjects: 1) Epidemiology related to the Chernobyl nuclear accident. 2) Appropriate methodologies for studying possible long-term effects of radiation on individuals exposed in a nuclear accident. Figs and tabs
The Tokaimura Nuclear Accident: A Tragedy of Human Errors.
Ryan, Michael E.
Discusses nuclear power and the consequences of a nuclear accident. Covers issues ranging from chemical process safety to risk management of chemical industries to the ethical responsibilities of the chemical engineer. (Author/ASK)
Applying Functional Modeling for Accident Management of Nuclear Power Plant
DEFF Research Database (Denmark)
Lind, Morten; Zhang, Xinxin
The paper investigate applications of functional modeling for accident management in complex industrial plant with special reference to nuclear power production. Main applications for information sharing among decision makers and decision support are identified. An overview of Multilevel Flow...
Applying Functional Modeling for Accident Management of Nucler Power Plant
DEFF Research Database (Denmark)
Lind, Morten; Zhang, Xinxin
The paper investigates applications of functional modeling for accident management in complex industrial plant with special reference to nuclear power production. Main applications for information sharing among decision makers and decision support are identified. An overview of Multilevel Flow...
Directory of Open Access Journals (Sweden)
Full Text Available
Introduction. Car accident mortality is the third order causes of death in the USA, following cardiovascular diseases and cancers. Given present survival and outcome Iranian data, more than 14,000 patients die annually in road accidents. Having a valid and reliable data could be useful in reduce mortality and morbidity reduction.
Energy Technology Data Exchange (ETDEWEB)
Zaitsev, S.L.; Tsygankov, A.V.
This paper evaluates influence of selected personal factors on accident rate in underground coal mines in the USSR. Investigations show that so-called organizational factors cause from 80 to 85% of all accidents. About 70% of the organizational factors is associated with social, personal and economic features of personnel. Selected results of the investigations carried out in Donbass mines are discussed. Causes of miner dissatisfaction are reviewed: 14% is caused by unsatisfactory working conditions, 21% by repeated machine failures, 16% by forced labor during days off, 14% by unsatisfactory material supply, 16% by hard physical labor, 19% by other reasons. About 25% of miners injured during work accidents are characterized as highly professionally qualified with automatic reactions, and about 41% by medium qualifications. About 60% of accidents is caused by miners with less than a 3 year period of service. About 15% of accidents occurs during the first month after a miner has returned from a leave. More than 30% of accidents occurs on the first work day after a day or days off. Distribution of accidents is also presented: 19% of accidents occurs during the first 2 hours of a shift, 36% from the second to the fourth hour, and 45% occurs after the fourth hour and before the shift ends.
Accident investigation and analysis
Kampen, J. van; Drupsteen, L.
Many organisations and companies take extensive proactive measures to identify, evaluate and reduce occupational risks. However, despite these efforts things still go wrong and unintended events occur. After a major incident or accident, conducting an accident investigation is generally the next ste
Quality function deployment applied to local traffic accident reduction.
Sohn, S Y
One of the major tasks of police stations is the management of local road traffic accidents. Proper prevention policy which reflects the local accident characteristics could immensely help individual police stations in decreasing various severity levels of road traffic accidents. In order to relate accident variation to local driving environmental characteristics, we use both cluster analysis and Poisson regression. The fitted result at the level of each cluster for each type of accident severity is utilized as an input to quality function deployment. Quality function deployment (QFD) has been applied to customer satisfaction in various industrial quality improvement settings, where several types of customer requirements are related to various control factors. We show how QFD enables one to set priorities on various road accident control policies to which each police station has to pay particular attention.
International Nuclear Information System (INIS)
The serious danger present tailing dumps of functioning and closed mineral resource industry in consequence of their weak security from natural disasters, proximity to water-ways, towns and state boundaries and also considering of past accidents
Management of severe accidents
International Nuclear Information System (INIS)
The definition and the multidimensionality aspects of accident management have been reviewed. The suggested elements in the development of a programme for severe accident management have been identified and discussed. The strategies concentrate on the two tiered approaches. Operative management utilizes the plant's equipment and operators capabilities. The recovery managment concevtrates on preserving the containment, or delaying its failure, inhibiting the release, and on strategies once there has been a release. The inspiration for this paper was an excellent overview report on perspectives on managing severe accidents in commercial nuclear power plants and extending plant operating procedures into the severe accident regime; and by the most recent publication of the International Nuclear Safety Advisory Group (INSAG) considering the question of risk reduction and source term reduction through accident prevention, management and mitigation. The latter document concludes that 'active development of accident management measures by plant personnel can lead to very large reductions in source terms and risk', and goes further in considering and formulating the key issue: 'The most fruitful path to follow in reducing risk even further is through the planning of accident management.' (author)
Accidents, risks and consequences
International Nuclear Information System (INIS)
Although the accident at Chernobyl can be considered as the worst accident in the world, it could have been worse. Other far worse situations are considered, such as a nuclear weapon hitting a nuclear reactor. Indeed the accident at Chernobyl is compared to a nuclear weapon. The consequences of Chernobyl in terms of radiation levels are discussed. Although it is believed that a similar accident could not occur in the United Kingdom, that possibility is considered. It is suggested that emergency plans should be made for just such an eventuality. Even if Chernobyl could not happen in the UK, the effects of accidents are international. The way in which nuclear reactor accidents happen is explored, taking the 1957 Windscale fire, Three Mile Island and Chernobyl as examples. Reactor designs and accident scenarios are considered. The different reactor designs are listed. As well as the Chernobyl RBMK design it is suggested that the light water reactors also have undesirable features from the point of view of safety. (U.K.)
Estimating the frequency of nuclear accidents
Raju, Suvrat
We used Bayesian methods to compare the predictions of probabilistic risk assessment -- the theoretical tool used by the nuclear industry to predict the frequency of nuclear accidents -- with empirical data. The existing record of accidents with some simplifying assumptions regarding their probability distribution is sufficient to rule out the validity of the industry's analyses at a very high confidence level. We show that this conclusion is robust against any reasonable assumed variation of safety standards over time, and across regions. The debate on nuclear liability indicates that the industry has independently arrived at this conclusion. We pay special attention to the Indian situation, where we show that the existing operating experience provides insufficient data to make any reliable claims about the safety of future reactors. We briefly discuss some policy implications.
Virenque, C; Laguerre, J
Fulguration, first electric accident in which the man was a victim, is to day better known. A clap of thunder is decomposed in two elements: lightning, and thunder. Lightning is caused by an electrical discharge, either within a cloud, or between two clouds, or, above all, between a cloud and the surface of the ground. Experimental equipments owned by the French Electricity Company and by the Atomic Energy Commission, have allowed to photograph lightnings and to measure certain physical characteristics (Intensity variable between 25 to 100 kA, voltage variable between 20 to 1 000 kV). The frequency of storms was learned: the isokeraunic level, in France, is about 20, meaning that thunder is heard twenty days during one year. Man may be stricken by thunder by direct hit, by sudden bursting, by earth current, or through various conductors. The electric charge which reached him may go to the earth directly by contact with the ground or may dissipate in the air through a bony promontory (elbow). The total number of victims, "wounded" or deceased, is not now known by statistics. Death comes by insulation breakdown of one of several anatomic cephalic formations: skull, meninx, brain. Many various lesions may happen in survivors: loss of consciousness, more or less long, sensorial or motion deficiencies. All these signs are momentary and generally reversible. Besides one may observe much more intense lesions on the skin: burns and, over all, characteristic aborescence (skin effect by high frequency current). The heart is protected, contrarily to what happens with industrial electrocution. The curative treatment is merely symptomatic : reanimation, surgery for burns or associated traumatic lesions. A prevention is researched to help the lonely man, in the country or in the mountains in the houses (lightning conductor, Faraday cage), in vehicles (aircraft, cars, ships). The mysterious and unforseeable character of lightning still stays, leaving a door opened for numerous
International Nuclear Information System (INIS)
Although the Soviet Union has more submarines than the NATO navies combined, and the technological superiority of western submarines is diminishing, there is evidence that there are more accidents with Soviet submarines than with western submarine fleets. Whether this is due to inadequate crews or lower standards of maintenance and overhaul procedures is discussed. In particular, it is suggested that since the introduction of nuclear powered submarines, the Soviet submarine safety record has deteriorated. Information on Soviet submarine accidents is difficult to come by, but a list of some 23 accidents, mostly in nuclear submarines, between 1966 and 1986, has been compiled. The approximate date, class or type of submarine, the nature and location of the accident, the casualties and damage and the source of information are tabulated. (U.K.)
Accident resistant transport container
Anderson, J.A.; Cole, K.K.
The invention relates to a container for the safe air transport of plutonium having several intermediate wood layers and a load spreader intermediate an inner container and an outer shell for mitigation of shock during a hypothetical accident.
Department of Homeland Security — Accident statistics available on the Coast Guard's website by state, year, and one variable to obtain tables and/or graphs. Data from reports has been loaded for...
The Fatal Accident Reporting System (FARS) database consist of three relational tables, containing data on automobile accidents on public U.S. roads that resulted in the death of one or more people within 30 days of the accident. Truck and trailer accidents are also included.
Traffic Accidents on Slippery Roads
DEFF Research Database (Denmark)
Fonnesbech, J. K.; Bolet, Lars
Police registrations from 65 accidents on slippery roads in normally Danish winters have been studied. The study showed: • 1 accident per 100 km when using brine spread with nozzles • 2 accidents per 100 km when using pre wetted salt • 3 accidents per 100 km when using kombi spreaders The results...
An Epidemiological Study of Accidents among Construction Workers in Kerman
Directory of Open Access Journals (Sweden)
Hasan Khaje
Full Text Available Introduction: Accidents are known among the leading causes of deaths and disabilities in developing and industrialized countries. Among the various occupations and activities, construction industry is among the most hazardous industries in the world, the risk of which and its following harms are still somehow unknown. This study aimed at investigating the epidemiology of accidents in construction, for the first time in Kerman. Methods: In this descriptive, analytical study, all construction workers (n=153 who had been hurt at work during 2006-2008 were investigated. The data were collected through questionnaire and were analyzed by chi-square and regression logistic test, SPSS statistical software. Results: The mean age of the injured workers was 32 years (the lowest age was 16 and the highest was 70 years and the highest rate of accidents occurred among the 16-36 years-old age group. Generally, 16.3 % (n=25 of the accidents led to death and 77.8% of the accidents occurred to people with junior high school and lower levels of education. There were significant relationships between the three variables of year, season and the shift in which the accident occurred and the result (death or survival of the accident. However, no significant relationships were observed between the insurance status of the injured and the results of the accidents. Conclusion: In Iran, there are strong relationships between reasons and results of accidents, so this study recommends more studies with the aim of changing the current trend to prevent the accidents in future.
Radiological impact to the population of the three major accidents happened in the civil nuclear industry; Impacto radiologico a la poblacion de los tres mayores accidentes ocurridos en la industria nuclear civil
Energy Technology Data Exchange (ETDEWEB)
Ortiz M, J. R., E-mail: email@example.com [Sociedad Nuclear Mexicana, Mexico D. F. (Mexico)
The greatest fear of the population before a nuclear accident, is the radiological impact to the health of people, due to the exposure to the liberated radioactive material during the accident, this fear is generally exaggerated or not well managed by the media. The best estimate in the received doses and their possible effects is carried out based on the information obtained during a certain time after the accident event. This work contains a summary of the information in the topic that at the present time has presented institutions as: the World Health Organization (Who), the United Nations Scientific Committee on Effects of Atomic Radiation (UNSCEAR), the Nuclear Regulatory Commission (NRC) and the World Nuclear Association, among others. The considered accidents are: first, the Unit-2 of the nuclear power plant of the Three Mile Island in Pennsylvania, USA occurred 28 March of 1979, in the Reactor TMI-2, type PWR of 900 M We; the second accident was 26 April of 1986, in the Unit-4 of the nuclear power plant of Chernobyl, in Ukraine, the involved reactor was type BRMK, of 1000 M We moderated by graphite and cooled with light water, the power plant is located to 100 Km to the northwest of Kiev; 25 years later occurred the third accident in the nuclear power plant of Fukushima Dai-ichi, in Japan, affecting at four of the six reactors of the power plant. A brief description of the accident is presented in each case, including the magnitude of the provoked liberations of radioactive material, the estimate doses of the population and the affected workers are presented, as well as the possible consequences of these doses on the health. The objective of this diffusion work is to give knowledge to the nuclear and radiological community of the available information on the topic, in order to be located in the appropriate professional context. (author)
Accident management information needs
International Nuclear Information System (INIS)
In support of the US Nuclear Regulatory Commission (NRC) Accident Management Research Program, a methodology has been developed for identifying the plant information needs necessary for personnel involved in the management of an accident to diagnose that an accident is in progress, select and implement strategies to prevent or mitigate the accident, and monitor the effectiveness of these strategies. This report describes the methodology and presents an application of this methodology to a Pressurized Water Reactor (PWR) with a large dry containment. A risk-important severe accident sequence for a PWR is used to examine the capability of the existing measurements to supply the necessary information. The method includes an assessment of the effects of the sequence on the measurement availability including the effects of environmental conditions. The information needs and capabilities identified using this approach are also intended to form the basis for more comprehensive information needs assessment performed during the analyses and development of specific strategies for use in accident management prevention and mitigation. 3 refs., 16 figs., 7 tabs
Development of Database for Accident Analysis in Indian Mines
Tripathy, Debi Prasad; Guru Raghavendra Reddy, K.
Mining is a hazardous industry and high accident rates associated with underground mining is a cause of deep concern. Technological developments notwithstanding, rate of fatal accidents and reportable incidents have not shown corresponding levels of decline. This paper argues that adoption of appropriate safety standards by both mine management and the government may result in appreciable reduction in accident frequency. This can be achieved by using the technology in improving the working conditions, sensitising workers and managers about causes and prevention of accidents. Inputs required for a detailed analysis of an accident include information on location, time, type, cost of accident, victim, nature of injury, personal and environmental factors etc. Such information can be generated from data available in the standard coded accident report form. This paper presents a web based application for accident analysis in Indian mines during 2001-2013. An accident database (SafeStat) prototype based on Intranet of the TCP/IP agreement, as developed by the authors, is also discussed.
Directory of Open Access Journals (Sweden)
Akinyemi Olasunkanmi Oriola
Full Text Available This research proposes an improved model for estimating runway accident cost in the aviation industry in Nigeria. Bayesian Network was used to model the probability of consequences of runway accidents and subsequently the cost of the potential consequences. The Bayesian Network was also used to implement causal and diagnostic inference. Market interest rate which incorporates the effect of inflation was included to relax the assumption of constant economic value. The three classes of consequences of runway accidents identified in this study were fatal, serious, and minor. Domain experts were used to obtain relevant Bayesian causes and evidences related to the occurrence of consequence of runway accident. A mathematical equation was developed to solve the Bayesian Network influence diagram to obtain the probability of minor runway accident, serious runway accident and fatal runway accident as 0.7603, 0.1547 and 0.0850 respectively. Consequently, the estimated cost of runway accident (minor, serious and fatal was $23, 813.52, $20, 052.64 and $772, 856.06 respectively. The Bayesian Network diagnostic inference reveals the close relation of runway accidents in Nigeria aviation sector with aircraft system failure, approach/takeoff procedures, human factors, weather conditions and collision risk.
Health consequences [of the Chernobyl accident
International Nuclear Information System (INIS)
The World Health Organisation Conference on the Health Consequences of the Chernobyl and Other Radiological Accidents, held in Geneva last November, is reported. The lack of representation from the civil nuclear industry led often to one-sided debates instigated by the anti-nuclear lobbies present. Thyroid cancer in children as a result of the Chernobyl accident received particular attention. In Belarus, 400 cases have been noted, 220 in Ukraine and 60 in the Russian Federation. All have been treated with a high degree of success. The incidence of this cancer would be expected to follow the fallout path as the main exposure route was ingestion of contaminated foods and milk products. It was noted that the only way to confirm causality was if those children born since the accident failed to show the same increased incidence. Explanations were offered for the particular susceptibility of children to thyroid cancer following exposure to radiation. Another significant cause of concern was the health consequences to clean-up workers in radiological accidents. The main factor is psychological problems from the stress of knowing that they have received high radiation doses. A dramatic increase in psychological disorders has occurred in the Ukraine over the past ten years and this is attributed to stress generated by the Chernobyl accident, compounded by the inadequacy of the public advice offered at the time and the socio-economic uncertainties accompanying the breakup of the former USSR. (UK)
Cyclical Fluctuations in Workplace Accidents
Boone, J.; van Ours, J.C.
This Paper presents a theory and an empirical investigation on cyclical fluctuations in workplace accidents. The theory is based on the idea that reporting an accident dents the reputation of a worker and raises the probability that he is fired. Therefore a country with a high or an increasing unemployment rate has a low (reported) workplace accident rate. The empirical investigation concerns workplace accidents in OECD countries. The analysis confirms that workplace accident rates are invers...
Energy Technology Data Exchange (ETDEWEB)
Oelgaard, P.L. [Risoe National Lab., Roskilde (Denmark)]|[Technical Univ. of Denmark, Lyngby (Denmark)
This report starts with a discussion of the types of nuclear vessels accidents, in particular accidents which involve the nuclear propulsion systems. Next available information on 61 reported nuclear ship events in considered. Of these 6 deals with U.S. ships, 54 with USSR ships and 1 with a French ship. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/explosions, sea-water leaks into the submarines and sinking of vessels are considered. For each event a summary of available information is presented, and comments are added. In some cases the available information is not credible, and these events are neglected. This reduces the number of events to 5 U.S. events, 35 USSR/Russian events and 1 French event. A comparison is made between the reported Soviet accidents and information available on dumped and damaged Soviet naval reactors. It seems possible to obtain good correlation between the two types of events. An analysis is made of the accident and estimates are made of the accident probabilities which are found to be of the order of 10{sup -3} per ship reactor years. It if finally pointed out that the consequences of nuclear ship accidents are fairly local and does in no way not approach the magnitude of the Chernobyl accident. It is emphasized that some of the information on which this report is based, may not be correct. Consequently some of the results of the assessments made may not be correct. (au).
International Nuclear Information System (INIS)
This report starts with a discussion of the types of nuclear vessels accidents, in particular accidents which involve the nuclear propulsion systems. Next available information on 61 reported nuclear ship events in considered. Of these 6 deals with U.S. ships, 54 with USSR ships and 1 with a French ship. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/explosions, sea-water leaks into the submarines and sinking of vessels are considered. For each event a summary of available information is presented, and comments are added. In some cases the available information is not credible, and these events are neglected. This reduces the number of events to 5 U.S. events, 35 USSR/Russian events and 1 French event. A comparison is made between the reported Soviet accidents and information available on dumped and damaged Soviet naval reactors. It seems possible to obtain good correlation between the two types of events. An analysis is made of the accident and estimates are made of the accident probabilities which are found to be of the order of 10-3 per ship reactor years. It if finally pointed out that the consequences of nuclear ship accidents are fairly local and does in no way not approach the magnitude of the Chernobyl accident. It is emphasized that some of the information on which this report is based, may not be correct. Consequently some of the results of the assessments made may not be correct. (au)
Report on the accident at the Chernobyl Nuclear Power Station
International Nuclear Information System (INIS)
This report presents the compilation of information obtained by various organizations regarding the accident (and the consequences of the accident) that occurred at Unit 4 of the nuclear power station at Chernobyl in the USSR on April 26, 1986. The various authors are identified in a footnote to each chapter. An overview of the report is provided. Very briefly the other chapters cover: the design of the Chernobyl nuclear station Unit 4; safety analyses for Unit 4; the accident scenario; the role of the operator; an assessment of the radioactive release, dispersion, and transport; the activities associated with emergency actions; and information on the health and environmental consequences from the accident. These subjects cover the major aspects of the accident that have the potential to present new information and lessons for the nuclear industry in general
Scoping accident(s) for emergency planning
International Nuclear Information System (INIS)
At the request of the Conference of State Radiation Control Program Director's (CRCPD), in November 1976 the U.S. Nuclear Regulatory Commission formed a joint Task Force with representatives of the U.S. Environmental Protection Agency to answer a number of questions posed by the States regarding emergency planning. This Task Force held monthly meetings through November 1977. In December 1977 a draft report was prepared for limited distribution for review and comment by selected State and local organizations. The NRC/EPA Task Force deliberations centered on the CRCPD request for '... a determination of the most severe accident basis for which radiological emergency response plans should be developed by offsite agencies...' in the vicinity of nuclear power plants. Federal Interagency guidance to the States in this regard has been that the scoping accident should be the most serious conservatively analyzed accident considered for siting purposes, as exemplified in the Commission's Regulations at 10 CFR Part 100 and the NRC staffs Regulatory Guides 1.3 and 1.4, and as presented in license applicant's Safety Analysis Reports and the USNRC Staffs Safety Evaluation Reports. The draft report of the Task Force amplifies on this recommendation: to present a clearer picture of its import and introduces the concept of protective action zones (PAZs) within which detailed emergency plans should be developed; one zone for the plume exposure pathway and a second, larger zone for contamination pathways. The time dependence of potential releases and atmospheric transport, and important radionuclide groups of possible import are also discussed in the draft Task Force report. A status report regarding this effort, as of June 1978, will be presented. (author)
Real and mythical consequences of Chernobyl accident
International Nuclear Information System (INIS)
This presentation describes the public Unacceptance of Nuclear Power as a consequence of Chernobyl Accident, an accident which was a severest event in the history of the nuclear industry. It was a shock for everybody, who has been involved in nuclear power programs. But nobody could expect that it was also the end romantic page in the nuclear story. The scale of the detriment was a great, and it could be compared with other big technological man-made catastrophes. But immediately after an accident mass media and news agencies started to transmit an information with a great exaggerations of the consequences of the event. In a report on the Seminar The lessons of the Chernobyl - 1' in 1996 examples of such incorrect information, were cited. Particularly, in the mass media it was declared that consequences of the accident could be compared with a results of the second world war, the number of victims were more than hundred thousand people, more than million of children have the serious health detriments. Such and other cases of the misconstruction have been called as myths. The real consequences of Chernobyl disaster have been summed on the International Conference 'One decade after Chernobyl' - 2, in April 1996. A very important result of the Chernobyl accident was a dissemination of stable unacceptance of the everything connected with 'the atom'. A mystic horror from invisible mortal radiation has been inspired in the masses. And from such public attitude the Nuclear Power Programs in many countries have changed dramatically. A new more pragmatic and more careful atomic era started with a slogan: 'Kernkraftwerk ? Nein, danke'. No doubt, a Chernobyl accident was a serious technical catastrophe in atomic industry. The scale of detriment is connected with a number of involved peoples, not with a number of real victims. In comparison with Bhopal case, earthquakes, crashes of the airplanes, floods, traffic accidents and other risky events of our life - the Chernobyl is
Dementia and Traffic Accidents
DEFF Research Database (Denmark)
Petersen, Jindong Ding; Siersma, Volkert; Nielsen, Connie Thurøe;
BACKGROUND: As a consequence of a rapid growth of an ageing population, more people with dementia are expected on the roads. Little is known about whether these people are at increased risk of road traffic-related accidents. OBJECTIVE: Our study aims to investigate the risk of road traffic...... Central Research Register, and/or (2) at least one dementia diagnosis-related drug prescription registration in the Danish National Prescription Registry. Police-, hospital-, and emergency room-reported road traffic-related accidents occurred within the study follow-up are defined as the study outcome...... selection bias due to nonparticipation and loss to follow-up. Furthermore, this ensures that the study results are reliable and generalizable. However, underreporting of traffic-related accidents may occur, which will limit estimation of absolute risks....
International Nuclear Information System (INIS)
A critical study about the technical and man-related facts in order to establish what is considered the worst commercial nuclear power accident until 1986. Radiological consequences and stress to the public are considered in contrast to antinuclear groups. This descriptive and technical study has the purpose to document written and oral opinions obtained abroad and then explain to the public in an easy language terminology. Preliminary study describing safety related systems fails and the accident itself with minute to minute description, conduct to the consequences and then, to learned lessons
Accidents caused by electric currents; Unfaelle durch elektrischen Strom
Energy Technology Data Exchange (ETDEWEB)
Juehling, J. [Berufsgenossenschaft der Feinmechanik und Elektrotechnik, Koeln (Germany). Inst. zur Erforschung Elektrischer Unfaelle
The present evaluation only refers to accidents caused by electric currents in member companies of the employees` industrial compensation society of the fine mechanics and electrical engineering professions (BGFE). In some cases the institute also publishes statistics on the frequency time course of electrical accidents which deviate from those the relevant annual report. This is mainly due to the fact that these statistics also contain non-notifiable accidents communicated via medical reports and the supplementary report on electrical accidents. They further contain keyed data on electrical accidents reported by other employees` industrial compensation societies. Inquiries made to the institute may therefore be answered on the basis of all the above-mentioned data on electrical accidents as well as on the overall accident statistics of the BGFE. [Deutsch] Die nachfolgenden Auswertungen beziehen sich nur auf Unfaelle in Mitgliedsbetrieben der BG F und E, verursacht durch den elektrischen Strom. Zum Teil veroeffentlicht aber das Institut Zahlen ueber die zeitliche Entwicklung von Stromunfaellen, die nicht immer mit den Angaben der jeweiligen Jahresberichte uebereinstimmen muessen. Das liegt vor allem daran, dass auch nicht-meldepflichtige Unfaelle ueber den D-Arztbericht und ueber den Ergaenzungsbericht bei Unfaellen durch elektrischen Strom - also ueber aerztliche Erhebungsformulare - erfasst werden. Ausserdem werden auch von anderen Berufsgenossenschaften eingehende Stromunfaelle verschluesselt. Zur Beantwortung von Anfragen an das Institut koennen also all die vorgenannten Daten zu elektrischen Unfaellen und natuerlich auch die Zahlen zum Gesamtunfallgeschehen der BG F und E herangezogen werden. (orig.)
Accidents Preventive Practice for High-Rise Construction
Directory of Open Access Journals (Sweden)
Goh Kai Chen
Full Text Available The demand of high-rise projects continues to grow due to the reducing of usable land area in Klang Valley, Malaysia. The rapidly development of high-rise projects has leaded to the rise of fatalities and accidents. An accident that happened in a construction site can cause serious physical injury. The accidents such as people falling from height and struck by falling object were the most frequent accidents happened in Malaysian construction industry. The continuous growth of high-rise buildings indicates that there is a need of an effective safety and health management. Hence, this research aims to identify the causes of accidents and the ways to prevent accidents that occur at high-rise building construction site. Qualitative method was employed in this research. Interview surveying with safety officers who are involved in highrise building project in Kuala Lumpur were conducted in this research. Accidents were caused by man-made factors, environment factors or machinery factors. The accidents prevention methods were provide sufficient Personal Protective Equipment (PPE, have a good housekeeping, execute safety inspection, provide safety training and execute accidents investigation. In the meanwhile, interviewees have suggested the new prevention methods that were develop a proper site layout planning and de-merit and merit system among sub-contractors, suppliers and even employees regarding safety at workplace matters. This research helps in explaining the causes of accidents and identifying area where prevention action should be implemented, so that workers and top management will increase awareness in preventing site accidents.
[Electrophysiologic criteria for the prevention of electric accidents].
Kupfer, J
About 0.25 percent of all registered industrial accidents are caused by electric current. One in 20 of these accidents has been fatal. The consequences of electric flow are determined by several factors, above all voltage, time and path of flow, type of current, and resistors within the power circuit. These are attributable to physiological criteria of conduction. Slight electric shock and death by ventricular fibrillation are close to each other by the all-or-nothing law. Conclusions are suggested for practice, and a discussion is proposed with a view to find an adequate definition of the power-related accident. PMID:2085034
Information on economic and social consequences of the Chernobyl accident
International Nuclear Information System (INIS)
This ''Information on economic and social consequences of the Chernobyl accident'' was presented to the July 1990 session of the Economic and Social Council of the United Nations by the delegations of the Union of Soviet Socialist Republics, the Byelorussian Soviet Socialist Republic and the Ukrainian Soviet Socialist Republic. It presents the radiation situation, the medical aspects of the accident, the evacuation of the inhabitants from areas affected by radioactive contamination and their social welfare, the agro-industrial production and forestry in these areas, the decontamination operations, the scientific back-up for the work dealing with the consequences of the accident and the expenditure and losses resulting from the Chernobyl disaster
Strategies for operator response in mitigating loss of containment heat removal accident scenarios
International Nuclear Information System (INIS)
In anticipation of the US Nuclear Regulatory Commission generic letter regarding accident management, the Boiling Water Reactor Owners' Group (BWROG) has commissioned the development of Accident Management Guidelines (AMGs). One outgrowth of the industry performance of individual plant examinations (IPES) is the development of more effective accident management guidance to prevent or mitigate the effects of severe accidents. The BWROG is determining a process for integrating these insights into a coherent format that can be implemented by BWR owners as part of accident management
MELCOR DB Construction for the Severe Accident Analysis DB
Energy Technology Data Exchange (ETDEWEB)
Song, Y. M.; Ahn, K. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
The Korea Atomic Energy Research Institute (KAERI) has been constructing a severe accident analysis database (DB) under a National Nuclear R and D Program. In particular, an MAAP (commercial code being widely used in industries for integrated severe accident analysis) DB for many scenarios including a station blackout (SBO) has been completed. This paper shows the MELCOR DB construction process with examples of SBO scenarios, and the results will be used for a comparison with the MAAP DB
Occupational accidents aboard merchant ships
DEFF Research Database (Denmark)
Hansen, H.L.; Nielsen, D.; Frydenberg, Morten
aboard. Relative risks for notified accidents and accidents causing permanent disability of 5% or more were calculated in a multivariate analysis including ship type, occupation, age, time on board, change of ship since last employment period, and nationality. Foreigners had a considerably lower recorded...... identified during a total of 31 140 years at sea. Among these, 209 accidents resulted in permanent disability of 5% or more, and 27 were fatal. The mean risk of having an occupational accident was 6.4/100 years at sea and the risk of an accident causing a permanent disability of 5% or more was 0.67/100 years...... rate of accidents than Danish citizens. Age was a major risk factor for accidents causing permanent disability. Change of ship and the first period aboard a particular ship were identified as risk factors. Walking from one place to another aboard the ship caused serious accidents. The most serious...
International Nuclear Information System (INIS)
The TMI-2 accident occurred in March 1979. The accident started with a simple and fairly common steam power plant failure--loss of feedwater to the steam generators. Because of a combination of design, training, regulatory policies, mechanical failures and human error, the accident progressed to the point where it eventually produced the worst known core damage in large nuclear power reactors. Core temperatures locally reached UO2 fuel liquefaction (metallic solution with Zr) and even fuel melt (3800-51000F). Extensive fission product release and Zircaloy cladding oxidation and embrittlement occurred. At least the upper 1/2 of the core fractured and crumbled upon quenching. The lower central portion of the core apparently had a delayed heatup and then portions of it collapsed into the reactor vessel lower head. The lower outer portion of the core may be relatively undamaged. Outside of the core boundary, only those steel components directly above and adjacent to the core (≤1 foot) are known to have suffered significant damage (localized oxidation and melting). Other portions of the primary system outside of the reactor vessel apparently had little chance of damage or even notable overheating. The demonstrated coolability of the severely damaged TMI-2 core, once adequate water injection began, was one of the most substantial and important results of the TMI-2 accident
The Chernobyl reactor accident
International Nuclear Information System (INIS)
The documentation abstracted contains a complete survey of the broadcasts transmitted by the Russian wire service of the Deutsche Welle radio station between April 28 and Mai 15, 1986 on the occasion of the Chernobyl reactor accident. Access is given to extracts of the remarkable eastern and western echoes on the broadcasts of the Deutsche Welle. (HP)
Measures against nuclear accidents
International Nuclear Information System (INIS)
A select committee appointed by the Norwegian Ministry of Social Affairs put forward proposals concerning measures for the improvement of radiation protection preparedness in Norway. On the basis on an assessment of the potential radiation accident threat, the report examines the process of response, and identifies the organizational and management factors that influence that process
Road Traffic Accidents in Kazakhstan
Alma Aubakirova; Alibek Kossumov; Nurbek Igissinov
Background: The article provides the analysis of death rates in road traffic accidents in Kazakhstan from 2004 to 2010 and explores the use of sanitary aviation. Methods: Data of fatalities caused by road traffic accidents were collected and analysed. Descriptive and analytical methods of epidemiology and biomedical statistics were applied. Results: Totaly 27,003 people died as a result of road traffic accidents in this period. The death rate for the total population due to road traffic accid...
The psychology of nuclear accidents
International Nuclear Information System (INIS)
Incidents involving nuclear weapons are described, as well as the accident to the Three Mile Island-2 reactor. Methods of assessment of risks are discussed, with particular reference to subjective judgements and the possible role of human error in civil nuclear accidents. Accidents or misunderstandings in communication or human actions which might lead to nuclear war are also discussed. (U.K.)
Marine Offshore Accidents in Nigeria, Causes and Necessary Preventive Measures
Directory of Open Access Journals (Sweden)
yinkepreye L. Bebeteidoh ,Robert Poku
Full Text Available With the ground-breaking developments in the maritime industry and the implementation of safety-related regulations and the institution of International Safety Codes and Protocols, marine offshore accidents in Nigeria are still a serious concern for global maritime organizations as the rate of offshore accidents has not reduced to the expected level. Ensuring the consistency of offshore accident investigation reports is recognized as a significant goal in order to plainly ascertain the core causes of offshore accidents. This research work though limited due to poor response on the part of the respondents as regards to releasing some data that would have been helpful, the researchers were still able to investigate the core causes of marine offshore accidents in Nigeria's maritime industry. With emphasis on the scope of work essentially, data was collected through the administration of a well-structured questionnaire to selected seafarers connected with the offshore oil and gas industry in Nigeria, which included Captains, engineers, deckhands, oilers and Quartermasters. The data's collected through the administration of a self-constructed questionnaire was analyzed using the concept of the statistical tool, Chi-Square, which was considered appropriate for testing the validity and reliability of each hypothesis established in this research. The aim of this research was to determine the causes of marine offshore accidents in Nigeria, which identified that human, environmental/natural, design, and technical factors comprises the major causes of marine offshore accidents. With the findings gotten, recommendations were made which if implemented by governments and maritime organizations and adhered to by maritime operators will go a long way to reduce marine offshore accidents.
Modeling accidents for prioritizing prevention
International Nuclear Information System (INIS)
The Workgroup Occupational Risk Model (WORM) project in the Netherlands is developing a comprehensive set of scenarios to cover the full range of occupational accidents. The objective is to support companies in their risk analysis and prioritization of prevention. This paper describes how the modeling has developed through projects in the chemical industry, to this one in general industry and how this is planned to develop further in the future to model risk prevention in air transport. The core modeling technique is based on the bowtie, with addition of more explicit modeling of the barriers needed for risk control, the tasks needed to ensure provision, use, monitoring and maintenance of the barriers, and the management resources and tasks required to ensure that these barrier life cycle tasks are carried out effectively. The modeling is moving from a static notion of barriers which can fail, to seeing risk control dynamically as (fallible) means for staying within a safe envelope. The paper shows how concepts develop slowly over a series of projects as a core team works continuously together. It concludes with some results of the WORM project and some indications of how the modeling is raising fundamental questions about the conceptualization of system safety, which need future resolution
Burnout y prescripción de incapacidad laboral temporal Work satisfaction and temporary sick leave prescription in a sample of doctors inside a mutual society of industrial accidents and occupational diseases (matepss
Directory of Open Access Journals (Sweden)
Dr. Ismael S. Diana Domínguez
Full Text Available Objetivo: Hallar el grado de satisfacción laboral en una muestra de médicos asistenciales de una mutua de accidentes de trabajo y enfermedades profesionales (MATEPSS, determinando su relación con una serie de aspectos sociodemográficos y laborales y con su repercusión sobre la prescripción de incapacidad temporal. Material y método: Se realizó un estudio transversal en una muestra final de 156 médicos (muestra total de 250 médicos, repartidos por toda la geografía española de una MATEPSS, a los que se les aplicó el Maslach burnout inventory, y un cuestionario de elaboración propia que mide una serie de variables sociodemográficas. Sobre 131 médicos pertenecientes a la muestra mencionada anteriormente, se realizó un estudio sobre la influencia que el burnout y esas variables sociodemográficas podían ejercer sobre la prescripción de bajas laborales. Se utilizó el paquete estadístico SPSS, realizándose dos métodos estadísticos diferentes. Resultados: El primer método arrojó los siguientes resultados: la oportunidad de padecer grado alto de cansancio emocional se asocia de forma significativa (pObjetive: Find the level of work satisfaction in a sample of doctors inside a mutual society of industrial accidents and occupational diseases (MATEPSS. In this report, the relation between work satisfaction, socio-demographics and industrial factors, and its influence on temporary sick leave is shown. Teaching aid and method: A transverse study has been carried out on a final sample of 156 doctors (whole sample: 250 doctors belonging to MATEPSS. The doctors are distributed in all Spanish geography. "The Maslach burnout inventory" was given to them. This questionnaire measures the burnout in its three sections: emotional tiredness, depersonalization and personal accomplishment. Another questionnaire was given also to them. This one, elaborated by the author, measures socio-demographics variables. On 131 doctors of the previous
Chernobyl reactor accident: medical management
International Nuclear Information System (INIS)
Chernobyl reactor accident on 26th April, 1986 is by far the worst radiation accident in the history of the nuclear industry. Nearly 500 plant personnel and rescue workers received doses varying from 1-16 Gy. Acute radiation syndrome (ARS) was seen only in the plant personnel. 499 individuals were screened for ARS symptoms like nausea, vomitting, diarrhoea and fever. Complete blood examination was done which showed initial granulocytosis followed by granulocytopenia and lymphocytopenia. Cytogenetic examinations were confirmatory in classifying the patients on the basis of the doses received. Two hundred and thirty seven cases of ARS were hospitalised in the first 24-36 hrs. No member of general public suffered from ARS. There were two immediate deaths and subsequently 28 died in hospital and one of the cases died due to myocardial infarction, making a total of 31 deaths. The majority of fatal cases had whole body doses of about 6 Gy, besides extensive skin burns. Two cases of radiation burns had thermal burns also. Treatment of ARS consisted of isolation, barrier nursing, replacement therapy with fluid electrolytes, platelets and RBC transfusions and antibiotic therapy for bacterial, fungal and viral infections. Bone marrow transplantations were given to 13 cases out of which 11 died due to various causes. Radiation burns due to beta, gamma radiations were seen in 56 cases and treated with dressings, surgical excision, skin grafting and amputation. Oropharangeal syndrome, producing extensive mucous in the oropharynx, was first seen in Chernobyl. The patients were treated with saline wash of the mouth. The patients who had radioactive contamination due to radioactive iodine were given stable iodine, following wash with soap, water and monitored. Fourteen survivors died subsequently due to other causes. Late health effects seen so far include excess of thyroid cancer in the children and psychological disorders due to stress. No excess leukemia has been reported so
Nuclear accident and medical staff
International Nuclear Information System (INIS)
Described is the commentary concerning normative action of medical staff at radiation emergency and actual actions taken/to be taken for the Nuclear Power Plant Accident (NPPA) in Fukushima. The normative medical staff's action at radiation emergency is essentially based on rules defined by such international authorities as United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), International Commission of Radiological Protection (ICRP), International Atomic Energy Agency (IAEA) and Basic Safety Standard (BSS) and by network in IAEA, World Health Organization (WHO) and so on. The rules stand on past atomic events like those in Hiroshima, Nagasaki, Three Mile Isl., Chernobyl, and in Japanese Tokai JCO accident. The action above is required as a medical teamwork over specialized doctors. At Fukushima NPPA, medicare flowed from the on-site first-aid station (doctors for industry and labors), then the base for patient transfer (doctors of Japanese Association of Acute Medicine and Tokyo Electric Power Comp.), to the primary hospital for acute exposure (Iwaki Kyoritsu Hos.), from which patients were further transported to the secondary (contamination detected or severe trauma, Fukushima Medical Univ.) and/or tertiary facilities (serious contamination or acute radiation injury, National Institute of Radiological Sciences (NIRS) and Hiroshima Univ.). The flow was built up by the previous lead of national official guidance and by urgent spontaneous network among medical facilities; exempli gratia (e.g.), Fukushima Medical Univ. rapidly specialized in coping with the radiation medicare by partial discontinuance of daily clinical practice. Specialists of acute radiation medicare are generally rare, for which measures for it are more desirable along with health risk communication in facilities concerned. The professional function and endowment required for medical staff at emergency are concluded to be their guts and devotion as well as medical
Tractor accidents in Swedish traffic.
Pinzke, Stefan; Nilsson, Kerstin; Lundqvist, Peter
The objective of this study is to reach a better understanding of accidents on Swedish roads involving tractors and to suggest ways of preventing them. In an earlier study we analyzed police-reported fatal accidents and accidents that led to physical injuries from 1992 to 2005. During each year of this period, tractors were involved in 128 traffic accidents on average, an average of 7 people were killed, 44 sustained serious injuries, and 143 sustained slight injuries. The number of fatalities in these tractor accidents was about 1.3% of all deaths in traffic accidents in Sweden. Cars were most often involved in the tractor accidents (58%) and 15% were single vehicle accidents. The mean age of the tractor driver involved was 39.8 years and young drivers (15-24 years) were overrepresented (30%). We are now increasing the data collected with the years 2006-2010 in order to study the changes in the number of accidents. Special attention will be given to the younger drivers and to single vehicle accidents. Based on the results we aim to develop suggestions for reducing road accidents, e.g. including measures for making farm vehicles more visible and improvement of the training provided at driving schools. PMID:22317543
Analysis on influence factors of electrostatic accidents in oil industry based on fishbone diagram and AHP%基于鱼骨图和层次分析法的石油静电事故影响因素分析∗
Institute of Scientific and Technical Information of China (English)
胡玉琴; 王殿生; 赵洪磊; 刘金玉
According to the characteristics of complexity, diversity and uncertainty about the influence factors of e-lectrostatic accidents in oil industry, the influencing factors leading to electrostatic accident in oil industry were i-dentified by adopting fishbone diagram method, and an assessment index system of oil electrostatic accidents was determined, which included 6 main factors and 25 sub factors. The AHP method was used to obtain the significance level of each factor, and the key factors leading to the accident were analyzed. The results showed that in the 6 main factors, the sum of weights of 3 main factors being attached to production operation process and work safety management, including the operation mistake, human static electricity and ground fault, is up to 0. 792, and they are the dominant factors leading to oil electrostatic accidents. The prevention emphasis of sub factors should be placed on splashing oil loading and unloading, friction between chemical fiber and human body, and grounding line damage. The combined application of fishbone diagram and AHP solves the difficult problem of influence factor analysis on e-lectrostatic accidents in oil industry reasonably, and it has a certain value of popularization and application.%针对石油静电事故影响因素的复杂性、多层次性和不确定性的特点,采用鱼骨图分析法,找出了引发石油静电事故的影响因素,确定出6个主因素、25个子因素的石油静电事故评价指标体系。应用层次分析法确定了各个影响因素的重要程度,分析出导致石油静电事故的重要因素。结果表明,6个主因素中,隶属于生产操作工艺和安全生产管理的操作错误、人体静电和接地故障3个主因素权重之和高达0.792,是引发石油静电事故的主导因素;子因素中预防的重点应放在喷溅式装卸油、化纤品与人体摩擦和接地线损坏方面。鱼骨图分析法和层次分析法的联合应�
[Drowning accidents in childhood].
Krandick, G; Mantel, K
This is a report on five boys aged between 1 and 5 years who, after prolonged submersion in cold water, were treated at our department. On being taken out of the water, all the patients were clinically dead. After 1- to 3-hour successful cardiopulmonary resuscitation, with a rectal temperature of about 27 degrees C, they were rewarmed at a rate of 1 degree/hour. Two patients died within a few hours after the accident. One patient survived with an apallic syndrome, 2 children survived with no sequelae. In the event of a water-related accident associated with hypothermia, we consider suitable resuscitation to have preference over rewarming measures. The most important treatment guidelines and prognostic factors are discussed.
International Nuclear Information System (INIS)
In this report available information on 28 nuclear ship accident and incidents is considered. Of these 5 deals with U.S. ships and 23 with USSR ships. The ships are in almost all cases nuclear submarines. Only events that involve the nuclear propulsion plants, radiation exposures, fires/explosions and sea water leaks into the submarines are considered. Comments are made on each of the events, and at the end of the report an attempt is made to point out the weaknesses of the submarine designs which have resulted in the accidents. It is emphasized that much of the available information is of a rather dubious nature. consequently some of the assessments made may not be correct. (au)
Cogbill, T H; Busch, H M; Stiers, G R
During a 6 1/2 year period, 105 children were admitted to the hospital as the result of trauma that occurred on farms. The mechanism of injury was animal related in 42 (40%), tractor or wagon accident in 28 (26%), farm machinery in 21 (20%), fall from farm building in six (6%), and miscellaneous in eight (8%). Injury Severity Score was calculated for each patient. An Injury Severity Score of greater than or equal to 25 was determined for 11 children (11%). Life-threatening injuries, therefore, are frequently the result of childhood activities that take place in agricultural environments. The most common injuries were orthopedic, neurologic, thoracoabdominal, and maxillofacial. There was one death in the series, and only one survivor sustained major long-term disability. Such injuries are managed with optimal outcome in a regional trauma center. Educational programs with an emphasis on prevention and safety measures may reduce the incidence of farm accidents. PMID:4047799
Dementia and Traffic Accidents
DEFF Research Database (Denmark)
Petersen, Jindong Ding; Siersma, Volkert; Nielsen, Connie Thurøe;
BACKGROUND: As a consequence of a rapid growth of an ageing population, more people with dementia are expected on the roads. Little is known about whether these people are at increased risk of road traffic-related accidents. OBJECTIVE: Our study aims to investigate the risk of road traffic......-related accidents for people aged 65 years or older with a diagnosis of dementia in Denmark. METHODS: We will conduct a nationwide population-based cohort study consisting of Danish people aged 65 or older living in Denmark as of January 1, 2008. The cohort is followed for 7 years (2008-2014). Individual's personal...... data are available in Danish registers and can be linked using a unique personal identification number. A person is identified with dementia if the person meets at least one of the following criteria: (1) a diagnosis of the disease in the Danish National Patient Register or in the Danish Psychiatric...
49 CFR 835.11 - Obtaining Board accident reports, factual accident reports, and supporting information.
... 49 Transportation 7 2010-10-01 2010-10-01 false Obtaining Board accident reports, factual accident... Board accident reports, factual accident reports, and supporting information. It is the responsibility... obtain Board accident reports, factual accident reports, and accompanying accident docket files....
Directory of Open Access Journals (Sweden)
Olasunkanmi Oriola AKINYEMI
Full Text Available Analysis of road traffic accidents revealed that most accidents are as a result of drivers' errors. Over the years, active safety systems (ASS were devised in vehicle to reduce the high level of road accidents, caused by human errors, leading to death and injuries.This study however evaluated the impacts of ASS inclusions into vehicles in Nigeria road transportation network. The objectives was to measure how ASS contributed to making driving safer and enhanced transport safety. Road accident data were collected, for a period of eleven years, from Lagos State Ministry of Economic Planning and Budget, Central Office of Statistics. Quantitative analysis of the retrospective accident was conducted by computing the proportion of yearly number of vehicles involved in road accident to the total number of vehicles for each year. Results of the analysis showed that the proportion of vehicles involved in road accidents decreased from 16 in 1996 to 0.89 in 2006, the injured persons reduced from 15.58 in 1998 to 0.3 in 2006 and the death rate diminished from 4.45 in 1998 to 0.1 in 2006. These represented 94.4%, 95% and 95% improvement respectively on road traffic safety. It can therefore be concluded that the inclusions of ASS into design of modern vehicles had improved road safety in Nigeria automotive industry.
International Nuclear Information System (INIS)
Described are the course of medical measures following Fukushima Daiichi Nuclear Power Plant (FNPP) Accident after the quake and tsunami (Mar. 11, 2011) and the future task for radiation accident/disaster. By the first hydrogen explosion in FNPP (Mar. 12), evacuation of residents within 20 km zone was instructed, and the primary base for measures of nuclear disaster (Off-site Center) 5 km afar from FNPP had to work as a front base because of damage of communicating ways, of saving of injured persons and of elevation of dose. On Mar. 13, the medical arrangement council consisting from stuff of Fukushima Medical University (FMU), National Institute of Radiological Sciences, Nuclear Safety Research Association and Prefectural officers was setup in residents' hall of Fukushima City, and worked for correspondence to persons injured or exposed, where communication about radiation and between related organizations was still poor. The Off-site Center's head section moved to Prefectural Office on Mar. 15 as headquarters. Early in the period, all residents evacuated from the 20 km zone, and in-hospital patients and nursed elderly were transported with vehicles, >50 persons of whom reportedly died mainly by their base diseases. The nation system of medicare for emergent exposure had consisted from the network of the primary to third facilities; there were 5 facilities in the Prefecture, 3 of which were localized at 4-9 km distance from FNPP and closed early after the Accident; and the secondary facility of FMU became responsible to all exposed persons. There was no death of workers of FNPP. Medical stuff also measured the ambient dose at various places near FNPP, having had risk of exposure. At the Accident, the important system of command, control and communication was found fragile and measures hereafter should be planned on assumption of the worst scenario of complete damage of the infrastructure and communication. It is desirable for Disaster Medical Assistance Team which
International Nuclear Information System (INIS)
When the TMI accident occurred it was 4 a.m., an hour when the error potential of the operators would have been very high. The frequency of car and train accidents in Japan is also highest between 4 a.m. and 6 a.m. The error potential may be classified into five phases corresponding to the electroencephalogramic pattern (EEG). At phase 0, when the delta wave appears, a person is unconscious and in deep sleep; at phase I, when the theta wave appears, he is very tired, sleepy and subnormal; at phase II, when the alpha wave appears, he is normal, relaxed and passive; at phase III, when the beta wave appears, he is normal, clear-minded and active; at phase IV, when the strong beta or epileptic wave appears, he is hypernormal, excited and incapable of normal judgement. Should an accident occur at phase II, the brain condition may jump to phase IV. At this phase the error or accident potential is maximum. The response of the human brain to different types of noises and signals may vary somewhat for different individuals and for different groups of people. Therefore, the possibility that such differences in brain functions may influence the mental structure would be worthy of consideration in human factors and in the design of man-machine systems. Human reliability and performance would be affected by many factors: medical, physiological and psychological, etc. The uncertainty involved in human factors may not necessarily be probabilistic, but fuzzy. Therefore, it would be important to develop a theory by which both non-probabilistic uncertainties, or fuzziness, of human factors and the probabilistic properties of machines can be treated consistently. From the mathematical point of view, probabilistic measure is considered a special case of fuzzy measure. Therefore, fuzzy set theory seems to be an effective tool for analysing man-machine systems. To minimize human error and the possibility of accidents, new safety systems should not only back up man and make up for his
Evaluation Metrics Applied to Accident Tolerant Fuels
Energy Technology Data Exchange (ETDEWEB)
Shannon M. Bragg-Sitton; Jon Carmack; Frank Goldner
The safe, reliable, and economic operation of the nation's nuclear power reactor fleet has always been a top priority for the United States' nuclear industry. Continual improvement of technology, including advanced materials and nuclear fuels, remains central to the industry's success. Decades of research combined with continual operation have produced steady advancements in technology and have yielded an extensive base of data, experience, and knowledge on light water reactor (LWR) fuel performance under both normal and accident conditions. One of the current missions of the U.S. Department of Energy's (DOE) Office of Nuclear Energy (NE) is to develop nuclear fuels and claddings with enhanced accident tolerance for use in the current fleet of commercial LWRs or in reactor concepts with design certifications (GEN-III+). Accident tolerance became a focus within advanced LWR research upon direction from Congress following the 2011 Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex. The overall goal of ATF development is to identify alternative fuel system technologies to further enhance the safety, competitiveness and economics of commercial nuclear power. Enhanced accident tolerant fuels would endure loss of active cooling in the reactor core for a considerably longer period of time than the current fuel system while maintaining or improving performance during normal operations. The U.S. DOE is supporting multiple teams to investigate a number of technologies that may improve fuel system response and behavior in accident conditions, with team leadership provided by DOE national laboratories, universities, and the nuclear industry. Concepts under consideration offer both evolutionary and revolutionary changes to the current nuclear fuel system. Mature concepts will be tested in the Advanced Test Reactor at Idaho National Laboratory beginning in Summer 2014 with additional concepts being
Evaluation Metrics Applied to Accident Tolerant Fuels
International Nuclear Information System (INIS)
The safe, reliable, and economic operation of the nation's nuclear power reactor fleet has always been a top priority for the United States' nuclear industry. Continual improvement of technology, including advanced materials and nuclear fuels, remains central to the industry's success. Decades of research combined with continual operation have produced steady advancements in technology and have yielded an extensive base of data, experience, and knowledge on light water reactor (LWR) fuel performance under both normal and accident conditions. One of the current missions of the US. Department of Energy's (DOE) Office of Nuclear Energy (NE) is to develop nuclear fuels and claddings with enhanced accident tolerance characteristics for use in the current fleet of commercial LWRs or in reactor concepts with design certifications (GEN-III+). LWR fuel with accident tolerant characteristics became a focus within advanced LWR research following the 2011 Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex, and upon receiving direction from Congress. The overall goal of ATF development is to identify alternative fuel system technologies to further enhance the safety, competitiveness and economics of commercial nuclear power. Enhanced accident tolerant fuels would endure loss of active cooling in the reactor core for a considerably longer period of time than the current fuel system while maintaining or improving performance during normal operations. The US. DOE is supporting multiple teams to investigate a number of technologies that may improve fuel system response and behaviour in accident conditions, with team leadership provided by DOE national laboratories, universities, and the nuclear industry. Concepts under consideration offer both evolutionary and revolutionary changes to the current nuclear fuel system. Mature concepts will be tested in the Advanced Test Reactor at Idaho National
Radioactive material accidents in the transport
International Nuclear Information System (INIS)
Transport is an important part of the worldwide nuclear industry and the safety record for nuclear transport across the world is excellent. The increase in the use of radioactive materials in our country requires that these materials be moved from production sites to the end user. Despite the number of packages transported, the number of incidents and accidents in which they are involved is low. In Brazil, do not be records of victims of the radiation as a result of the transport of radioactive materials and either due to the accidents happened during the transports. The absence of victims of the radiation as result of accidents during the transports is a highly significant fact, mainly to consider that annually approximately two hundred a thousand packages containing radioactive material are consigned for transport throughout the country, of which eighty a thousand are for a medical use. This is due to well-founded regulations developed by governmental and intergovernmental organizations and to the professionalism of those in the industry. In this paper, an overview is presented of the activities related to the transport of radioactive material in the state of Sao Paulo. The applicable legislation, the responsibilities and tasks of the competent authorities are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. It also presents the packages amounts of carried and the accidents occurred during the transport of radioactive materials, in the last five years. The main occurred events are argued, demonstrating that the demanded requirements of security for any transport of radioactive material are enough to guarantee the necessary control of ionizing radiation expositions to transport workers, members of general public and the environment. (author)
Applying Functional Modeling for Accident Management of Nuclear Power Plant
Energy Technology Data Exchange (ETDEWEB)
Lind, Morten; Zhang Xinxin [Harbin Engineering University, Harbin (China)
The paper investigate applications of functional modeling for accident management in complex industrial plant with special reference to nuclear power production. Main applications for information sharing among decision makers and decision support are identified. An overview of Multilevel Flow Modeling is given and a detailed presentation of the foundational means-end concepts is presented and the conditions for proper use in modelling accidents are identified. It is shown that Multilevel Flow Modeling can be used for modelling and reasoning about design basis accidents. Its possible role for information sharing and decision support in accidents beyond design basis is also indicated. A modelling example demonstrating the application of Multilevel Flow Modelling and reasoning for a PWR LOCA is presented.
Psychophysiological and other factors affecting human performance in accident prevention and investigation
International Nuclear Information System (INIS)
Psychophysiological factors are not uncommon terms in the aviation incident/accident investigation sequence where human error is involved. It is highly suspect that the same psychophysiological factors may also exist in the industrial arena where operator personnel function; but, there is little evidence in literature indicating how management and subordinates cope with these factors to prevent or reduce accidents. It is apparent that human factors psychophysological training is quite evident in the aviation industry. However, while the industrial arena appears to analyze psychophysiological factors in accident investigations, there is little evidence that established training programs exist for supervisors and operator personnel
Systematic register of nuclear accidents
International Nuclear Information System (INIS)
The Systematic Register of Nuclear Accidents is a consolidation of important accidents occurred in the world during the period 1945-1984. Important accidents can be defined as those involving high radiation doses, which require the exposed individuals to undergo medical treatment. The organization and structuring of this register rests on the necessity for the availability of a database specifically oriented to researchers interested in studying the different nuclear accidents reported. Approximately 150 accidents in that period are presented in a summary form; these accidents had been described or reported in the scientific literature or made known through informal communications of Brazilian and foreign institutions and researchers. This register can be of interest particularly to all professionals who either directly of indirectly work in the area of nuclear or radioactive installations safety. In order to facilitate analysis by the researcher, that casuistic system was divided into 3 groups: criticality accidents (table I), fall-out on Marshall Islands (table II) and external irradiation accidents (table III). It is also included an overview of accidents in that period, indicating the total number of victims, fatal cases, and number of survivors. The author offers to the reader an extensive bibliography on the accidents described. (Author)
Analysis of causes and sequences of the accident on Fukushima NPP as a factor of sever accidents prevention in the vessel reactor
International Nuclear Information System (INIS)
In this monograph, the provisional analysis of the causes and sequences of the sever accidents on the Fukushima NPP is presented. The analysis of the possibility of the origin of extreme events connected with the flooding of Zaporizhzhia NPP industrial site, emergency of the steam-gas explosions on NPPs with WWER and other phenomena occurred under sever accidents was carried out. It was presented the authors original working-out on symptom-oriented approaches of sever accident initiating event list identification, on criteria substantiation of explosion safety and optimization of processes management at sever accidents, as well as on the methodological support of the accident beyond the design basis management at the WWER for prevention of their transition in the stage of sever accidents.
Criticality accident in uranium fuel processing plant. Progress and reflection of the criticality accident in the uranium fuel processing plant
International Nuclear Information System (INIS)
As one year is already passing since forming of the JCO criticality accident, impact given by this accident was so large as to vibrate all of nuclear energy field. This accident was the first instantly forming criticality accident since beginning of peaceful use in nuclear energy in Japan, which formed some severe victims containing two dead and an experienced affair required for evacuation and shelter of the peripheral inhabitants. Direct cause of the instantly forming criticality accident in this accident is simple and clear, and is caused by failure in the most essential technology specific to nuclear energy called by criticality management. And that, it was caused not by instrument accident or human individual error but by recent exceptional blunder in and out of Japan at a point of direct reason on evil violation act due to management organization. And, for the response specific to the nuclear energy field, a drastic reinvestigation on safety filed, a drastic reinvestigation on safety regulation system is also required. On the other hand, in nuclear safety education requiring establishment of safety culture for its foundation, a reflection that it has remained only to moral action to bring a result to suppress power carrying out its practice inversely, was also recognized. And, it is necessary to carry out more efforts and devices for difficulty on management forecast in future in nuclear energy industry not so as to make a system of safety conservation weaker. (G.K.)
[Accident cause masculinity?--Gender-related issues of accident victims between prevention and coping in Kaiserreich and Weimarer Republik].
Knoll-Jung, Sebastian
Occupational accidents in industrial workplaces are a specific health problem for man. Therefore it seems adequate to use masculinities as a category of research in this field. For the Kaiserreich and the Weimarer Republik it shows that male workers relating to their danger awareness and behavior, prevention, accident causes and coping strategies are settled in an area of conflict between a hard workplace environment and the family. On the basis of health practices of the accident victims it appears that there are different forms of labor masculinities. They have an important influence on all levels of an occupational accident from the endangerment to the success of the treatment. Through a critical use of the category academic void can be shown and alternative explanatory models can be offered.
Accident management insights after the Fukushima Daiichi NPP accident
International Nuclear Information System (INIS)
The Fukushima Daiichi nuclear power plant (NPP) accident, that took place on 11 March 2011, initiated a significant number of activities at the national and international levels to reassess the safety of existing NPPs, evaluate the sufficiency of technical means and administrative measures available for emergency response, and develop recommendations for increasing the robustness of NPPs to withstand extreme external events and beyond design basis accidents. The OECD Nuclear Energy Agency (NEA) is working closely with its member and partner countries to examine the causes of the accident and to identify lessons learnt with a view to the appropriate follow-up actions to be taken by the nuclear safety community. Accident management is a priority area of work for the NEA to address lessons being learnt from the accident at the Fukushima Daiichi NPP following the recommendations of Committee on Nuclear Regulatory Activities (CNRA), Committee on the Safety of Nuclear Installations (CSNI), and Committee on Radiation Protection and Public Health (CRPPH). Considering the importance of these issues, the CNRA authorised the formation of a task group on accident management (TGAM) in June 2012 to review the regulatory framework for accident management following the Fukushima Daiichi NPP accident. The task group was requested to assess the NEA member countries needs and challenges in light of the accident from a regulatory point of view. The general objectives of the TGAM review were to consider: - enhancements of on-site accident management procedures and guidelines based on lessons learnt from the Fukushima Daiichi NPP accident; - decision-making and guiding principles in emergency situations; - guidance for instrumentation, equipment and supplies for addressing long-term aspects of accident management; - guidance and implementation when taking extreme measures for accident management. The report is built on the existing bases for capabilities to respond to design basis
International Nuclear Information System (INIS)
Following the accident at Chernobyl nuclear reactor, WHO organized on 6 May 1986 in Copenhagen a one day consultation of experts with knowledge in the fields of meteorology, radiation protection, biological effects, reactor technology, emergency procedures, public health and psychology in order to analyse the development of events and their consequences and to provide guidance as to the needs for immediate public health action. The present report provides detailed information on the transportation and dispersion of the radioactive material in the atmosphere, especially volatile elements, during the release period 26 April - 5 May. Presented are the calculated directions and locations of the radioactive plume over Europe in the first 5 days after the accident, submitted by the Swedish Meteorological and Hydrological Institute. The calculations have been made for two heights, 1500m and 750m and the plume directions are grouped into five periods, covering five European areas. The consequences of the accident inside the USSR and the radiological consequences outside the USSR are presented including the exposure routes and the biological effects, paying particular attention to iodine-131 effects. Summarized are the first reported measured exposure rates above background, iodine-131 deposition and concentrations in milk and the remedial actions taken in various European countries. Concerning the cesium-137 problem, based on the UNSCEAR assessment of the consequences of the nuclear fallout, one concludes that the cesium contamination outside the USSR is not likely to cause any serious problems. Finally, the conclusions and the recommendations of the meeting, taking into account both the short-term and longer term considerations are presented
International Nuclear Information System (INIS)
RBMK reactors (reactor control, protection systems, containment) and the nuclear power plant of Chernobyl are first presented. The scenario of the accident is given with a detailed chronology. The actions and consequences on the site are reviewed. This report then give the results of the source term estimation (fision product release, core inventory, trajectories, meteorological data...), the radioactivity measurements obtained in France. Health consequences for the French population are evoked. The medical consequences for the population who have received a high level of doses are reviewed
International Nuclear Information System (INIS)
The bibliography contains 1568 descriptions of papers devoted to Chernobylsk accident and recorded in ''INIS Atomindex'' to 30 June 1990. The descriptions were taken from ''INIS Atomindex'' and are presented in accordance with volumes of this journal (chronology of recording). Therefore all descriptions have numbers showing first the number of volume and then the number of record. The bibliography has at the end the detailed subject index consisting of 465 main headings and a lot of qualifiers. Some of them are descriptors taken from ''INIS Atomindex'' and some are key words taken from natural language. The index is in English as descriptions in the bibliography. (author)
Guidance on accidents involving radioactivity
International Nuclear Information System (INIS)
This annex contains advice to Health Authorities on their response to accidents involving radioactivity. The guidance is in six parts:-(1) planning the response required to nuclear accidents overseas, (2) planning the response required to UK nuclear accidents a) emergency plans for nuclear installations b) nuclear powered satellites, (3) the handling of casualties contaminated with radioactive substances, (4) background information for dealing with queries from the public in the event of an accident, (5) the national arrangements for incident involving radioactivity (NAIR), (6) administrative arrangements. (author)
1976 Hanford americium accident
Energy Technology Data Exchange (ETDEWEB)
Heid, K R; Breitenstein, B D; Palmer, H E; McMurray, B J; Wald, N
This report presents the 2.5-year medical course of a 64-year-old Hanford nuclear chemical operator who was involved in an accident in an americium recovery facility in August 1976. He was heavily externally contaminated with americium, sustained a substantial internal deposition of this isotope, and was burned with concentrated nitric acid and injured by flying debris about the face and neck. The medical care given the patient, including the decontamination efforts and clinical laboratory studies, are discussed. In-vivo measurements were used to estimate the dose rates and the accumulated doses to body organs. Urinary and fecal excreta were collected and analyzed for americium content. Interpretation of these data was complicated by the fact that the intake resulted both from inhalation and from solubilization of the americium embedded in facial tissues. A total of 1100 ..mu..Ci was excreted in urine and feces during the first 2 years following the accident. The long-term use of diethylenetriaminepentate (DTPA), used principally as the zinc salt, is discussed including the method, route of administration, and effectiveness. To date, the patient has apparently experienced no complications attributable to this extensive course of therapy, even though he has been given approximately 560 grams of DTPA. 4 figures, 1 table.
Government: Nuclear Safety in Doubt a Year after Accident.
Ember, Lois R.
A year after the accident at Three Mile Island (TMI), the signals transmitted to the public are still confused. Industry says that nuclear power is safe and that the aftermath of TMI ushers in a new era of safety. Antinuclear activists say TMI sounded nuclear power's death knell. (Author/RE)
Zero Accident Vision based strategies in organisations: Innovative perspectives
Zwetsloot, G.I.J.M.; Kines, P.; Wybo, J.L.; Ruotsala, R.; Drupsteen, L.; Bezemer, R.A.
The Zero Accident Vision (ZAV) is a promising approach developed in industry, but not so much addressed by the safety science research community. In a discussion paper in Safety Science (2013) a call was made for more research in this area. Three years later is a good time to take status of developm
Psychological distress and post-traumatic symptoms following occupational accidents.
Ghisi, Marta; Novara, Caterina; Buodo, Giulia; Kimble, Matthew O; Scozzari, Simona; Di Natale, Arianna; Sanavio, Ezio; Palomba, Daniela
Depression and post-traumatic stress disorder frequently occur as a consequence of occupational accidents. To date, research has been primarily focused on high-risk workers, such as police officers or firefighters, and has rarely considered individuals whose occupational environment involves the risk of severe, but not necessarily life-threatening, injury. Therefore, the present study was aimed at assessing the psychological consequences of accidents occurring in several occupational settings (e.g., construction and industry). Thirty-eight victims of occupational accidents (injured workers) and 38 gender-, age-, and years of education-matched workers who never experienced a work accident (control group) were recruited. All participants underwent a semi-structured interview administered by a trained psychologist, and then were requested to fill in the questionnaires. Injured workers reported more severe anxious, post-traumatic and depressive symptoms, and poorer coping skills, as compared to controls. In the injured group low levels of resilience predicted post-traumatic symptomatology, whereas the degree of physical injury and the length of time since the accident did not play a predictive role. The results suggest that occupational accidents may result in a disabling psychopathological condition, and that a brief psychological evaluation should be included in the assessment of seriously injured workers. PMID:25379258
Health Problems in Radiation Accidents
International Nuclear Information System (INIS)
The authors define a radiation accident as a situation which has led or could have led to the unexpected irradiation of persons or contamination of the environment over and above the levels accepted as safe. Several categories of accidents are distinguished as a function of the consequences to be expected. The suggested system of classifying accidents makes it possible to plan post-accident measures within a single system of 'concentric circles', taking into account at the same time whether it will be possible to carry out the post-accident measures unaided or whether it will be necessary to bring in additional manpower and resources from outside. The authors consider the possibility of countering the effects of accidents as a function of their nature, with reference to the biological, economic and psychological aspects. They evaluate the part played by the health service in planning and carrying out accident prevention measures, and consider the function of radiological units attached to epidemiological health stations ; these units are essentially centres providing for precautionary measures to avert accidents and action to counter their effects. (author)
Containment severe accident thermohydraulic phenomena
International Nuclear Information System (INIS)
This report describes and discusses the containment accident progression and the important severe accident containment thermohydraulic phenomena. The overall objective of the report is to provide a rather detailed presentation of the present status of phenomenological knowledge, including an account of relevant experimental investigations and to discuss, to some extent, the modelling approach used in the MAAP 3.0 computer code. The MAAP code has been used in Sweden as the main tool in the analysis of severe accidents. The dependence of the containment accident progression and containment phenomena on the initial conditions, which in turn are heavily dependent on the in-vessel accident progression and phenomena as well as associated uncertainties, is emphasized. The report is in three parts dealing with: * Swedish reactor containments, the severe accident mitigation programme in Sweden and containment accident progression in Swedish PWRs and BWRs as predicted by the MAAP 3.0 code. * Key non-energetic ex-vessel phenomena (melt fragmentation in water, melt quenching and coolability, core-concrete interaction and high temperature in containment). * Early containment threats due to energetic events (hydrogen combustion, high pressure melt ejection and direct containment heating, and ex-vessel steam explosions). The report concludes that our understanding of the containment severe accident progression and phenomena has improved very significantly over the parts ten years and, thereby, our ability to assess containment threats, to quantify uncertainties, and to interpret the results of experiments and computer code calculations have also increased. (au)
Preventing accidents at intake towers
Energy Technology Data Exchange (ETDEWEB)
Villegas, F. (INTEGRAL S.A., Medellin, CO (United States))
Strong air blow-outs occurring in the intake tower of Guatape Hydroelectric Power Plant in Colombia have caused two serious accidents recently. The causes of the accidents were investigated and recommendations are made here to prevent future repetitions of these dangerous events. (UK)
Industrial Education Safety Guide.
California State Dept. of Education, Sacramento.
California is one of the few states in which school districts have a legal responsibility for accidents involving students while they are participating in assigned school activities. This guide was prepared to help school administrators and teachers evaluate their safety instruction programs and industrial education facilities in accordance with…
Probability of spent fuel transportation accidents
Energy Technology Data Exchange (ETDEWEB)
McClure, J. D.
The transported volume of spent fuel, incident/accident experience and accident environment probabilities were reviewed in order to provide an estimate of spent fuel accident probabilities. In particular, the accident review assessed the accident experience for large casks of the type that could transport spent (irradiated) nuclear fuel. This review determined that since 1971, the beginning of official US Department of Transportation record keeping for accidents/incidents, there has been one spent fuel transportation accident. This information, coupled with estimated annual shipping volumes for spent fuel, indicated an estimated annual probability of a spent fuel transport accident of 5 x 10/sup -7/ spent fuel accidents per mile. This is consistent with ordinary truck accident rates. A comparison of accident environments and regulatory test environments suggests that the probability of truck accidents exceeding regulatory test for impact is approximately 10/sup -9//mile.
Analysis of the radiation accident in El Salvador
International Nuclear Information System (INIS)
On 5 February 1989 at 2 a.m. local time in a cobalt-60 industrial irradiation facility, a series of events started leading to one of the most serious radiation accidents in this type of installation. It took place in Soyapango, a city situated 5 km from San Salvador, the capital of the Republic of El Salvador. In this accident, three workers were involved in the first event and a further four in the second. When the accident took place, the activity level was approximately 0.66 PBq (18,000 Ci). The source became blocked when being lowered to its safe position, where upon the technician responsible for the irradiator entered the chamber in breach of the few inadequate safety procedures, accompanied by two colleagues from an adjacent department; the three workers suffered acute radiation exposure, with the result that one of them died six-and-a-half months later, the second had both his legs amputated at mid-thigh, while the third recovered completely. This article describes the irradiator, outlines the causes of the accident and analyses the economic and social repercussions, with the aim of helping teams responsible for radiation protection and safety in industrial irradiation facilities to identify potentially hazardous circumstances and avoid accidents. (author)
Industries and environment - 2014 edition
International Nuclear Information System (INIS)
After a general overview of the French economic context (composition of the French industry, the manufacturing industry, industry production and trade balance), this report presents industrial installations with risks: installations classified for the protection of the environment and submitted to industrial authorizations (ICPEA), basic nuclear installations, Seveso industrial facilities, IPPC industrial installations. The next part analyzes the various pressures exerted by the industry on the environment: material production and consumption, water taking, consumption of energetic products, release of pollutants in waters of industrial ICPE, releases in the air, greenhouse gas emissions, production of wastes, accidents and incidents with environmental consequences, polluted sites and soils, hazardous chemical products in the industry, industrial companies involved in nano-technologies and nano-materials. The last part proposes an overview of responses to these issues: implementation of environmental management system, corporate societal responsibility, investments and expenditures for the protection of the environment, industrial eco-activities, eco-labelled products manufactured by the industry
Directory of Open Access Journals (Sweden)
K Nasseri
Full Text Available A total of 38, 300 traffic collisions have occurred in Tehran, the capital of Iran, during 1973. 5, 655 of these collisions in 6, 700 injuries and 560 deaths are selected and discussed. There has been no difference between the accident rates in working and holidays. Winter has had the lowest rate, and accidents have been in direct relationship with the crowdedness and heavy traffic periods. Ninety – eight per cent of the accidents have been caused by either the drivers or the pedestrians' negligence. These and other findings are discussed.
Economic risks of nuclear power reactor accidents
International Nuclear Information System (INIS)
Models to be used for analyses of economic risks from events which occur during US LWR plant operation are developed in this study. The models include capabilities to estimate both onsite and offsite costs of LWR events ranging from routine plant forced outages to severe core-melt accidents resulting in large releases of radioactive material to the environment. The models have been developed for potential use by both the nuclear power industry and regulatory agencies in cost/benefit analyses for decision-making purposes. The new onsite cost models estimate societal losses from power production cost increases, plant capital losses, plant decontamination costs, and plant repair costs which may be incurred after LWR operational events. Early decommissioning costs, plant worker health impact costs, electric utility business costs, nuclear power industry costs, and litigation costs are also addressed. The newly developed offsite economic consequence models estimate The costs of post-accident population protective measures and public health impacts. The costs of population evacuation and temporary relocation, agricultural product disposal, land and property decontamination, and land interdiction are included in the economic models for population protective measures. Costs of health impacts and medical care costs are also included in the models
Severe accident analysis code Sampson for impact project
Energy Technology Data Exchange (ETDEWEB)
Hiroshi, Ujita; Takashi, Ikeda; Masanori, Naitoh [Nuclear Power Engineering Corporation, Advanced Simulation Systems Dept., Tokyo (Japan)
Four years of the IMPACT project Phase 1 (1994-1997) had been completed with financial sponsorship from the Japanese government's Ministry of Economy, Trade and Industry. At the end of the phase, demonstration simulations by combinations of up to 11 analysis modules developed for severe accident analysis in the SAMPSON Code were performed and physical models in the code were verified. The SAMPSON prototype was validated by TMI-2 and Phebus-FP test analyses. Many of empirical correlation and conventional models have been replaced by mechanistic models during Phase 2 (1998-2000). New models for Accident Management evaluation have been also developed. (author)
Handling of Radiation Accidents. Proceedings of a Symposium on the Handling of Radiation Accidents
International Nuclear Information System (INIS)
Many types of radiation accidents can theoretically be foreseen, ranging from minor spills of radioactive materials within a laboratory to serious accidents characterized by the presence of intense radiation fields and the uncontrolled release of large quantities of radioactive contaminants. They could lead to the irradiation and contamination of persons and the contamination of premises and the natural environment. As a result of the great emphasis that has been placed on safety in the development of nuclear energy programmes and in the use of radiation sources, accidents involving the serious overexposure of persons are in fact very rare. Nevertheless such accidents can occur and it is necessary to plan in advance for those that can be,reasonably foreseen. The handling of serious radiation accidents requires the co-operation of experts with diverse qualifications and experience: radiation monitoring and dosimetry specialists; medical doctors experienced in diagnosing and treating radiation injury; nuclear safety, decontamination and waste management specialists; public relations officers; and many others. This symposium, organized by the International Atomic Energy Agency and the World Health Organization as part of a co-ordinated programme, was designed to enable these specialists to discuss their problems on a very broad basis. The meeting was attended by 212 participants from 34 countries and 9 international organizations. In his opening address Professor Zheludev reminded the participants that the good safety record of the nuclear industry must not give rise to complacency and that we must all learn as much as possible from reported accidents in order to be ready to deal promptly and effectively with those that may be encountered in the future. It is noteworthy that some of the most severe injuries reported were suffered by persons who found lost-sources and carried them for long periods without any knowledge of the dangers involved. Organizational
International aspects of nuclear accidents
International Nuclear Information System (INIS)
The accident at Chernobyl revealed that there were shortcomings and gaps in the existing international mechanisms and brought home to governments the need for stronger measures to provide better protection against the risks of severe accidents. The main thrust of international co-operation with regard to nuclear safety issues is aimed at achieving a uniformly high level of safety in nuclear power plants through continuous exchanges of research findings and feedback from reactor operating experience. The second type of problem posed in the event of an accident resulting in radioactive contamination of several countries relates to the obligation to notify details of the circumstances and nature of the accident speedily so that the countries affected can take appropriate protective measures and, if necessary, organize mutual assistance. Giving the public accurate information is also an important aspect of managing an emergency situation arising from a severe accident. Finally, the confusion resulting from the unwarranted variety of protective measures implemented after the Chernobyl accident has highlighted the need for international harmonization of the principles and scientific criteria applicable to the protection of the public in the event of an accident and for a more consistent approach to emergency plans. The international conventions on third party liability in the nuclear energy sector (Paris/Brussels Conventions and the Vienna Convention) provide for compensation for damage caused by nuclear accidents in accordance with the rules and jurisdiction that they lay down. These provisions impose obligations on the operator responsible for an accident, and the State where the nuclear facility is located, towards the victims of damage caused in another country
Review of five investigation committees' reports on the Fukushima Dai-ichi Nuclear Power Plant severe accident. Focusing on accident progression and causes
International Nuclear Information System (INIS)
On March 11, 2011, the Tohoku District-off the Pacific Ocean Earthquake and the subsequent tsunami resulted in the severe core damage at TEPCO's Fukushima Dai-ichi Nuclear Power Station Units 1-3, involving hydrogen explosions at Units 1, 3, and 4 and the large release of radioactive materials to the environment. Four independent committees were established by the Japanese government, the Diet of Japan, the Rebuild Japan Initiative Foundation, and TEPCO to investigate the accident and published their respective reports. Also, the Nuclear and Industrial Safety Agency carried out an analysis of accident causes to obtain the lessons learned from the accident and made its report public. This article reviews the reports and clarifies the differences in their positions, from the technological point of view, focusing on the accident progression and causes. Moreover, the undiscussed issues are identified to provide insights useful for the near-term regulatory activities including accident investigation by the Nuclear Regulation Authority. (author)
Safety Considerations in the Chemical Process Industries
Englund, Stanley M.
There is an increased emphasis on chemical process safety as a result of highly publicized accidents. Public awareness of these accidents has provided a driving force for industry to improve its safety record. There has been an increasing amount of government regulation.
Systematic approach for assessment of accident risks in chemical and nuclear processing
International Nuclear Information System (INIS)
The industrial accidents which occurred in the last years, particularly in the 80's, contributed a significant way to draw the attention of the government, industry and the society as a whole to the mechanisms for preventing events that could affect people's safety and the environment quality. Techniques and methods extensively used the nuclear, aeronautic and war industries so far were adapted to performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. The risk analysis in industrial facilities is carried out through the evaluation of the probability or frequency of the accidents and their consequences. However, no systematized methodology that could supply the tools for identifying possible accidents likely to take place in an installation is available in the literature. Neither existing are methodologies for the identification of the models for evaluation of the accidents' consequences nor for the selection of the available techniques for qualitative or quantitative analysis of the possibility of occurrence of the accident being focused. The objective of this work is to develop and implement a methodology for identification of the risks of accidents in chemical and nuclear processing facilities as well as for the evaluation of their consequences on persons. For the development of the methodology, the main possible accidents that could occur in such installations were identified and the qualitative and quantitative techniques available for the identification of the risks and for the evaluation of the consequences of each identified accidents were selected. The use of the methodology was illustrated by applying it in two case examples adapted from the literature, involving accidents with inflammable, explosives, and radioactive materials. The computer code MRA - Methodology for Risk Assessment was developed using DELPHI, version 5.0, with the purpose of systematizing
[Prevention of bicycle accidents].
Zwipp, H; Barthel, P; Bönninger, J; Bürkle, H; Hagemeister, C; Hannawald, L; Huhn, R; Kühn, M; Liers, H; Maier, R; Otte, D; Prokop, G; Seeck, A; Sturm, J; Unger, T
For a very precise analysis of all injured bicyclists in Germany it would be important to have definitions for "severely injured", "seriously injured" and "critically injured". By this, e.g., two-thirds of surgically treated bicyclists who are not registered by the police could become available for a general analysis. Elderly bicyclists (> 60 years) are a minority (10 %) but represent a majority (50 %) of all fatalities. They profit most by wearing a helmet and would be less injured by using special bicycle bags, switching on their hearing aids and following all traffic rules. E-bikes are used more and more (145 % more in 2012 vs. 2011) with 600,000 at the end of 2011 and are increasingly involved in accidents but still have a lack of legislation. So even for pedelecs 45 with 500 W and a possible speed of 45 km/h there is still no legislative demand for the use of a protecting helmet. 96 % of all injured cyclists in Germany had more than 0.5 ‰ alcohol in their blood, 86 % more than 1.1 ‰ and 59 % more than 1.7 ‰. Fatalities are seen in 24.2 % of cases without any collision partner. Therefore the ADFC calls for a limit of 1.1 ‰. Some virtual studies conclude that integrated sensors in bicycle helmets which would interact with sensors in cars could prevent collisions or reduce the severity of injury by stopping the cars automatically. Integrated sensors in cars with opening angles of 180° enable about 93 % of all bicyclists to be detected leading to a high rate of injury avoidance and/or mitigation. Hanging lamps reduce with 35 % significantly bicycle accidents for children, traffic education for children and special trainings for elderly bicyclists are also recommended as prevention tools. As long as helmet use for bicyclists in Germany rates only 9 % on average and legislative orders for using a helmet will not be in force in the near future, coming up campaigns seem to be necessary to be promoted by the Deutscher
[Prevention of bicycle accidents].
Zwipp, H; Barthel, P; Bönninger, J; Bürkle, H; Hagemeister, C; Hannawald, L; Huhn, R; Kühn, M; Liers, H; Maier, R; Otte, D; Prokop, G; Seeck, A; Sturm, J; Unger, T
For a very precise analysis of all injured bicyclists in Germany it would be important to have definitions for "severely injured", "seriously injured" and "critically injured". By this, e.g., two-thirds of surgically treated bicyclists who are not registered by the police could become available for a general analysis. Elderly bicyclists (> 60 years) are a minority (10 %) but represent a majority (50 %) of all fatalities. They profit most by wearing a helmet and would be less injured by using special bicycle bags, switching on their hearing aids and following all traffic rules. E-bikes are used more and more (145 % more in 2012 vs. 2011) with 600,000 at the end of 2011 and are increasingly involved in accidents but still have a lack of legislation. So even for pedelecs 45 with 500 W and a possible speed of 45 km/h there is still no legislative demand for the use of a protecting helmet. 96 % of all injured cyclists in Germany had more than 0.5 ‰ alcohol in their blood, 86 % more than 1.1 ‰ and 59 % more than 1.7 ‰. Fatalities are seen in 24.2 % of cases without any collision partner. Therefore the ADFC calls for a limit of 1.1 ‰. Some virtual studies conclude that integrated sensors in bicycle helmets which would interact with sensors in cars could prevent collisions or reduce the severity of injury by stopping the cars automatically. Integrated sensors in cars with opening angles of 180° enable about 93 % of all bicyclists to be detected leading to a high rate of injury avoidance and/or mitigation. Hanging lamps reduce with 35 % significantly bicycle accidents for children, traffic education for children and special trainings for elderly bicyclists are also recommended as prevention tools. As long as helmet use for bicyclists in Germany rates only 9 % on average and legislative orders for using a helmet will not be in force in the near future, coming up campaigns seem to be necessary to be promoted by the Deutscher
Ranking of severe accident research priorities
Energy Technology Data Exchange (ETDEWEB)
Schwinges, B. [Gesell Anlagen and Reaktorsicherheit GRS mbH, D-50667 Cologne (Germany); Journeau, C. [CEA Cadarache, DEN STRI LMA, F-13115 St Paul Les Durance (France); Haste, T. [Paul Scherrer Inst, NES LTH, OVGA 312, CH-5232 Villigen (Switzerland); Meyer, L.; Tromm, W. [Forschungszentrum Karlsruhe, D-76021 Karlsruhe (Germany); Trambauer, K. [GRS mbH, Forschungsgelande, D-85748 Garching (Germany)
The objectives of the SARNET network are to define common research programmes in the field of severe accidents and to develop common computer tools and methodologies for safety assessment in this field. To reach these objectives, one of the work packages, named 'Severe Accident Research Priorities' (SARP), aimed at reviewing and reassessing the priorities of research issues as a basis to harmonize and to re-orient research programmes, to define new ones, and to close - if possible - resolved issues on a common basis. The work was performed in close collaboration with 8 participating institutions, led by GRS, representing technical safety organisations, industry and utilities (IRSN, CEA, EDF, FZK, GRS, KTH, TUS, VTT). This action made use notably of (1) the outcomes of the EURSAFE project in the 5. Framework Programme, i. e. the Phenomena Identification and Ranking Tables (PIRT) on severe accidents, (2) the results of the validation and benchmarking activities on ASTEC, (3) the results of reactor calculations carried out in the other SARNET tasks, and (4) the outcome of the research performed in the three thematic sub-domains of SARNET (corium, containment and source term). The main outcome of EURSAFE was a list of 21 topics which included recommendations for experimental programmes and code developments. This list formed the basis of the work in SARP. Also the methodology applied in EURSAFE to consider both the risk potential and the severe accident issues where large uncertainties still subsist was adopted. The analyses of the progress of research and development activities considered whether (1) any research issue was resolved due to reduction of uncertainties or gain of scientific insights, (2) any new issue had to be added to the list of needed research, (3) any new process or phenomenon had to be included in the general PIRT list taking into account the safety relevance and the lack of knowledge, and (4) any new accident management program has to be
A Tool for Safety Officers Investigating " simple" Accidents
DEFF Research Database (Denmark)
Jørgensen, Kirsten
Most workplace accidents that happen in enterprises are simple and seldom result in serious injuries. Very often these kinds of workplace accidents are not investigated, and if they are, then the investigation is very brief, with comments such as that it was the victim's own fault or just...... an unfortunate situation which could not be helped. Most prevention analysis and investigation methods focus on high risks, such as explosion, fire, lack of containment for chemicals, etc. In the industrial world, such risks do give rise to disasters, albeit very seldom. Nevertheless, the fact is that simpler...... on the investigation methods applied in major accidents, but comprises a simpler and more user-friendly presentation. The tool involves three steps: Mapping the facts, analysing the events, and developing preventive solutions. Practical application of the tool has shown that it affords managers and workers...
Three Mile Island Accident Data
National Oceanic and Atmospheric Administration, Department of Commerce — Three Mile Island Accident Data consists of mostly upper air and wind observations immediately following the nuclear meltdown occurring on March 28, 1979, near...
29 CFR 1960.29 - Accident investigation.
... 29 Labor 9 2010-07-01 2010-07-01 false Accident investigation. 1960.29 Section 1960.29 Labor... MATTERS Inspection and Abatement § 1960.29 Accident investigation. (a) While all accidents should be investigated, including accidents involving property damage only, the extent of such investigation shall...
49 CFR 195.54 - Accident reports.
... 49 Transportation 3 2010-10-01 2010-10-01 false Accident reports. 195.54 Section 195.54... PIPELINE Annual, Accident, and Safety-Related Condition Reporting § 195.54 Accident reports. (a) Each operator that experiences an accident that is required to be reported under § 195.50 shall as soon...
49 CFR 801.32 - Accident reports.
... 49 Transportation 7 2010-10-01 2010-10-01 false Accident reports. 801.32 Section 801.32... PUBLIC AVAILABILITY OF INFORMATION Accident Investigation Records § 801.32 Accident reports. (a) The NTSB....S. civil transportation accidents, in accordance with 49 U.S.C. 1131(e). (b) These reports may...
The measurement of accident-proneness
As, Sicco van
This paper deals with the measurement of accident-proneness. Accidents seem easy to observe, however accident-proneness is difficult to measure. In this paper I first define the concept of accident-proneness, and I develop an instrument to measure it. The research is mainly executed within chemical
49 CFR 230.22 - Accident reports.
... 49 Transportation 4 2010-10-01 2010-10-01 false Accident reports. 230.22 Section 230.22... Requirements § 230.22 Accident reports. In the case of an accident due to failure, from any cause, of a steam... persons, the railroad on whose line the accident occurred shall immediately make a telephone report of...
49 CFR 845.40 - Accident report.
... 49 Transportation 7 2010-10-01 2010-10-01 false Accident report. 845.40 Section 845.40... RULES OF PRACTICE IN TRANSPORTATION; ACCIDENT/INCIDENT HEARINGS AND REPORTS Board Reports § 845.40 Accident report. (a) The Board will issue a detailed narrative accident report in connection with...
A review of accidents, prevention and mitigation options related to hazardous gases
International Nuclear Information System (INIS)
Statistics on industrial accidents are incomplete due to lack of specific criteria on what constitutes a release or accident. In this country, most major industrial accidents were related to explosions and fires of flammable materials, not to releases of chemicals into the environment. The EPA in a study of 6,928 accidental releases of toxic chemicals revealed that accidents at stationary facilities accounted for 75% of the total number of releases, and transportation accidents for the other 25%. About 7% of all reported accidents (468 cases) resulted in 138 deaths and 4,717 injuries ranging from temporary respiratory problems to critical injuries. In-plant accidents accounted for 65% of the casualties. The most efficient strategy to reduce hazards is to choose technologies which do not require the use of large quantities of hazardous gases. For new technologies this approach can be implemented early in development, before large financial resources and efforts are committed to specific options. Once specific materials and options have been selected, strategies to prevent accident initiating events need to be evaluated and implemented. The next step is to implement safety options which suppress a hazard when an accident initiating event occurs. Releases can be prevented or reduced with fail-safe equipment and valves, adequate warning systems and controls to reduce and interrupt gas leakage. If an accident occurs and safety systems fail to contain a hazardous gas release, then engineering control systems will be relied on to reduce/minimize environmental releases. As a final defensive barrier, the prevention of human exposure is needed if a hazardous gas is released, in spite of previous strategies. Prevention of consequences forms the final defensive barrier. Medical facilities close by that can accommodate victims of the worst accident can reduce the consequences of personnel exposure to hazardous gases
ANS [American Nuclear Society] topical meeting on radiological accidents: Perspectives and emergency planning: Proceedings
International Nuclear Information System (INIS)
The increasing use of radioactive materials and the increasing public concern about possible accidents involving these materials has led to greater emphasis on preparing for such emergencies. The ANS Topical Meeting on Radiological Accidents - Perspectives and Emergency Planning provided a review of experiences with radiological accidents. The meeting covered some of the most important aspects of radiological accidents. Papers were presented which dealt with radiological accident experience. Technical response to accidents is of primary interest to many in the nuclear community; most of the papers submitted fell into this area. So many of these papers dealt with the use of computers in response that a session on that topic was arranged. A very significant impact of most radiological accidents is the cost, especially the cost of cleanup. There were papers on what is known about costs and associated current topics, such as modification and extension of the Price-Anderson Act. At least as important as the technical response to accidents is how society attempts to deal with them. A session on institutional issues was included to discuss how governments and other organizations respond to and deal with accidents. Medical effects of accidents are of great concern to the public. Invited papers to review the effects of high doses of radiation as well as very low doses were included in that session. Although the nuclear industry has an excellent safety record, this fact often does not agree with the public perception of the industry. The final session explored the public response to and perception of radiological emergencies and accidents. This subject will ultimately determine the future use of radioactive materials in this country
Evaluation of the Relationship between Job Stress and Unsafe Acts with Occupational Accidents in a Vehicle Manufacturing Plant
I. Mohammadfam; Bahrami, A.; F. Fatemi; R Golmohammadi; H. Mahjub
Introduction & Objective: Nowadays the vehicle manufacturing industries in Iran are critical sites as far as occupational accidents are concerned. At the same time, occupational stress and unsafe acts have also been recognized as effective factors in increasing the risk of mental and physical health problems and occupational accidents. The main aim of this research was to evaluate the relationship between job stress and unsafe acts with occupational accidents.Materials & Methods: Data were co...
Nuclear fuel cycle facility accident analysis handbook
International Nuclear Information System (INIS)
The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH
Nuclear fuel cycle facility accident analysis handbook
Energy Technology Data Exchange (ETDEWEB)
Ayer, J E; Clark, A T; Loysen, P; Ballinger, M Y; Mishima, J; Owczarski, P C; Gregory, W S; Nichols, B D
The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH.
CARNSORE: Hypothetical reactor accident study
International Nuclear Information System (INIS)
Two types of design-basis accident and a series of hypothetical core-melt accidents to a 600 MWe reactor are described and their consequences assessed. The PLUCON 2 model was used to calculate the consequences which are presented in terms of individual and collective doses, as well as early and late health consequences. The site proposed for the nucelar power station is Carnsore Point, County Wexford, south-east Ireland. The release fractions for the accidents described are those given in WASH-1400. The analyses are based on the resident population as given in the 1979 census and on 20 years of data from the meteorological stations at Rosslare Harbour, 8.5 km north of the site. The consequences of one of the hypothetical core-melt accidents are described in detail in a meteorological parametric study. Likewise the consequences of the worst conceivable combination of situations are described. Finally, the release fraction in one accident is varied and the consequences of a proposed, more probable ''Class 9 accident'' are presented. (author)
Historical analysis of US pipeline accidents triggered by natural hazards
Girgin, Serkan; Krausmann, Elisabeth
Natural hazards, such as earthquakes, floods, landslides, or lightning, can initiate accidents in oil and gas pipelines with potentially major consequences on the population or the environment due to toxic releases, fires and explosions. Accidents of this type are also referred to as Natech events. Many major accidents highlight the risk associated with natural-hazard impact on pipelines transporting dangerous substances. For instance, in the USA in 1994, flooding of the San Jacinto River caused the rupture of 8 and the undermining of 29 pipelines by the floodwaters. About 5.5 million litres of petroleum and related products were spilled into the river and ignited. As a results, 547 people were injured and significant environmental damage occurred. Post-incident analysis is a valuable tool for better understanding the causes, dynamics and impacts of pipeline Natech accidents in support of future accident prevention and mitigation. Therefore, data on onshore hazardous-liquid pipeline accidents collected by the US Pipeline and Hazardous Materials Safety Administration (PHMSA) was analysed. For this purpose, a database-driven incident data analysis system was developed to aid the rapid review and categorization of PHMSA incident reports. Using an automated data-mining process followed by a peer review of the incident records and supported by natural hazard databases and external information sources, the pipeline Natechs were identified. As a by-product of the data-collection process, the database now includes over 800,000 incidents from all causes in industrial and transportation activities, which are automatically classified in the same way as the PHMSA record. This presentation describes the data collection and reviewing steps conducted during the study, provides information on the developed database and data analysis tools, and reports the findings of a statistical analysis of the identified hazardous liquid pipeline incidents in terms of accident dynamics and
Woodworking injuries: a comparative study of work-related and hobby-related accidents.
Loisel, F; Bonin, S; Jeunet, L; Pauchot, J; Tropet, Y; Obert, L
The primary objective of this study was to describe the injury characteristics and demographics of patients injured during woodworking activities, upon their arrival to the emergency department in a regional of France where this industry is prevalent. The secondary objective was to compare patient and injury characteristics for work-related and hobby-related accidents. A cohort of 87 patients who had suffered a woodworking accident over a two-year period was evaluated; 79 were available for follow-up. The context and circumstances of the accident, nature and location of the injuries and patient demographics were recorded. Hobby-related accidents accounted for two-thirds of the accidents (51/79). Most of the injured workers were either loggers (35%) or carpenters (46%). The hand was injured in 53 cases (67%). Work-related accidents resulted in significantly more serious consequences in terms of hospital stay, work stoppage, resumption of work or retraining than hobby-related accidents. For the workplace accidents, 86% occurred on new machines; more than 25% of the machines involved in accidents at home were over 15 years. Sixty-eight per cent of workers were wearing their safety gear, while only 31% of those injured during recreational woodworking wore the appropriate gear. Several elements of prevention should be improved: information about the need to maintain the equipment, protect the worker with suitable clothing, and learn which maneuvers are considered hazardous. Safety gear should be regularly inspected in the workplace.
Best practices to reduce the accident rate hotel
García Revilla, M. R.; Kahale Carrillo, D. T.
Examining the available databases and existing tourism organizations can conclude that appear studies on accidents and their relationship with other variables. But in our case we want to assess this relationship in the performance of the hotel in relation to lower the accident rate. The Industrial Safety studies analyzing this accident causes (why they happen), their sources (committed activities), their agents (participants work means), its type (how the events occur or develop), all in order to develop prevention. In our case, as accidents happen because people commit wrongful acts or because the equipment, tools, machinery or workplaces are not in proper conditions, the preventive point of view we analyze through the incidence of workplace accidents hotel subsector. The crash occurs because there is a risk, so that adequate control of it would avoid despite individual factors. Absenteeism or absence from work was taken into account first by Dubois in 1977, as he realized the time lost in the nineteenth century due to the long working hours, which included the holidays. Motivation and job satisfaction were the elements that have been most important in the phenomenon of social psychology.
Substance use among Iranian drivers involved in fatal road accidents
Directory of Open Access Journals (Sweden)
Shervin eAssari
Full Text Available Background: Although the problem of substance use among drivers is not limited to a special part of the world, most published epidemiological reports on this topic is from industrial world.Aim: To determine drug use among Iranian adults who were imprisoned for vehicle accidents with fatality. Methods: This study enrolled 51 Iranian adults who were imprisoned for vehicle accidents with fatality. This sample came from a national survey of prisoners. Data was collected at entry to prisons during the last 4 months of 2008 in 7 prisons in different parts of the country. Self reported drug use was registered. Commercial substance use screening tests were also done. Results: Drug test was positive for opioids, cannabis and both in 37.3%, 2.0% and 13.7%, respectively. 29.4% tested positive for benzodiazepines. Using test introduced 23.5% of our sample as drug users, who had declined to report any drug use. Conclusion: Opioids are the most used illicit drug in the case of vehicle accidents with fatality, however, 20% of users do not declare their use. This high rate of drug use in vehicle accidents with fatality reflects the importance of drug use control as a part of injury prevention in Iran. There might be a need for drug screening after severe car accidents.
Emergency planning and preparedness for a nuclear accident
International Nuclear Information System (INIS)
Based on current regulations, FEMA approves each site-specific plan of state and local governments for each power reactor site after 1) formal review offsite preparedness, 2) holding a public meeting at which the preparedness status has been reviewed, and 3) a satisfactory joint exercise has been conducted with both utility and local participation. Annually, each state, within any position of the 10-mile emergency planning zone, must conduct a joint exercise with the utility to demonstrate its preparedness for a nuclear accident. While it is unlikely that these extreme measures will be needed as a result of an accident at a nuclear power station, the fact that these plans have been well thought out and implemented have already proven their benefit to society. The preparedness for a nuclear accident can be of great advantage in other types of emergencies. For example, on December 11, 1982, a non-nuclear chemical storage tank exploded at a Union Carbide plant in Louisiana shortly after midnight. More than 20,000 people were evacuated from their homes. They were evacuated under the emergency response plan formulated for use in the event of a nuclear accident at the nearby Waterford Nuclear plants. Clearly, this illustrates how a plan conceived for one purpose is appropriate to handle other types of accidents that occur in a modern industrial society
Report on the accident at the Chernobyl Nuclear Power Station
International Nuclear Information System (INIS)
This report presents the compilation of information obtained by various organizations regarding the accident (and the consequences of the accident) that occurred at Unit 4 of the nuclear power station at Chernobyl in the USSR on April 26, 1986. Each organization has independently accepted responsibility for one or more chapters. The specific responsibility of each organization is indicated. The various authors are identified in a footnote to each chapter. Very briefly the other chapters cover: the design of the Chernobyl nuclear station Unit 4; safety analyses for Unit 4; the accident scenario; the role of the operator; an assessment of the radioactive release, dispersion, and transport; the activities associated with emergency actions; and information on the health and environmental consequences from the accident. These subjects cover the major aspects of the accident that have the potential to present new information and lessons for the nuclear industry in general. The task of evaluating the information obtained in these various areas and the assessment of the potential implications has been left to each organization to pursue according to the relevance of the subject to their organization. Those findings will be issued separately by the cognizant organizations. The basic purpose of this report is to provide the information upon which such assessments can be made
The Fukushima Daiichi Accident. Technical Volume 1/5. Description and Context of the Accident
International Nuclear Information System (INIS)
This volume presents the key events that happened before, during and after the accident at the Fukushima Daiichi nuclear power plant (NPP), operated by the Tokyo Electric Power Company (TEPCO). The description of the event in this volume is based on objective and factual information, and is presented largely in a chronological manner. The volume also describes the Fukushima Daiichi NPP site, the reactor designs, the structure of the nuclear industry in Japan and the Japanese regulatory framework at the time of the accident. It describes in detail the earthquake, the tsunami, the events at the Fukushima Daiichi NPP and the actions taken there and elsewhere for post-accident management up to December 2014. The description of the events is largely based on information provided by the Government of Japan to the IAEA; reports of the investigation committees established by the Japanese Government, the National Diet of Japan and TEPCO, including updates and supplements by TEPCO; the regulatory body; and the IAEA missions listed in Section 1.6.5. Information is provided without judgement and evaluation, unless it is necessary to clarify a certain occurrence assessments are contained in Technical Volumes 2 to 5
Accident Tolerant Fuel Analysis
Energy Technology Data Exchange (ETDEWEB)
Curtis Smith; Heather Chichester; Jesse Johns; Melissa Teague; Michael Tonks; Robert Youngblood
Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced "RISMC toolkit" that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional "accident-tolerant" (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and
Accident tolerant fuel analysis
Energy Technology Data Exchange (ETDEWEB)
Smith, Curtis [Idaho National Laboratory; Chichester, Heather [Idaho National Laboratory; Johns, Jesse [Texas A& M University; Teague, Melissa [Idaho National Laboratory; Tonks, Michael Idaho National Laboratory; Youngblood, Robert [Idaho National Laboratory
Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced ''RISMC toolkit'' that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional ''accident-tolerant'' (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant
Industrial hazard and safety handbook
King, Ralph W
Industrial Hazard and Safety Handbook (Revised Impression) describes and exposes the main hazards found in industry, with emphasis on how these hazards arise, are ignored, are identified, are eliminated, or are controlled. These hazard conditions can be due to human stresses (for example, insomnia), unsatisfactory working environments, as well as secret industrial processes. The book reviews the cost of accidents, human factors, inspections, insurance, legal aspects, planning for major emergencies, organization, and safety measures. The text discusses regulations, codes of practice, site layou
Development of MAAP5.0.3 Spent Fuel Pool Model for Severe Accident Analysis
Energy Technology Data Exchange (ETDEWEB)
Seo, Mi Ro [KHNP-CRI, Daejeon (Korea, Republic of)
After the Fukushima accident, the severe accident phenomena in the Spent Fuel Pool (SFP) have been the great issues in the nuclear industry. Generally, during full power operation status, the decay heat of the spent fuel in the SFP is not high enough to cause the severe accident that is the say, the melting of fuel and fuel rack. In addition to this, the SFP of the PWR is not isolated within the containment like the SFP of the old BWR plant, there are so many possible measures to prevent and mitigate severe accidents in the SFP. On the other hand, in the low power shutdown status (fuel refueling), all the core is transferred into the SFP during the refueling period. At this period, if some accidents happen such as the loss of SFP cooling and the failure of SFP integrity then the accidents may be developed into severe accident because the decay heat is high enough. So, the analysis of severe accidents in the SFP during low power shutdown state is greatly affected to the establishment of the major strategies in the severe accident management guideline (SAMG). However, the status of the domestic technical background for those analyses is very weak. it is known that the decay heat of the spent fuel in the SFP is not high enough to cause the severe accident qualitatively. However, there are some possibilities that can cause the severe accidents in the SFP if the loss of SFP cooling and integrity happens simultaneously. The severe accident phenomena in SFP themselves are not much different from those in the containment. However, since the structure of SFP cannot be isolated during the accidents like the containment, the consequence can be extremely significant. So, in terms of the establishment of the severe accident management strategy, it is necessary that the quantitative analysis for the severe accident progression in the SFP should be performed. In this study, the general behavior which can be appeared during the severe accidents in the SFP was analyzed using the
Independent accident investigation: a modern safety tool
International Nuclear Information System (INIS)
Historically, safety has been subjected to a fragmented approach. In the past, every department has had its own responsibility towards safety, focusing either on working conditions, internal safety, external safety, rescue and emergency, public order or security. They each issued policy documents, which in their time were leading statements for elaboration and regulation. They also addressed safety issues with tools of various nature, often specifically developed within their domain. Due to a series of major accidents and disasters, the focus of attention is shifting from complying with quantitative risk standards towards intervention in primary operational processes, coping with systemic deficiencies and a more integrated assessment of safety in its societal context. In The Netherlands recognition of the importance of independent investigations has led to an expansion of this philosophy from the transport sector to other sectors. The philosophy now covers transport, industry, defense, natural disaster, environment and health and other major occurrences such as explosions, fires, and collapse of buildings or structures. In 2003 a multi-sector covering law will establish an independent safety board in The Netherlands. At a European level, mandatory investigation agencies are recognized as indispensable safety instruments for aviation, railways and the maritime sector, for which EU Directives are in place or being progressed [Transport accident and incident investigation in the European Union, European Transport Safety Council, ISBN 90-76024-10-3, Brussel, 2001]. Due to a series of major events, attention has been drawn to the consequences of disasters, highlighting the involvement of rescue and emergency services. They also have become subjected to investigative efforts, which in return, puts demands on investigation methodology. This paper comments on an evolutionary development in safety thinking and of safety boards, highlighting some consequences for strategic
Catastrophe model of the accident process, safety climate, and anxiety.
Guastello, Stephen J; Lynn, Mark
This study aimed (a) to address the evidence for situational specificity in the connection between safety climate to occupational accidents, (b) to resolve similar issues between anxiety and accidents, (c) to expand and develop the concept of safety climate to include a wider range of organizational constructs, (d) to assess a cusp catastrophe model for occupational accidents where safety climate and anxiety are treated as bifurcation variables, and environ-mental hazards are asymmetry variables. Bifurcation, or trigger variables can have a positive or negative effect on outcomes, depending on the levels of asymmetry, or background variables. The participants were 1262 production employees of two steel manufacturing facilities who completed a survey that measured safety management, anxiety, subjective danger, dysregulation, stressors and hazards. Nonlinear regression analyses showed, for this industry, that the accident process was explained by a cusp catastrophe model in which safety management and anxiety were bifurcation variables, and hazards, age and experience were asymmetry variables. The accuracy of the cusp model (R2 = .72) exceeded that of the next best log-linear model (R2 = .08) composed from the same survey variables. The results are thought to generalize to any industry where serious injuries could occur, although situationally specific effects should be anticipated as well.
Consequences and countermeasures in a nuclear power accident: Chernobyl experience.
Kirichenko, Vladimir A; Kirichenko, Alexander V; Werts, Day E
Despite the tragic accidents in Fukushima and Chernobyl, the nuclear power industry will continue to contribute to the production of electric energy worldwide until there are efficient and sustainable alternative sources of energy. The Chernobyl nuclear accident, which occurred 26 years ago in the former Soviet Union, released an immense amount of radioactivity over vast territories of Belarus, Ukraine, and the Russian Federation, extending into northern Europe, and became the most severe accident in the history of the nuclear industry. This disaster was a result of numerous factors including inadequate nuclear power plant design, human errors, and violation of safety measures. The lessons learned from nuclear accidents will continue to strengthen the safety design of new reactor installations, but with more than 400 active nuclear power stations worldwide and 104 reactors in the Unites States, it is essential to reassess fundamental issues related to the Chernobyl experience as it continues to evolve. This article summarizes early and late events of the incident, the impact on thyroid health, and attempts to reduce agricultural radioactive contamination.
Influências das condições e organização do trabalho de uma indústria de transformação de cana-de-açúcar na ocorrência de acidentes de trabalho Influences of working conditions and organization in a sugar cane transformation industry in the event of accidents at work
Directory of Open Access Journals (Sweden)
Cassiano Ricardo Rumin
Full Text Available Este estudo discute a relação entre as condições e a organização do trabalho como elementos que contribuem para a ocorrência de acidentes do trabalho. Os dados foram coletados em uma indústria produtora de açúcar, álcool e derivados, situada no Estado de São Paulo. Para a coleta dos dados utilizamos a observação direta do trabalho e realizamos entrevistas semidirigidas individuais como 22 trabalhadores do setor de produção de açúcar. A produção de açúcar foi indicada pela Equipe de Segurança e Higiene no Trabalho como o setor em que havia a maior ocorrência de acidentes. Por destacar o papel que a relação homem-trabalho desempenha na saúde física e psíquica dos trabalhadores, utilizamos a Psicodinâmica do Trabalho (Dejours, 1994 como referencial teórico para a análise dos dados obtidos nas entrevistas. A análise das entrevistas envolveu três aspectos: condições e organização do trabalho e insatisfação. Os resultados revelaram que o ambiente estudado apresenta fatores físicos, químicos e biológicos desfavoráveis à saúde dos trabalhadores. Quanto à organização do trabalho, os dados revelaram que a divisão do trabalho bem como o conteúdo das tarefas determinavam sobrecarga aos trabalhadores. O relato sobre a insatisfação envolveu: ausência de perspectiva para progressão profissional, falta de treinamento técnico, dificuldade em manejar equipamentos e inadequação dos equipamentos de proteção. Destaca-se também no discurso dos trabalhadores a ineficiência das ações organizacionais para a eliminação ou a neutralização dos riscos de acidentes do trabalho e a predominância da teoria do "Ato inseguro" na apuração da causalidade dos acidentes do trabalho.The present study is about the relationship between the work conditions and organization as elements that contribute to work accidents. The data were collected in a sugar cane industry that produces sugar, alcohol and other derivates
Radiological emergencies in industry (causes and consequences). Address at the second national course of Radiation Safety in Industry. Jun 5-7 2000 Guatemala
International Nuclear Information System (INIS)
The address discusses the following issues: review of accidents in industrial radiography, human factors, technical failures, factors that decrease risk, personnel training, design of equipment and recommendations
Emergency drinking water treatment during source water pollution accidents in China: origin analysis, framework and technologies.
Zhang, Xiao-Jian; Chen, Chao; Lin, Peng-Fei; Hou, Ai-Xin; Niu, Zhang-Bin; Wang, Jun
China has suffered frequent source water contamination accidents in the past decade, which has resulted in severe consequences to the water supply of millions of residents. The origins of typical cases of contamination are discussed in this paper as well as the emergency response to these accidents. In general, excessive pursuit of rapid industrialization and the unreasonable location of factories are responsible for the increasing frequency of accidental pollution events. Moreover, insufficient attention to environmental protection and rudimentary emergency response capability has exacerbated the consequences of such accidents. These environmental accidents triggered or accelerated the promulgation of stricter environmental protection policy and the shift from economic development mode to a more sustainable direction, which should be regarded as the turning point of environmental protection in China. To guarantee water security, China is trying to establish a rapid and effective emergency response framework, build up the capability of early accident detection, and develop efficient technologies to remove contaminants from water. PMID:21133359
A New Cultivation-Evolution Technology of Accident Immune Function for a Petrochemical Enterprise
Institute of Scientific and Technical Information of China (English)
Yang Zhenhong; Zhang Xuhua; Wang Xiangyao; Wang Zhihu; Liu Yan; Zhang Xuan
For the purpose of developing an immune function on production accidents in a petrochemical enterprise, a new cultivation-evolution approach of preventive mechanism is suggested by analyzing various factors relating to immune deficiency syndrome and by referring to immunity genetic algorithm and relevant concepts applied in medicine science. Accident-immunity system for highly hazardous petrochemical enterprise, which is made up of its productive system's Safety Organ and Safety Organization, is typically an evolution-cultivation progress for immune function, The new B immune cell is generated after several layers' screening, clone expanding, receptor editing, organizing in immune system of work accident in petrochemical enterprise. There is a B immune cell with high appetency and a manipulative function chain for accident-immunity. Taking the antigen of accidents in industry as the target function and the immune antibody as the solution, the authors carried out a computation diagram for prediction of appetency between the antigen and antibody.
Fuel safety analysis following feeder break accident for refurbished Wolsong 1
International Nuclear Information System (INIS)
The objective of the fuel analysis for the postulated accident was to estimate the quantity and timing of a fission product release from fuels when a postulated single channel accident occurs in CANDU 6 reactors. In this study, a fuel safety analysis for the refurbished Wolsong 1 was carried out by using the latest IST (Industrial Standard Toolset) fuel code. The relevant accident scenario focused in this study was a feeder stagnation break accident. The amount of fission product inventory and its distribution during the normal operating conditions were calculated by using the latest ELESTRES-IST code. For a calculation of transient fission product release following the feeder stagnation break, it was assumed that all fuel sheaths in the channel were failed and the entire gap inventory was released instantaneously at the beginning of the accident. The additional releases from the grain boundary and in-grain bound inventories were estimated by applying the Gehl's release model. (author)
Accident knowledge and emergency management
Energy Technology Data Exchange (ETDEWEB)
Rasmussen, B.; Groenberg, C.D.
The report contains an overall frame for transformation of knowledge and experience from risk analysis to emergency education. An accident model has been developed to describe the emergency situation. A key concept of this model is uncontrolled flow of energy (UFOE), essential elements are the state, location and movement of the energy (and mass). A UFOE can be considered as the driving force of an accident, e.g., an explosion, a fire, a release of heavy gases. As long as the energy is confined, i.e. the location and movement of the energy are under control, the situation is safe, but loss of confinement will create a hazardous situation that may develop into an accident. A domain model has been developed for representing accident and emergency scenarios occurring in society. The domain model uses three main categories: status, context and objectives. A domain is a group of activities with allied goals and elements and ten specific domains have been investigated: process plant, storage, nuclear power plant, energy distribution, marine transport of goods, marine transport of people, aviation, transport by road, transport by rail and natural disasters. Totally 25 accident cases were consulted and information was extracted for filling into the schematic representations with two to four cases pr. specific domain. (au) 41 tabs., 8 ills.; 79 refs.
Nuclear accident dosimetry intercomparison studies.
Sims, C S
Twenty-two nuclear accident dosimetry intercomparison studies utilizing the fast-pulse Health Physics Research Reactor at the Oak Ridge National Laboratory have been conducted since 1965. These studies have provided a total of 62 different organizations a forum for discussion of criticality accident dosimetry, an opportunity to test their neutron and gamma-ray dosimetry systems under a variety of simulated criticality accident conditions, and the experience of comparing results with reference dose values as well as with the measured results obtained by others making measurements under identical conditions. Sixty-nine nuclear accidents (27 with unmoderated neutron energy spectra and 42 with eight different shielded spectra) have been simulated in the studies. Neutron doses were in the 0.2-8.5 Gy range and gamma doses in the 0.1-2.0 Gy range. A total of 2,289 dose measurements (1,311 neutron, 978 gamma) were made during the intercomparisons. The primary methods of neutron dosimetry were activation foils, thermoluminescent dosimeters, and blood sodium activation. The main methods of gamma dose measurement were thermoluminescent dosimeters, radiophotoluminescent glass, and film. About 68% of the neutron measurements met the accuracy guidelines (+/- 25%) and about 52% of the gamma measurements met the accuracy criterion (+/- 20%) for accident dosimetry. PMID:2777549
Radioactive materials transport accident analysis
Energy Technology Data Exchange (ETDEWEB)
McSweeney, T.I.; Maheras, S.J.; Ross, S.B. [Battelle Memorial Inst. (United States)
Over the last 25 years, one of the major issues raised regarding radioactive material transportation has been the risk of severe accidents. While numerous studies have shown that traffic fatalities dominate the risk, modeling the risk of severe accidents has remained one of the most difficult analysis problems. This paper will show how models that were developed for nuclear spent fuel transport accident analysis can be adopted to obtain estimates of release fractions for other types of radioactive material such as vitrified highlevel radioactive waste. The paper will also show how some experimental results from fire experiments involving low level waste packaging can be used in modeling transport accident analysis with this waste form. The results of the analysis enable an analyst to clearly show the differences in the release fractions as a function of accident severity. The paper will also show that by placing the data in a database such as ACCESS trademark, it is possible to obtain risk measures for transporting the waste forms along proposed routes from the generator site to potential final disposal sites.
Accident knowledge and emergency management
International Nuclear Information System (INIS)
The report contains an overall frame for transformation of knowledge and experience from risk analysis to emergency education. An accident model has been developed to describe the emergency situation. A key concept of this model is uncontrolled flow of energy (UFOE), essential elements are the state, location and movement of the energy (and mass). A UFOE can be considered as the driving force of an accident, e.g., an explosion, a fire, a release of heavy gases. As long as the energy is confined, i.e. the location and movement of the energy are under control, the situation is safe, but loss of confinement will create a hazardous situation that may develop into an accident. A domain model has been developed for representing accident and emergency scenarios occurring in society. The domain model uses three main categories: status, context and objectives. A domain is a group of activities with allied goals and elements and ten specific domains have been investigated: process plant, storage, nuclear power plant, energy distribution, marine transport of goods, marine transport of people, aviation, transport by road, transport by rail and natural disasters. Totally 25 accident cases were consulted and information was extracted for filling into the schematic representations with two to four cases pr. specific domain. (au) 41 tabs., 8 ills.; 79 refs
Modeling injury rates as a function of industrialized versus on-site construction techniques.
Rubio-Romero, J C; Suárez-Cebador, M; Abad, Jesús
It is often predicted that the industrialization of building activities will lead to a reduction of accident rates in the construction sector, particularly as a result of switching activities from building sites to factories. However, to date no scientific research has provided objective quantitative results to back up this claim. The aim of this paper is to evaluate how industrialization affects the accident rate in different industrialized building systems in Spain. Our results revealed that the industrialized steel modular system presents the lowest accident rate, while the highest accident rate was recorded in the construction method with cast-in-place concrete. The lightweight construction system also presents a high accident rate. Accordingly, industrialized building systems cannot claim to be safer than traditional ones. The different types of "on-site work" seem to be the main variable which would explain the accident rates recorded in industrialized construction systems.
Nuclear law and radiological accidents
International Nuclear Information System (INIS)
Nuclear activities in Brazil, and particularly the radiological accident of Goiania, are examined in the light of the environmental and nuclear laws of Brazil and the issue of responsibility. The absence of legislation covering radioactive wastes as well as the restrictions on Brazilian States to issue regulations covering nuclear activities are reviewed. The radiological accident and its consequences, including the protection and compensation of the victims, the responsibility of the shareholders of the Instituto Goiano de Radioterapia, operator of the radioactive source, the provisional storage and the final disposal at Abadia de Goias of the radioactive waste generated by the accident are reviewed. Finally, nuclear responsibility, the inapplicability of the Law 6453/77 which deals with nuclear damages, and the state liability regime are analysed in accordance with the principles of the Brazilian Federal Constitution. (author)
Severe accident management guidelines tool
International Nuclear Information System (INIS)
Severe Accident is addressed by means of a great number of documents such as guidelines, calculation aids and diagnostic trees. The response methodology often requires the use of several documents at the same time while Technical Support Centre members need to assess the appropriate set of equipment within the adequate mitigation strategies. In order to facilitate the response, TECNATOM has developed SAMG TOOL, initially named GGAS TOOL, which is an easy to use computer program that clearly improves and accelerates the severe accident management. The software is designed with powerful features that allow the users to focus on the decision-making process. Consequently, SAMG TOOL significantly improves the severe accident training, ensuring a better response under a real situation. The software is already installed in several Spanish Nuclear Power Plants and trainees claim that the methodology can be followed easier with it, especially because guidelines, calculation aids, equipment information and strategies availability can be accessed immediately (authors)
Severe accident simulation at Olkiuoto
Energy Technology Data Exchange (ETDEWEB)
Tirkkonen, H.; Saarenpaeae, T. [Teollisuuden Voima Oy (TVO), Olkiluoto (Finland); Cliff Po, L.C. [Micro-Simulation Technology, Montville, NJ (United States)
A personal computer-based simulator was developed for the Olkiluoto nuclear plant in Finland for training in severe accident management. The generic software PCTRAN was expanded to model the plant-specific features of the ABB Atom designed BWR including its containment over-pressure protection and filtered vent systems. Scenarios including core heat-up, hydrogen generation, core melt and vessel penetration were developed in this work. Radiation leakage paths and dose rate distribution are presented graphically for operator use in diagnosis and mitigation of accidents. Operating on an graphically for operator use in diagnosis and mitigation of accidents. Operating on an 486 DX2-66, PCTRAN-TVO achieves a speed about 15 times faster than real-time. A convenient and user-friendly graphic interface allows full interactive control. In this paper a review of the component models and verification runs are presented.
Internal Accident Report on EDH
SC Department
The A2 Safety Code requires that, the Internal Accident Report form must be filled in by the person concerned or any witness to ensure that all the relevant services are informed. Please note that an electronic version of this form has been elaborated in collaboration with SC-IE, HR-OPS-OP and IT-AIS. Whenever possible, the electronic form shall be used. The relative icon is available on the EDH Desktop, Other tasks page, under the Safety heading, or directly here: https://edh.cern.ch/Document/Accident/. If you have any questions, please contact the SC Secretariat, tel. 75097 Please notice that the Internal Accident Report is an integral part of the Safety Code A2 and does not replace the HS50.
Fukushima accident study using MELCOR
Institute of Scientific and Technical Information of China (English)
Randall O Gauntt
The accidents at the Fukushima Daiichi nuclear power station stunned the world as the sequences played out over severals days and videos of hydrogen explosions were televised as they took place.The accidents all resulted in severe damage to the reactor cores and releases of radioactivity to the environment despite heroic measures had taken by the operating personnel.The following paper provides some background into the development of these accidents and their root causes,chief among them,the prolonged station blackout conditions that isolated the reactors from their ultimate heat sink — the ocean.The interpretations given in this paper are summarized from a recently completed report funded by the United States Department of Energy (USDOE).
Road characteristics and bicycle accidents.
Nyberg, P; Björnstig, U; Bygren, L O
In Umeå, Sweden, defects in the physical road surface contributed to nearly half of the single bicycle accidents. The total social cost of these injuries to people amount to at least SEK 20 million (SEK 60,000 or about USD 8,500 per accident), which corresponds to the estimated loss of "eight life equivalents a year". Improved winter maintenance seems to have the greatest injury prevention potential and would probably reduce the number of injuries considerably, whereas improved road quality and modification of kerbs would reduce the most severe injuries. A local traffic safety program should try to prevent road accidents instead of handling the consequences of them. In accordance with Parliament decisions on traffic we would like to see increased investment in measures favoring bicycle traffic, where cycling is seen as a solution, not as a problem.
Advocating System Safety Concept in Preventing Airline Accidents
Lu, Chien-tsung; Wetmore, Michael; Smith, John
System safety was conceptualized by the aerospace industry in the late 1940s in the United States (U.S.). Traditionally, users of system safety applied analysis to identify operational hazards and subsequently provide countermeasures before or after an accident. Unfortunately, very few aviation safety researches from the airlines had utilized it to promote aviation safety. To enrich this knowledge and contribute interest from academia, this paper adopted the inductive techniques of system saf...
Hindsight Bias in Cause Analysis of Accident
Institute of Scientific and Technical Information of China (English)
Atsuo Murata; Yasunari Matsushita
It is suggested that hindsight becomes an obstacle to the objective investigation of an accident, and that the proper countermeasures for the prevention of such an accident is impossible if we view the accident with hindsight. Therefore, it is important for organizational managers to prevent hindsight from occurring so that hindsight does not hinder objective and proper measures to be taken and this does not lead to a serious accident. In this study, a basic phenomenon potentially related to accidents, that is, hindsight was taken up, and an attempt was made to explore the phenomenon in order to get basically insights into the prevention of accidents caused by such a cognitive bias.
The child accident repeater: a review.
Jones, J G
The child accident repeater is defined as one who has at least three accidents that come to medical attention within a year. The accident situation has features in common with those of the child who has a single accident through simple "bad luck", but other factors predispose him to repeated injury. In the child who has a susceptible personality, a tendency for accident repetition may be due to a breakdown in adjustment to a stressful environment. Prevention of repeat accidents should involve the usual measures considered appropriate for all children as well as an attempt to provide treatment of significant maladjustment and modification of a stressful environment.
Fukushima nuclear power plant accident was preventable
Kanoglu, Utku; Synolakis, Costas
On 11 March 2011, the fourth largest earthquake in recorded history triggered a large tsunami, which will probably be remembered from the dramatic live pictures in a country, which is possibly the most tsunami-prepared in the world. The earthquake and tsunami caused a major nuclear power plant (NPP) accident at the Fukushima Dai-ichi, owned by Tokyo Electric Power Company (TEPCO). The accident was likely more severe than the 1979 Three Mile Island and less severe than the Chernobyl 1986 accidents. Yet, after the 26 December 2004 Indian Ocean tsunami had hit the Madras Atomic Power Station there had been renewed interest in the resilience of NPPs to tsunamis. The 11 March 2011 tsunami hit the Onagawa, Fukushima Dai-ichi, Fukushima Dai-ni, and Tokai Dai-ni NPPs, all located approximately in a 230km stretch along the east coast of Honshu. The Onagawa NPP was the closest to the source and was hit by an approximately height of 13m tsunami, of the same height as the one that hit the Fukushima Dai-ichi. Even though the Onagawa site also subsided by 1m, the tsunami did not reach to the main critical facilities. As the International Atomic Energy Agency put it, the Onagawa NPP survived the event "remarkably undamaged." At Fukushima Dai-ichi, the three reactors in operation were shut down due to strong ground shaking. The earthquake damaged all offsite electric transmission facilities. Emergency diesel generators (EDGs) provided back up power and started cooling down the reactors. However, the tsunami flooded the facilities damaging 12 of its 13 EDGs and caused a blackout. Among the consequences were hydrogen explosions that released radioactive material in the environment. It is unfortunately clear that TEPCO and Japan's principal regulator Nuclear and Industrial Safety Agency (NISA) had failed in providing a professional hazard analysis for the plant, even though their last assessment had taken place only months before the accident. The main reasons are the following. One
From Aberfan to the "Canvey Factor": Schools, Children and Industrial Disasters
Preston, John
Children, and schools, are potent symbols of victimhood in industrial disasters. In the case of historical industrial disasters such as Aberfan and Flixborough, and in terms of preparation for future industrial disasters under Control of Major Accident Hazard regulations, communities are seen as passive responders to accidents. Moreover, following…
JCO criticality accident termination operation
International Nuclear Information System (INIS)
In 2001, we summarized the circumstances surrounding termination of the JCO criticality accident based on testimony in the Mito District Court on December 17, 2001. JCO was the company for uranium fuels production in Japan. That document was assembled based on actual testimony in the belief that a description of the work involved in termination of the accident would be useful in some way for preventing nuclear disasters in the future. The description focuses on the witness' own behavior, and what he saw and heard, and thus is written from the perspective of action by one individual. This was done simply because it was easier for the witness to write down his memories as he remembers them. Description of the activities of other organizations and people is provided only as necessary, to ensure that consistency in the descriptive approach is not lost. The essentials of this report were rewritten as a third-person objective description in the summary of the report by the Atomic Energy Society of Japan (AESJ). Since then, comments have been received from sources such as former members of the Nuclear Safety Commission (Dr. Kenji Sumita and Dr. Akira Kanagawa), concerned parties from the former Science and Technology Agency, and reports from the JCO Criticality Accident Investigation Committee of the AESJ, and thus this report was rewritten to correct incorrect information, and add material where that was felt to be necessary. This year is the tenth year of the JCO criticality accident. To mark this occasion we have decided to translate the record of what occurred at the accident site into English so that more people can draw lessons from this accident. This report is an English version of JAEA-Technology 2009-073. (author)
Road Traffic Accidents in Kazakhstan
Directory of Open Access Journals (Sweden)
Alma Aubakirova
Full Text Available Background: The article provides the analysis of death rates in road traffic accidents in Kazakhstan from 2004 to 2010 and explores the use of sanitary aviation.Methods: Data of fatalities caused by road traffic accidents were collected and analysed. Descriptive and analytical methods of epidemiology and biomedical statistics were applied.Results: Totaly 27,003 people died as a result of road traffic accidents in this period. The death rate for the total population due to road traffic accidents was 25.0±2.10/0000. The death rate for men was (38.3±3.20/0000, which was higher (P<0.05 than that for women (12.6±1.10/0000. High death rates in the entire male population were identified among men of 30-39 years old, whereas the highest rates for women were attributed to the groups of 50-59 years old and 70-79 years old. In time dynamics, death rates tended to decrease: the total population (Тdec=−2.4%, men (Тdec=−2.3% and women (Тdec=−1.4%. When researching territorial relevance, the rates were established as low (to 18.30/0000, average (between18.3 and24.00/0000 and high (from 24.00/0000 and above. Thus, the regions with high rates included Akmola region (24.30/0000, Mangistau region (25.90/0000, Zhambyl region (27.30/0000, Almaty region (29.30/0000 and South Kazakhstan region (32.40/0000.Conclusion: The identified epidemiological characteristics of the population deaths rates from road traffic accidents should be used in integrated and targeted interventions to enhance prevention of injuries in accidents.
Fatal motorcycle accidents and alcohol
DEFF Research Database (Denmark)
Larsen, C F; Hardt-Madsen, M
A series of fatal motorcycle accidents from a 7-year period (1977-1983) has been analyzed. Of the fatalities 30 were operators of the motorcycle, 11 pillion passengers and 8 counterparts. Of 41 operators 37% were sober at the time of accident, 66% had measurable blood alcohol concentration (BAC......); 59% above 0.08%. In all cases where a pillion passenger was killed, the operator of the motorcycle had a BAC greater than 0.08%. Of the killed counterparts 2 were non-intoxicated, 2 had a BAC greater than 0.08%, and 4 were not tested. The results advocate that the law should restrict alcohol...
Study on accident response robot for nuclear power plant and analysis of key technologies
International Nuclear Information System (INIS)
With the rapid development of nuclear power industry and improving demand for nuclear safety, the demand for developing accident response robot in nuclear power plant is increasingly urgent. Firstly, design analysis for accident response robot is taken with environmental conditions in nuclear power plant. Secondly, development for response robots after Chernobyl, JCO and Fukushima accidents are reviewed, and improvements for commercial mobile robot for use in radioactive environments are summarized. Finally, some key technologies including radiation-tolerance and system reliability are analyzed in details. (authors)
Analysis and Simulation of Severe Accidents in a Steam Methane Reforming Plant
MohammadJavad Jafari; Iraj Mohammadfam; Esmaeil Zarei
Severe accidents of process industries in Iran have increased significantly in recent decade. This study quantitatively analyzes the hazards of severe accidents imposed on people, equipment and building by a hydrogen production facility. A hazard identification method was applied. Then a consequence simulation was carried out using PHAST 6.54 software package and at the end, consequence evaluation was carried out based on the best-known and different criteria. Most hazardous jet fire and flas...
Execution of the Occupational Safety and Health Act (1994) in the Construction Industry from Contractors' Point of View
Awang H.; Kamil I.M.
Construction is one of the highest contributing industries to occupational accidents by sector in Malaysia. Statistics have been drawn from year to year that show an increasing number of cases of accidents by industry sector. While it is impossible to completely eliminate all accidents, with a proper and effective safety and health policy or rules set by top management, especially contractors, the rate of accidents on construction sites can be reduced. The main objective of this study is to a...
Road Accident Trends in Africa and Europe
DEFF Research Database (Denmark)
Jørgensen, N O
The paper decribes trends and suggests prediction models for accident risks in African and European countries......The paper decribes trends and suggests prediction models for accident risks in African and European countries...
49 CFR 229.17 - Accident reports.
... CFR part 225. ... 49 Transportation 4 2010-10-01 2010-10-01 false Accident reports. 229.17 Section 229.17..., DEPARTMENT OF TRANSPORTATION RAILROAD LOCOMOTIVE SAFETY STANDARDS General § 229.17 Accident reports. (a)...
How to reduce the number of accidents
Among the safety objectives that the Director-General has established for CERN in 2012 is a reduction in the number of workplace accidents. The best way to prevent workplace accidents is to learn from experience. This is why any accident, fire, instance of pollution, or even a near-miss, should be reported using the EDH form that can be found here. All accident reports are followed up. The departments investigate all accidents that result in sick leave, as well as all the more common categories of accidents at CERN, essentially falls (slipping, falling on stairs, etc.), regardless of whether or not they lead to sick leave. By studying the accident causes that come to light in this way, it is possible to take preventive action to avoid such accidents in the future. If you have any questions, the HSE Unit will be happy to answer them. Contact us at firstname.lastname@example.com. HSE Unit
Accident consequence assessment code development
International Nuclear Information System (INIS)
This paper describes the new computer code system, OSCAAR developed for off-site consequence assessment of a potential nuclear accident. OSCAAR consists of several modules which have modeling capabilities in atmospheric transport, foodchain transport, dosimetry, emergency response and radiological health effects. The major modules of the consequence assessment code are described, highlighting the validation and verification of the models. (author)
New technology for accident prevention
Energy Technology Data Exchange (ETDEWEB)
Byne, P. [Shiftwork Solutions, Vancouver, BC (Canada)
This power point presentation examined the effects of fatigue in the workplace and presented 3 technologies designed to prevent or monitor fatigue. The relationship between mental fatigue, circadian rhythms and cognitive performance was explored. Details of vigilance related degradations in the workplace were presented, as well as data on fatigue-related accidents and a time-line of meter-reading errors. It was noted that the direct cause of the Exxon Valdez disaster was sleep deprivation. Fatigue related accidents during the Gulf War were reviewed. The effects of fatigue on workplace performance include impaired logical reasoning and decision-making; impaired vigilance and attention; slowed mental operations; loss of situational awareness; slowed reaction time; and short cuts and lapses in optional or self-paced behaviours. New technologies to prevent fatigue-related accidents include (1) the driver fatigue monitor, an infra-red camera and computer that tracks a driver's slow eye-lid closures to prevent fatigue related accidents; (2) a fatigue avoidance scheduling tool (FAST) which collects actigraphs of sleep activity; and (3) SAFTE, a sleep, activity, fatigue and effectiveness model. refs., tabs., figs.
Consequences of the Chernobyl accident
International Nuclear Information System (INIS)
A collection of three papers about the fallout in Austria from the 1986 Chernobyl reactor accident is given: 1. An overview of the research projects in Austria; 2. On the transfer into and uptake by crops and animal fodder; 3. On the reduction of cesium concentration in food. 18 tabs., 21 figs., 69 refs
Trismus: An unusual presentation following road accident
Directory of Open Access Journals (Sweden)
Thakur Jagdeep
Full Text Available Trismus due to trauma usually follows road accidents leading to massive faciomaxillary injury. In the literature there is no report of a foreign body causing trismus following a road accident, this rare case is an exception. We present a case of isolated presentation of trismus following a road accident. This case report stresses on the thorough evaluation of patients presenting with trismus following a road accident.
Calculating nuclear accident probabilities from empirical frequencies
Ha-Duong, Minh; Journé, V.
International audience Since there is no authoritative, comprehensive and public historical record of nuclear power plant accidents, we reconstructed a nuclear accident data set from peer-reviewed and other literature. We found that, in a sample of five random years, the worldwide historical frequency of a nuclear major accident, defined as an INES level 7 event, is 14 %. The probability of at least one nuclear accident rated at level ≥4 on the INES scale is 67 %. These numbers are subject...
Accident management advisor system (AMAS): A Decision Aid for Interpreting Instrument Information and Managing Accident Conditions in Nuclear Power Plants
International Nuclear Information System (INIS)
for the development of models specifically tailored to real-time accident management. While it is almost impossible to develop and utilize exact models of the evolution of all possible accident sequences for each given type of nuclear power plant and containment design (e.g., PWR and BWR designs at various power ratings, large dry containment or ice condenser types, etc.), it appears possible to develop a sound approach to monitor the progression of an accident with respect to the integrity and effectiveness of a set of principal safety functions. The key to doing this is the development of a knowledge base 'housing structure', where uncertain knowledge regarding the predicted plant behavior and real-time, but also uncertain, information compiled from plant instrumentation readings can be compared and matched to produce the best possible identification of plant states and possible accident control actions. In summary: This paper illustrates the concept and the architecture of the Accident Management Advisor System, a decision aid which enables the use of combined instrument information to reduce uncertainty in decision making associated with nuclear plant accident conditions. The principal benefits offered by this concept are the definition of an approach to utilize instrument information under uncertain accident conditions in such a way as to allow the best possible assessment of plant status and the implementation of a formalized accident management decision-making strategy by means of a computer-based operator assistance tool. When fully developed, we expect AMAS to find application in both the commercial and government sections of the U.S. nuclear industry. We currently plan to have a working prototype of the system, ready to demonstrate its functionality for a representative commercial PWR plant, by the end of the next phase of our research, in which both model development and software development activities will have to be carried out. Finally, the AMAS
Detection and analysis of accident black spots with even small accident figures.
Oppe, S.
Accident black spots are usually defined as road locations with high accident potentials. In order to detect such hazardous locations we have to know the probability of an accident for a traffic situation of some kind, or the mean number of accidents for some unit of time. In almost all procedures
48 CFR 836.513 - Accident prevention.
... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Accident prevention. 836... prevention. The contracting officer must insert the clause at 852.236-87, Accident Prevention, in solicitations and contracts for construction that contain the clause at FAR 52.236-13, Accident Prevention....
48 CFR 1836.513 - Accident prevention.
... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Accident prevention. 1836... 1836.513 Accident prevention. The contracting officer must insert the clause at 1852.223-70, Safety and Health, in lieu of FAR clause 52.236-13, Accident Prevention, and its Alternate I....
48 CFR 636.513 - Accident prevention.
... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Accident prevention. 636... CONTRACTING CONSTRUCTION AND ARCHITECT-ENGINEER CONTRACTS Contract Clauses 636.513 Accident prevention. (a) In... contracting activities shall insert DOSAR 652.236-70, Accident Prevention, in lieu of FAR clause...
Detection and analysis of accident black spots with even small accident figures.
Oppe, S.
Accident black spots are usually defined as road locations with high accident potentials. In order to detect such hazardous locations we have to know the probability of an accident for a traffic situation of some kind, or the mean number of accidents for some unit of time. In almost all procedures known to us, the various road locations are treated as isolated spots. With small accident figures it is difficult to detect such places in the known procedures. An alternative procedure starts from...
Deepwater Horizon Accident Investigation Report
Energy Technology Data Exchange (ETDEWEB)
On the evening of April 20, 2010, a well control event allowed hydrocarbons to escape from the Macondo well onto Transocean's Deepwater Horizon, resulting in explosions and fire on the rig. Eleven people lost their lives, and 17 others were injured. The fire, which was fed by hydrocarbons from the well, continued for 36 hours until the rig sank. Hydrocarbons continued to flow from the reservoir through the wellbore and the blowout preventer (BOP) for 87 days, causing a spill of national significance. BP Exploration and Production Inc. was the lease operator of Mississippi Canyon Block 252, which contains the Macondo well. BP formed an investigation team that was charged with gathering the facts surrounding the accident, analyzing available information to identify possible causes and making recommendations to enable prevention of similar accidents in the future. The BP investigation team began its work immediately in the aftermath of the accident, working independently from other BP spill response activities and organizations. The ability to gather information was limited by a scarcity of physical evidence and restricted access to potentially relevant witnesses. The team had access to partial real-time data from the rig, documents from various aspects of the Macondo well's development and construction, witness interviews and testimony from public hearings. The team used the information that was made available by other companies, including Transocean, Halliburton and Cameron. Over the course of the investigation, the team involved over 50 internal and external specialists from a variety of fields: safety, operations, subsea, drilling, well control, cementing, well flow dynamic modeling, BOP systems and process hazard analysis. This report presents an analysis of the events leading up to the accident, eight key findings related to the causal chain of events and recommendations to enable the prevention of a similar accident. The investigation team worked
Development of TRAIN for accident management
International Nuclear Information System (INIS)
Severe accident management can be defined as the use of existing and alternative resources, systems, and actions to prevent or mitigate a core-melt accident in nuclear power plants. TRAIN (Training pRogram for AMP In NPP), developed for training control room staff and the technical group, is introduced in this paper. The TRAIN composes of phenomenological knowledge base (KB), accident sequence KB and accident management procedures with AM strategy control diagrams and information needs. This TRAIN might contribute to training them by obtaining phenomenological knowledge of severe accidents, understanding plant vulnerabilities, and solving problems under high stress. (author)
Development of a prototype graphic simulation program for severe accident training
International Nuclear Information System (INIS)
This is a report of the development process and related technologies of severe accident graphic simulators, required in industrial severe accident management and training. Here, we say 'a severe accident graphic simulator' as a graphics add-in system to existing calculation codes, which can show the severe accident phenomena dynamically on computer screens and therefore which can supplement one of main defects of existing calculation codes. With graphic simulators it is fairly easy to see the total behavior of nuclear power plants, where it was very difficult to see only from partial variable numerical information. Moreover, the fast processing and control feature of a graphic simulator can give some opportunities of predicting the severe accident advancement among several possibilities, to one who is not an expert. Utilizing graphic simulators' we expect operators' and TSC members' physical phenomena understanding enhancement from the realistic dynamic behavior of plants. We also expect that severe accident training course can gain better training effects using graphic simulator's control functions and predicting capabilities, and therefore we expect that graphic simulators will be effective decision-aids tools both in sever accident training course and in real severe accident situations. With these in mind, we have developed a prototype graphic simulator having surveyed related technologies, and from this development experiences we have inspected the possibility to build a severe accident graphic simulator. The prototype graphic simulator is developed under IBM PC WinNT environments and is suited to Uljin 3and4 nuclear power plant. When supplied with adequate severe accident scenario as an input, the prototype can provide graphical simulations of plant safety systems' dynamic behaviors. The prototype is composed of several different modules, which are phenomena display module, MELCOR data interface module and graphic database interface module. Main functions of
Severe accident recriticality analyses (SARA)
DEFF Research Database (Denmark)
Frid, W.; Højerup, C.F.; Lindholm, I.;
Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated control rods, has been studied for a total loss of electric power accident scenario. In order to assess the impact of recriticality on reactor safety, including accident management strategies......, the following issues have been investigated in the SARA project: (1) the energy deposition in the fuel during super-prompt power burst; (2) the quasi steady-state reactor power following the initial power burst; and (3) containment response to elevated quasi steady-state reactor power. The approach was to use...... the regulatory limits for fuel failure, but close to or above recently observed thresholds for fragmentation and dispersion of high burn-up fuel. The highest calculated quasi steady-state power following initial power excursion was in most cases approximately 20% of the nominal reactor power, according...
Accident Simulation: Design and Results
Idasiak, Vincent; David, Pierre
International audience The French legislation regulates the functioning of factories that may be dangerous towards their environment. This legislation imposes the creation of an Internal Operation Plan (P.O.I.) on the plant managers. Those plans describe the proceedings that have to be implemented in case of an accident. Within a framework involving our laboratory and a gas company we have designed a software to create, maintain and execute P.O.I.s . In this paper, in addition to the softw...
Accident/Mishap Investigation System
Keller, Richard; Wolfe, Shawn; Gawdiak, Yuri; Carvalho, Robert; Panontin, Tina; Williams, James; Sturken, Ian
InvestigationOrganizer (IO) is a Web-based collaborative information system that integrates the generic functionality of a database, a document repository, a semantic hypermedia browser, and a rule-based inference system with specialized modeling and visualization functionality to support accident/mishap investigation teams. This accessible, online structure is designed to support investigators by allowing them to make explicit, shared, and meaningful links among evidence, causal models, findings, and recommendations.
Accident analysis and DOE criteria
International Nuclear Information System (INIS)
In analyzing the radiological consequences of major accidents at DOE facilities one finds that many facilities fall so far below the limits of DOE Order 6430 that compliance is easily demonstrated by simple analysis. For those cases where the amount of radioactive material and the dispersive energy available are enough for accident consequences to approach the limits, the models and assumptions used become critical. In some cases the models themselves are the difference between meeting the criteria or not meeting them. Further, in one case, we found that not only did the selection of models determine compliance but the selection of applicable criteria from different chapters of Order 6430 also made the difference. DOE has recognized the problem of different criteria in different chapters applying to one facility, and has proceeded to make changes for the sake of consistency. We have proposed to outline the specific steps needed in an accident analysis and suggest appropriate models, parameters, and assumptions. As a result we feed DOE siting and design criteria will be more fairly and consistently applied
Medical consequences of Chernobyl accident
Directory of Open Access Journals (Sweden)
Galstyan I.A.
Full Text Available Aim: to study the long-term effects of acute radiation syndrome (ARS, developed at the victims of the Chernobyl accident. Material and Methods. 237 people were exposed during the accident, 134 of them were diagnosed with ARS. Dynamic observation implies a thorough annual examination in a hospital. Results. In the first 1.5-2 years after the ARS mean group indices of peripheral blood have returned to normal. However, many patients had transient expressed moderate cytopenias. Granulocytopenia, thrombocytopenia, lymphopenia and erythropenia were the most frequently observed things during the first 5 years after the accident. After 5 years their occurences lowered. In 11 patients the radiation cataract was detected. A threshold dose for its development is a dose of 3.2 Gy Long-term effects of local radiation lesions (LRL range from mild skin figure smoothing to a distinct fibrous scarring, contractures, persistently recurrent late radiation ulcers. During all years of observation we found 8 solid tumors, including 2 thyroid cancers. 5 hematologic diseases were found. During 29 years 26 ARS survivors died of various causes. Conclusion. The health of ones with long-term ARS effects is determined by the evolution of the LRL effects on skin, radiation cataracts, hema-tological diseases and the accession of of various somatic diseases, not caused by radiation.
Reports of the Chernobyl accident consequences in Brazilian newspapers
International Nuclear Information System (INIS)
The public perception of the risks associated with nuclear power plants was profoundly influenced by the accidents at Three Mile Island and Chernobyl Power Plants which also served to exacerbate in the last decades the growing mistrust on the 'nuclear industry'. Part of the mistrust had its origin in the arrogance of nuclear spokesmen and in the secretiveness of nuclear programs. However, press agencies have an important role in shaping and upsizing the public awareness against nuclear energy. In this paper we present the results of a survey in reports of some Brazilian popular newspapers on Chernobyl consequences, as measured by the total death toll of the accident, to show the up and down dance of large numbers without any serious judgment. (author)
Directory of Open Access Journals (Sweden)
O. Gamankova
Full Text Available The paper deals with the peculiarities of formation of relationships in the reform of social security. Examines institutional support provided social insurance accidents with the latest trends reform of the sector. The study notes that the organization of social security is lost insurance principle, the general principles of the Social Insurance Institute, added other excess principles that form the basis for misappropriation of funds and various abuses. These problems are urgent and require research. The paper reviews the basic principles to achieve the optimal balance of economic and social needs of providing social protection of citizens of Ukraine. The results emphasize the need for heightened security procedures for consolidation of compulsory state social insurance against industrial accidents and the State Mandatory Social Insurance against disability.
Enhanced Accident Tolerant LWR Fuels National Metrics Workshop Report
Energy Technology Data Exchange (ETDEWEB)
Lori Braase
The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), in collaboration with the nuclear industry, has been conducting research and development (R&D) activities on advanced Light Water Reactor (LWR) fuels for the last few years. The emphasis for these activities was on improving the fuel performance in terms of increased burnup for waste minimization and increased power density for power upgrades, as well as collaborating with industry on fuel reliability. After the events at the Fukushima Nuclear Power Plant in Japan in March 2011, enhancing the accident tolerance of LWRs became a topic of serious discussion. In the Consolidated Appropriations Act, 2012, Conference Report 112-75, the U.S. Congress directed DOE-NE to: • Give "priority to developing enhanced fuels and cladding for light water reactors to improve safety in the event of accidents in the reactor or spent fuel pools." • Give "special technical emphasis and funding priority…to activities aimed at the development and near-term qualification of meltdown-resistant, accident-tolerant nuclear fuels that would enhance the safety of present and future generations of light water reactors." • Report "to the Committee, within 90 days of enactment of this act, on its plan for development of meltdown-resistant fuels leading to reactor testing and utilization by 2020." Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, and operational transients, as well as design-basis and beyond design-basis events. The overall draft strategy for development and demonstration is comprised of three phases: Feasibility Assessment and Down-selection; Development and Qualification; and
Hazard Identification, Risk Assessment and Risk Control (HIRARC Accidents at Power Plant
Directory of Open Access Journals (Sweden)
Ahmad Asmalia Che
Full Text Available Power plant had a reputation of being one of the most hazardous workplace environments. Workers in the power plant face many safety risks due to the nature of the job. Although power plants are safer nowadays since the industry has urged the employer to improve their employees' safety, the employees still stumble upon many hazards thus accidents at workplace. The aim of the present study is to investigate work related accidents at power plants based on HIRARC (Hazard Identification, Risk Assessment and Risk Control process. The data were collected at two coal-fired power plant located in Malaysia. The finding of the study identified hazards and assess risk relate to accidents occurred at the power plants. The finding of the study suggested the possible control measures and corrective actions to reduce or eliminate the risk that can be used by power plant in preventing accidents from occurred
Severe Accident Recriticality Analyses (SARA)
Energy Technology Data Exchange (ETDEWEB)
Frid, W. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Hoejerup, F. [Risoe National Lab. (Denmark); Lindholm, I.; Miettinen, J.; Puska, E.K. [VTT Energy, Helsinki (Finland); Nilsson, Lars [Studsvik Eco and Safety AB, Nykoeping (Sweden); Sjoevall, H. [Teoliisuuden Voima Oy (Finland)
Recriticality in a BWR has been studied for a total loss of electric power accident scenario. In a BWR, the B{sub 4}C control rods would melt and relocate from the core before the fuel during core uncovery and heat-up. If electric power returns during this time-window unborated water from ECCS systems will start to reflood the partly control rod free core. Recriticality might take place for which the only mitigating mechanisms are the Doppler effect and void formation. In order to assess the impact of recriticality on reactor safety, including accident management measures, the following issues have been investigated in the SARA project: 1. the energy deposition in the fuel during super-prompt power burst, 2. the quasi steady-state reactor power following the initial power burst and 3. containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core state initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality - both superprompt power bursts and quasi steady-state power generation - for the studied range of parameters, i. e. with core uncovery and heat-up to maximum core temperatures around 1800 K and water flow rates of 45 kg/s to 2000 kg/s injected into the downcomer. Since the recriticality takes place in a small fraction of the core the power densities are high which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal/g, was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding
Concentration fluctuations in gas releases by industrial accidents. Final report
Energy Technology Data Exchange (ETDEWEB)
Nielsen, M.; Chatwin, P.C.; Joergensen, H.E.; Mole, N.; Munro, R.J.; Ott, S.
The COFIN project studied existing remote-sensing Lidar data on concentration fluctuations in atmospheric dispersion from continuous sources at ground level. Fluctuations are described by stochastic models developed by a combination of statistical analyses and surface-layer scaling. The statistical moments and probability density distribution of the fluctuations are most accurately determined in a frame of reference following the instantaneous plume centreline. The spatial distribution of these moments is universal with a gaussian core and exponential tails. The instantaneous plume width is fluctuating with a log-normal distribution. The position of the instantaneous plume centre-line is modelled by a normal distribution and a Langevin equation, by which the meander effect on the time-averaged plume width is predicted. Fixed-frame statistics are modelled by convolution of moving-frame statistics and the probability distribution for the plume centreline. The distance-neighbour function generalized for higher-order statistics has a universal exponential shape. Simulation tools for concentration fluctuations have been developed for either multiple correlated time series or multi-dimensional fields. These tools are based on Karhunen-Loeve expansion and Fourier transformations using iterative or correlation-distortion techniques. The input to the simulation is the probability distribution of the individual processes, assumed stationary, and the cross-correlations of all signal combinations. The use in practical risk assessment is illustrated by implementation of a typical heavy-gas dispersion model, enhanced for prediction and simulation of concentration fluctuations. (au)
Concentration fluctuations in gas releases by industrial accidents
DEFF Research Database (Denmark)
Nielsen, M.; Chatwin, P.C.; Ejsing Jørgensen, Hans;
The COFIN project studied existing remote-sensing Lidar data on concentration fluctuations in atmospheric dispersion from continuous sources at ground level. Fluctuations are described by stochastic models developed by a combination of statisticalanalyses and surface-layer scaling. The statistica...
Risk and protection factors in fatal accidents.
Dupont, Emmanuelle; Martensen, Heike; Papadimitriou, Eleonora; Yannis, George
This paper aims at addressing the interest and appropriateness of performing accident severity analyses that are limited to fatal accident data. Two methodological issues are specifically discussed, namely the accident-size factors (the number of vehicles in the accident and their level of occupancy) and the comparability of the baseline risk. It is argued that - although these two issues are generally at play in accident severity analyses - their effects on, e.g., the estimation of survival probability, are exacerbated if the analysis is limited to fatal accident data. As a solution, it is recommended to control for these effects by (1) including accident-size indicators in the model, (2) focusing on different sub-groups of road-users while specifying the type of opponent in the model, so as to ensure that comparable baseline risks are worked with. These recommendations are applied in order to investigate risk and protection factors of car occupants involved in fatal accidents using data from a recently set up European Fatal Accident Investigation database (Reed and Morris, 2009). The results confirm that the estimated survival probability is affected by accident-size factors and by type of opponent. The car occupants' survival chances are negatively associated with their own age and that of their vehicle. The survival chances are also lower when seatbelt is not used. Front damage, as compared to other damaged car areas, appears to be associated with increased survival probability, but mostly in the case in which the accident opponent was another car. The interest of further investigating accident-size factors and opponent effects in fatal accidents is discussed. PMID:20159090
Public health response to the nuclear accident
International Nuclear Information System (INIS)
The Act on Special Measures Concerning Nuclear Emergency Preparedness was established in 2000 as a specific act within the broader Disaster Control Measures and Reactor Regulation Act which was written in response to the JCO Criticality Accident of 1999. However, this regulatory system did not address all aspects of the Fukushima Daiichi Nuclear Power Plant Accident. This was especially evident with public health issues. For example, radioactive screening, prophylactic use of potassium iodide, support for vulnerable people, and management of contaminated dead bodies were all requested immediately after the occurrence of the nuclear power plant accident but were not included in these regulatory acts. Recently, the regulatory system for nuclear accidents has been revised in response to this reactor accident. Herein we review the revised plan for nuclear reactor accidents in the context of public health. (author)
Accident scenario diagnostics with neural networks
International Nuclear Information System (INIS)
Nuclear power plants are very complex systems. The diagnoses of transients or accident conditions is very difficult because a large amount of information, which is often noisy, or intermittent, or even incomplete, need to be processed in real time. To demonstrate their potential application to nuclear power plants, neural networks axe used to monitor the accident scenarios simulated by the training simulator of TVA's Watts Bar Nuclear Power Plant. A self-organization network is used to compress original data to reduce the total number of training patterns. Different accident scenarios are closely related to different key parameters which distinguish one accident scenario from another. Therefore, the accident scenarios can be monitored by a set of small size neural networks, called modular networks, each one of which monitors only one assigned accident scenario, to obtain fast training and recall. Sensitivity analysis is applied to select proper input variables for modular networks
Transportation accident scenarios for commercial spent fuel
Energy Technology Data Exchange (ETDEWEB)
Wilmot, E L
A spectrum of high severity, low probability, transportation accident scenarios involving commercial spent fuel is presented together with mechanisms, pathways and quantities of material that might be released from spent fuel to the environment. These scenarios are based on conclusions from a workshop, conducted in May 1980 to discuss transportation accident scenarios, in which a group of experts reviewed and critiqued available literature relating to spent fuel behavior and cask response in accidents.
Accidents with biological material in workers
Cleonice Andréa Alves Cavalcante; Elisângela Franco de Oliveira Cavalcante; Maria Lúcia Azevedo Ferreira de Macêdo; Eliane Cavalcante dos Santos; Soraya Maria de Medeiros
The objective was to describe the accidents with biological material occurred among workers of Rio Grande do Norte, Brazil, between 2007 and 2009. Secondary data were collected in the National Notifiable Diseases Surveillance System by exporting data to Excel using Tabwin. Among the types of occupational accidents reported in the state, the biological accidents (no. = 1,170) accounted for 58.3% with a predominance of cases among nurses (48.6%). The percutaneous exposure was the most frequent ...
Energy Technology Data Exchange (ETDEWEB)
S.O. Bader
The purpose of this design analysis is to specify and document the total and respirable fractions for radioactive materials that are released from an accident event at the Monitored Geologic Repository (MGR) involving commercial spent nuclear fuel (CSNF) in a dry environment. The total and respirable release fractions will be used to support the preclosure licensing basis for the MGR. The total release fraction is defined as the fraction of total CSNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. The radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses. This subset of the total release fraction is referred to as the respirable release fraction. Potential accidents may involve waste forms that are characterized as either bare (unconfined) fuel assemblies or confined fuel assemblies. The confined CSNF assemblies at the MGR are contained in shipping casks, canisters, or disposal containers (waste packages). In contrast to the bare fuel assemblies, the container that confines the fuel assemblies has the potential of providing an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. However, this analysis will not take credit for this additional bamer and will establish only the total release fractions for bare unconfined CSNF assemblies, which may however be
The Accident at Fukushima: What Happened?
Energy Technology Data Exchange (ETDEWEB)
Fujie, Takao [Japan Nuclear Technology Institute - JANTI (Japan)
At 2:46 PM, on the coast of the Pacific Ocean in eastern Japan, people were spending an ordinary afternoon. The earthquake had a magnitude of 9.0, the fourth largest ever recorded in the world. Avery large number of aftershocks were felt after the initial earthquake. More than 100 of them had a magnitude of over 6.0. There were very few injured or dead at this point. The large earthquake caused by this enormous crustal deformation spawned a rare and enormous tsunami that crashed down 30-40 minutes later. It easily cleared the high levees, washing away cars and houses and swallowing buildings of up to three stories in height. The largest tsunami reading taken from all regions was 40 meters in height. This tsunami reached the West Coast of the United States and the Pacific coast of South America, with wave heights of over two meters. It was due to this tsunami that the disaster became one of a not imaginable scale, which saw the number of dead or missing reach about 20,000 persons. The enormous tsunami headed for 15 nuclear power plants on the Pacific coast, but 11 power plants withstood the tsunami and attained cold shutdown. The flood height of the tsunami that struck each power station ranged to a maximum of 15 meters. The Fukushima Daiichi Nuclear Power Plant Units experienced the largest and the cores of three reactors suffered meltdown. As a result, more than 160,000 residents were forced to evacuate, and are still living in temporary accommodation. The main focus of this presentation is on what happened at the Fukushima Daiichi, and how station personnel responded to the accident, with considerable international support. A year after the Fukushima Daiichi accident, Japan is in the process of leveraging the lessons learned from the accident to further improve the safety of nuclear power facilities and regain the trust of society. In this connection, not only international organizations, including IAEA, and WANO, but also governmental organizations and nuclear
Elements to diminish radioactive accidents
International Nuclear Information System (INIS)
In this work it is presented an application of the cause-effect diagram method or Ichikawa method identifying the elements that allow to diminish accidents when the radioactive materials are transported. It is considered the transport of hazardous materials which include radioactive materials in the period: December 1996 until March 1997. Among the identified elements by this method it is possible to mention: the road type, the radioactive source protection, the grade driver responsibility and the preparation that the OEP has in the radioactive material management. It is showed the differences found between the country inner roads and the Mexico City area. (Author)
Interventions after serious reactor accidents
International Nuclear Information System (INIS)
Manifold and promising approaches to active measures to be taken during accidents were studied hypothetically at the HTR which already has outstanding inherent safety properties in respect of afterheat removal. Based on incident scenarios prepared for hypothetical air inleakage incidents, in particular into the core of the HTR module reactor, many and various peripheral conditions for intervention possibilities could be studied. In addition, intervention possibilities appropriate for the respective incidents were examined as to their feasibility and consequences to be expected after their application. From these studies suggestions were derived for verifying experiments. (orig./HP) With 66 refs., 24 tabs., 79 figs
Guidance on accidents involving radioactivity
International Nuclear Information System (INIS)
This booklet sets out United Kingdom government policy on the management of the effects of radioactivity accidents by the Health Service. Monitoring of persons affected will be undertaken by hospital staff in order to assess damage levels for the whole population as well as treat individuals, while general practitioners will disseminate information from the Department of Health. The National Response Plan is set out, covering incidents connected with the use or transport of radioactive substances, and emergency plans for incidents in civil nuclear installations. (UK)
Accident Management in VVER-1000
Directory of Open Access Journals (Sweden)
F. D'Auria
Full Text Available The present paper deals with the investigation study on accident management in VVER-1000 reactor type conducted in the framework of a European Commission funded project. The mentioned study involved both experimental and computational fields. The purpose of this paper is to summarize the main findings from the execution of a wide-range analysis focused on AM in VVER-1000 with main regard to the qualification of computational tools and the proposal for an optimal AM strategy for this kind of NPP.
Aircraft Loss-of-Control Accident Analysis
Belcastro, Christine M.; Foster, John V.
Loss of control remains one of the largest contributors to fatal aircraft accidents worldwide. Aircraft loss-of-control accidents are complex in that they can result from numerous causal and contributing factors acting alone or (more often) in combination. Hence, there is no single intervention strategy to prevent these accidents. To gain a better understanding into aircraft loss-of-control events and possible intervention strategies, this paper presents a detailed analysis of loss-of-control accident data (predominantly from Part 121), including worst case combinations of causal and contributing factors and their sequencing. Future potential risks are also considered.
Systematics of Reconstructed Process Facility Criticality Accidents
Energy Technology Data Exchange (ETDEWEB)
Pruvost, N.L.; McLaughlin, T.P.; Monahan, S.P.
The systematics of the characteristics of twenty-one criticality accidents occurring in nuclear processing facilities of the Russian Federation, the United States, and the United Kingdom are examined. By systematics the authors mean the degree of consistency or agreement between the factual parameters reported for the accidents and the experimentally known conditions for criticality. The twenty-one reported process criticality accidents are not sufficiently well described to justify attempting detailed neutronic modeling. However, results of classic hand calculations confirm the credibility of the reported accident conditions.
The cost of nuclear accidents in France
International Nuclear Information System (INIS)
IRSN has produced estimates for costs of possible nuclear accidents on French PWRs. This paper outlines the strong differences between severe accidents, which feature a core melt but more or less controlled radioactive releases, and major accidents implying massive releases. In the first case, crisis managers would be faced with a mainly 'economic' accident, the larger part of costs being borne in a diffused fashion by the economy at large (image costs and impacts on electricity production). In the second case, authorities would be faced with the challenges of a full-scale radiological crisis involving sizeable areas of contaminated territories and large numbers of radiological refugees. (author)
Monitoring severe accidents using AI techniques
International Nuclear Information System (INIS)
After the Fukushima nuclear accident in 2011, there has been increasing concern regarding severe accidents in nuclear facilities. Severe accident scenarios are difficult for operators to monitor and identify. Therefore, accurate prediction of a severe accident is important in order to manage it appropriately in the unfavorable conditions. In this study, artificial intelligence (AI) techniques, such as support vector classification (SVC), probabilistic neural network (PNN), group method of data handling (GMDH), and fuzzy neural network (FNN), were used to monitor the major transient scenarios of a severe accident caused by three different initiating events, the hot-leg loss of coolant accident (LOCA), the cold-leg LOCA, and the steam generator tube rupture in pressurized water reactors (PWRs). The SVC and PNN models were used for the event classification. The GMDH and FNN models were employed to accurately predict the important timing representing severe accident scenarios. In addition, in order to verify the proposed algorithm, data from a number of numerical simulations were required in order to train the AI techniques due to the shortage of real LOCA data. The data was acquired by performing simulations using the MAAP4 code. The prediction accuracy of the three types of initiating events was sufficiently high to predict severe accident scenarios. Therefore, the AI techniques can be applied successfully in the identification and monitoring of severe accident scenarios in real PWRs.
Martín-Espinosa, Noelia M; Píriz-Campos, Rosa Ma; Cordeiro, Raú; Muñoz Bermejo, Laura; Casado Verdjo, Inés; Postigo Mota, Salvador
Home accidents are more common in the elderly and they can have serious consequences to the injured person's health. At home, chances to suffer accidents of any type are higher, because it's the place where old people spend most of their daily time. It is important to point out that a high percentage of domestic accidents could be easily avoided by taking some simple cautions. The main aim of this paper is to know how we can prevent most common domestic accidents in the aged population: falls, burnings, poisonings and fire prevention. PMID:27405149
Occupational Accidents with Agricultural Machinery in Austria.
Kogler, Robert; Quendler, Elisabeth; Boxberger, Josef
The number of recognized accidents with fatalities during agricultural and forestry work, despite better technology and coordinated prevention and trainings, is still very high in Austria. The accident scenarios in which people are injured are very different on farms. The common causes of accidents in agriculture and forestry are the loss of control of machine, means of transport or handling equipment, hand-held tool, and object or animal, followed by slipping, stumbling and falling, breakage, bursting, splitting, slipping, fall, and collapse of material agent. In the literature, a number of studies of general (machine- and animal-related accidents) and specific (machine-related accidents) agricultural and forestry accident situations can be found that refer to different databases. From the database Data of the Austrian Workers Compensation Board (AUVA) about occupational accidents with different agricultural machinery over the period 2008-2010 in Austria, main characteristics of the accident, the victim, and the employer as well as variables on causes and circumstances by frequency and contexts of parameters were statistically analyzed by employing the chi-square test and odds ratio. The aim of the study was to determine the information content and quality of the European Statistics on Accidents at Work (ESAW) variables to evaluate safety gaps and risks as well as the accidental man-machine interaction.
Adjusting ability and sensibility for an accident
International Nuclear Information System (INIS)
Adjusting ability (technical competence) and sensibility (consciousness) are the two most important priorities any staff member of any organization should bear in mind while acting during a nuclear or radiological emergency. The discussion is aimed at the national authorities of states which do not have a major nuclear power reactor programme, and especially at the IAEA and WHO: although a decade has gone by, the lessons from the radiological accident in Goiania have not been fully learned. The events which unravelled in the fall of 1987 took the population of the city of Goiania completely by surprise: they did not comprehend what had happened and failed to grasp what measures needed to be taken, a situation which precipitated a very complex psychological reaction, coupled with discrimination. To ensure the safety of radiation sources and nuclear installations, national and international organizations should direct their efforts towards educating and training staff in developing countries who work with ionizing radiation and promoting organizational capacity. This should be done first, by improving safety qualitatively so as to better control the uses of radioactive materials in medicine, agriculture, industry and research, and secondly, by assisting countries without a major nuclear power reactor programme to develop an objective and realistic emergency response training programme. (author)
41 CFR 101-39.407 - Accident records.
... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Accident records. 101-39...-INTERAGENCY FLEET MANAGEMENT SYSTEMS 39.4-Accidents and Claims § 101-39.407 Accident records. If GSA's records of vehicle accidents indicate that a particular activity has had an unusually high accident...
22 CFR 102.17 - Reports on accident.
... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Reports on accident. 102.17 Section 102.17... Accidents Abroad Foreign Aircraft Accidents Involving United States Persons Or Property § 102.17 Reports on accident. When an accident occurs to a foreign aircraft in the district of a Foreign Service post...
Integrated Countermeasures for Urban Industrial Disaster Reduction
Institute of Scientific and Technical Information of China (English)
JIN Lei
The 2nd UN World Conference on Disaster Reduction convened in July 1999 proposed the "Geneva Strategy" which highlighted the need that disaster reduction should be focused on cities and communities in the 21st Cent try. Having long been engaged in research on urban disaster reduction, the author noticed that although great importance has been attached to natural disasters and related accidents in recent years, little attention has been paid to urban industrial accidents that constitute the biggest threat to cities. Urban disaster reduction should be given enough attention whether in developing large and medium-sized cities or promoting the construction of small towns in China. Attention should be paid not only to the research on the mechanism of industrial accidents,but also to industrial construction and disaster reduction planning and layout. This is of strategic importance to sustainable development.
Post accident training program design at Three Mile Island
International Nuclear Information System (INIS)
The TMI preaccident training staff typically consisted of 9 professional and 3 administrative support persons. Procedures were prepared and facilities designated for operator training. The thrust of the post accident effort was directed to expanding the training function to include all other personnel while modifying the operator training to address lessons learned. Significant experiences were encountered in part task simulation, job and task analysis, decision analysis and with various external committees. These experiences led to specific opinions on industry needs in the areas of staffing, regulation, importance of training and contractor assistance
Learning Safety Assessment from Accidents in a University Environment
DEFF Research Database (Denmark)
Jensen, Niels; Jørgensen, Sten Bay
This contribution describes how a chemical engineering department started learning from accidents during experimental work and ended up implementing an industrially inspired system for risk assessment of new and existing experimental setups as well as a system for assessing potential risk from...... the chemicals used in the experimental work. These experiences have led to recent developments which focus increasingly on the a theoretical basis for modeling and reasoning on safety as well as operational aspects within a common framework. Presently this framework is being extended with barrier concepts both...
Economic damage caused by a nuclear reactor accident
International Nuclear Information System (INIS)
The impacts of a nuclear reactor accident have been estimated for: the public water supply; the use of surface water for sprinkling in agriculture, for industry water supply, recreation, etc.; and fisheries. Contamination of water sources may affect the public water supply severely. In such a situation demand of water cannot always be met. Agriculture faces production losses, if demand for uncontaminated surface water cannot be met. The impacts on recreation can also be significant. The losses to other water users are less substantial. Fisheries may lose (export) markets, as people become reluctant to buy fish and fish products. 33 refs.; 3 figs.; 35 tabs
The Fukushima major accident. Seismic, nuclear and medical considerations
International Nuclear Information System (INIS)
The first part of this voluminous report addresses mega-earthquakes and mega-tsunamis: scientific data, case of France (West Indies and metropolitan France), and socioeconomic aspects (governance, regulation, para-seismic protection). The second part deals with the nuclear accident at Fukushima: event sequence, situation of the nuclear industry in France after Fukushima, fuel cycle and future opportunities. The third part addresses health and environmental consequences. Each part is completed by a large number of documents in which some specific aspects are more precisely reported, commented and discussed
CANDU safety under severe accidents
International Nuclear Information System (INIS)
The characteristics of the CANDU reactor relevant to severe accidents are set first by the inherent properties of the design, and second by the Canadian safety/licensing approach. The pressure-tube concept allows the separate, low-pressure, heavy-water moderator to act as a backup heat sink even if there is no water in the fuel channels. Should this also fail, the calandria shell itself can contain the debris, with heat being transferred to the water-filled shield tank around the core. Should the severe core damage sequence progress further, the shield tank and the concrete reactor vault significantly delay the challenge to containment. Furthermore, should core melt lead to containment overpressure, the containment behaviour is such that leaks through the concrete containment wall reduce the possibility of catastrophic structural failure. The Canadian licensing philosophy requires that each accident, together with failure of each safety system in turn, be assessed (and specified dose limits met) as part of the design and licensing basis. In response, designers have provided CANDUs with two independent dedicated shutdown systems, and the likelihood of Anticipated Transients Without Scram is negligible. Probabilistic safety assessment studies have been performed on operating CANDU plants, and on the 4 x 880 MW(e) Darlington station now under construction; furthermore a scoping risk assessment has been done for a CANDU 600 plant. They indicate that the summed severe core damage frequency is of the order of 5 x 10-6/year. 95 refs, 3 tabs
CANDU safety under severe accidents
International Nuclear Information System (INIS)
The characteristics of the CANDU reactor relevant to severe accidents are set first by the inherent properties of the design, and second by the Canadian safety/licensing approach. Probabilistic safety assessment studies have been performed on operating CANDU plants, and on the 4 x 880 MW(e) Darlington station now under construction; furthermore a scoping risk assessment has been done for a CANDU 600 plant. They indicate that the summed severe core damage frequency is of the order of 5 x 10-6/year. CANDU nuclear plant designers and owner/operators share information and operational experience nationally and internationally through the CANDU Owners' Group (COG). The research program generally emphasizes the unique aspects of the CANDU concept, such as heat removal through the moderator, but it has also contributed significantly to areas generic to most power reactors such as hydrogen combustion, containment failure modes, fission product chemistry, and high temperature fuel behaviour. Abnormal plant operating procedures are aimed at first using event-specific emergency operating procedures, in cases where the event can be diagnosed. If this is not possible, generic procedures are followed to control Critical Safety Parameters and manage the accident. Similarly, the on-site contingency plans include a generic plan covering overall plant response strategy, and a specific plan covering each category of contingency
Dynamic response of MARS reactor under design basis accident conditions
International Nuclear Information System (INIS)
The 600 MWth MARS (Multipurpose Advanced Reactor Inherently Safe) one single loop reactor for electric power and/or industrial heat generation relies on a totally inherent and passive safety concept. The key issue of residual heat evacuation in case of accident is solved through a completely passive Emergency Core Cooling System (ECCS) which consists of two independent circuits based on natural circulation triggered by passive check valves activated by the primary pump trip. In principle such a scheme for the decay heat removal system provides for an infinite cooling capability and no man intervention is required. In case of accident the ECCS is activated by the primary pump trip and after a first transient phase, the natural forcing head assures natural convection in the ECCS. The accident analysis related to those design basis events such as Station Blackout, Steam Line Break and Steam Generator Tube Rupture, demonstrates that thanks to its inherent and passive safety features, the reactor is always correctly cooled within the required safety limits. The results evidentiate that the ECCS intervenes in a relatively short time and provides adequate coolant flow rates so that no damage to the fuel and core structures is to be expected. Even in the residual case of lack of both air condensers in the ECCS, the about 100 hours grace period' provided by the water reserve stored in the pool, reasonably allows for undertaking the most appropriate countermeasures. (author)
Implications of the Fukushima Accident on Research Reactor Safety
International Nuclear Information System (INIS)
Preliminary findings of Fukushima accident show that there is no evidence of major human errors as in previous accidents in the nuclear power industry, namely, Three Mile Island (USA) and Chernobyl (Soviet Union), and that the initiating event, a natural catastrophe of extraordinary magnitude, caused a long term loss of the normal power supply producing the failure of each defence-in depth barriers with the final release of radioactive material to the atmosphere. It is worth noticing that the direct damage caused in Japan by the earthquake and tsunami far exceeded any damage caused by the accident at the nuclear plant. In the light of this event the question whether safety systems of research reactors will cope with this type of scenarios arises. The objective of this works is to present an overview of the current practice commonly used in the safety analysis in research reactors and to assess the capability to mitigate conditions from a beyond-design-basis event like the one occurred at Fukushima power plant. (author)
Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems Analysis
Energy Technology Data Exchange (ETDEWEB)
Gilles Youinou; R. Sonat Sen
The severe accident at Fukushima Daiichi nuclear plants illustrates the need for continuous improvements through developing and implementing technologies that contribute to safe, reliable and cost-effective operation of the nuclear fleet. Development of enhanced accident tolerant fuel contributes to this effort. These fuels, in comparison with the standard zircaloy – UO2 system currently used by the LWR industry, should be designed such that they tolerate loss of active cooling in the core for a longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, and design-basis events. This report presents a preliminary systems analysis related to most of these concepts. The potential impacts of these innovative LWR fuels on the front-end of the fuel cycle, on the reactor operation and on the back-end of the fuel cycle are succinctly described without having the pretension of being exhaustive. Since the design of these various concepts is still a work in progress, this analysis can only be preliminary and could be updated as the designs converge on their respective final version.
Correspondence model of occupational accidents
Directory of Open Access Journals (Sweden)
Juan C. Conte
Full Text Available We present a new generalized model for the diagnosis and prediction of accidents among the Spanish workforce. Based on observational data of the accident rate in all Spanish companies over eleven years (7,519,732 accidents, we classified them in a new risk-injury contingency table (19×19. Through correspondence analysis, we obtained a structure composed of three axes whose combination identifies three separate risk and injury groups, which we used as a general Spanish pattern. The most likely or frequent relationships between the risk and injuries identified in the pattern facilitated the decision-making process in companies at an early stage of risk assessment. Each risk-injury group has its own characteristics, which are understandable within the phenomenological framework of the accident. The main advantages of this model are its potential application to any other country and the feasibility of contrasting different country results. One limiting factor, however, is the need to set a common classification framework for risks and injuries to enhance comparison, a framework that does not exist today. The model aims to manage work-related accidents automatically at any level.Apresentamos aqui um modelo generalizado para o diagnóstico e predição de acidentes na classe de trabalhadores da Espanha. Baseados em dados sobre a frequência de acidentes em todas as companhias da Espanha em 11 anos (7.519.732 acidentes, nós os classificamos em uma nova tabela de contingência risco-injúria (19×19. Através de uma análise por correspondência obtivemos uma estrutura composta por 3 eixos cuja combinação identifica 3 grupos separados de risco e injúria, que nós usamos como um perfil geral na Espanha. As mais prováveis ou frequentes relações entre risco e injúrias identificadas nesse perfil facilitaram o processo de decisão nas companhias em um estágio inicial de apreciação do risco. Cada grupo de risco-injúria tem suas próprias caracter
Literature survey of motorcycle accidents with respect to the influence of engine size
Honk, J. van; Klootwijk, C.W.; Ruijs, P.A.J.
For completion of the type approval of two- or three-wheeled motor vehicles, and in particular of Directive 95/1/EC of the European Community, the Directorate General III (Industry) commissioned a study to examine wether there is a relation between motorcycle accident occurence and motorcycle engine
Severe Accident Research Program plan update
International Nuclear Information System (INIS)
In August 1989, the staff published NUREG-1365, ''Revised Severe Accident Research Program Plan.'' Since 1989, significant progress has been made in severe accident research to warrant an update to NUREG-1365. The staff has prepared this SARP Plan Update to: (1) Identify those issues that have been closed or are near completion, (2) Describe the progress in our understanding of important severe accident phenomena, (3) Define the long-term research that is directed at improving our understanding of severe accident phenomena and developing improved methods for assessing core melt progression, direct containment heating, and fuel-coolant interactions, and (4) Reflect the growing emphasis in two additional areas--advanced light water reactors, and support for the assessment of criteria for containment performance during severe accidents. The report describes recent major accomplishments in understanding the underlying phenomena that can occur during a severe accident. These include Mark I liner failure, severe accident scaling methodology, source term issues, core-concrete interactions, hydrogen transport and combustion, TMI-2 Vessel Investigation Project, and direct containment heating. The report also describes the major planned activities under the SARP over the next several years. These activities will focus on two phenomenological issues (core melt progression, and fuel-coolant interactions and debris coolability) that have significant uncertainties that impact our understanding and ability to predict severe accident phenomena and their effect on containment performance SARP will also focus on severe accident code development, assessment and validation. As the staff completes the research on severe accident issues that relate to current generation reactors, continued research will focus on efforts to independently evaluate the capability of new advanced light water reactor designs to withstand severe accidents
NASA Accident Precursor Analysis Handbook, Version 1.0
Groen, Frank; Everett, Chris; Hall, Anthony; Insley, Scott
Catastrophic accidents are usually preceded by precursory events that, although observable, are not recognized as harbingers of a tragedy until after the fact. In the nuclear industry, the Three Mile Island accident was preceded by at least two events portending the potential for severe consequences from an underappreciated causal mechanism. Anomalies whose failure mechanisms were integral to the losses of Space Transportation Systems (STS) Challenger and Columbia had been occurring within the STS fleet prior to those accidents. Both the Rogers Commission Report and the Columbia Accident Investigation Board report found that processes in place at the time did not respond to the prior anomalies in a way that shed light on their true risk implications. This includes the concern that, in the words of the NASA Aerospace Safety Advisory Panel (ASAP), "no process addresses the need to update a hazard analysis when anomalies occur" At a broader level, the ASAP noted in 2007 that NASA "could better gauge the likelihood of losses by developing leading indicators, rather than continue to depend on lagging indicators". These observations suggest a need to revalidate prior assumptions and conclusions of existing safety (and reliability) analyses, as well as to consider the potential for previously unrecognized accident scenarios, when unexpected or otherwise undesired behaviors of the system are observed. This need is also discussed in NASA's system safety handbook, which advocates a view of safety assurance as driving a program to take steps that are necessary to establish and maintain a valid and credible argument for the safety of its missions. It is the premise of this handbook that making cases for safety more experience-based allows NASA to be better informed about the safety performance of its systems, and will ultimately help it to manage safety in a more effective manner. The APA process described in this handbook provides a systematic means of analyzing candidate
Evaluation of the Relationship between Job Stress and Unsafe Acts with Occupational Accidents in a Vehicle Manufacturing Plant
Directory of Open Access Journals (Sweden)
I. Mohammadfam
Full Text Available Introduction & Objective: Nowadays the vehicle manufacturing industries in Iran are critical sites as far as occupational accidents are concerned. At the same time, occupational stress and unsafe acts have also been recognized as effective factors in increasing the risk of mental and physical health problems and occupational accidents. The main aim of this research was to evaluate the relationship between job stress and unsafe acts with occupational accidents.Materials & Methods: Data were collected using of "safety behaviors sampling technique", standardized job stress questionnaire and analytical accident indices were calculated. The selection method of all samples was on a random basis. The information was then analyzed using Excel, SPSS and appropriate statistical tests.Results: The results of the study showed that there was a significant relationship between job stress and unsafe acts, the level of stress and unsafe acts with the number of occurred accidents (p-value<0.05. The study of the relationship between job stress, unsafe acts and occupational accidents via regression logistic test showed that increasing one percent in unsafe acts have more effect on accidents than increasing one grade in job stress. So, the rate or probability accidents can be predicted in organization by changes in the two mentioned variables.Conclusion: Reducing or eliminating identified effective stress factors and decreasing unsafe acts require the investment and implementation of an occupational stress management program.
Coordinability and consistency in accident causation and prevention: formal system theoretic concepts for safety in multilevel systems.
Cowlagi, Raghvendra V; Saleh, Joseph H
Although a "system approach" to accidents in sociotechnical systems has been frequently advocated, formal system theoretic concepts remain absent in the literature on accident analysis and system safety. To address this gap, we introduce the notions of coordinability and consistency from the hierarchical and multilevel systems theory literature. We then investigate the applicability and the importance of these concepts to accident causation and safety. Using illustrative examples, including the worst disaster in aviation history, and recent incidents in the United States of aircraft clipping each other on the tarmac, we propose that the lack of coordinability is a fundamental failure mechanism causing or contributing to accidents in multilevel systems. We make a similar case for the lack of consistency. Coordinability and consistency become ingredients for accident prevention, and their absence fundamental failure mechanisms that can lead to system accidents. Finally, using the concepts introduced in this work, we identify several venues for further research, including the development of a theory of coordination in multilevel systems, the investigation of potential synergies between coordinability, consistency, and the high reliability organizations paradigm, and the possibility of reframing the view that "sloppy management is the root cause of many industrial accidents" as one of lack of coordinability and/or consistency between management and operations. By introducing and expanding on the concepts of coordinability and consistency, we hope to contribute to the thinking about, and the to language of, accident causation, and prevention and to add to the intellectual toolkit of safety professionals and academics. PMID:22967134
Site restoration: Estimation of attributable costs from plutonium-dispersal accidents
International Nuclear Information System (INIS)
A nuclear weapons accident is an extremely unlikely event due to the extensive care taken in operations. However, under some hypothetical accident conditions, plutonium might be dispersed to the environment. This would result in costs being incurred by the government to remediate the site and compensate for losses. This study is a multi-disciplinary evaluation of the potential scope of the post-accident response that includes technical factors, current and proposed legal requirements and constraints, as well as social/political factors that could influence decision making. The study provides parameters that can be used to assess economic costs for accidents postulated to occur in urban areas, Midwest farmland, Western rangeland, and forest. Per-area remediation costs have been estimated, using industry-standard methods, for both expedited and extended remediation. Expedited remediation costs have been evaluated for highways, airports, and urban areas. Extended remediation costs have been evaluated for all land uses except highways and airports. The inclusion of cost estimates in risk assessments, together with the conventional estimation of doses and health effects, allows a fuller understanding of the post-accident environment. The insights obtained can be used to minimize economic risks by evaluation of operational and design alternatives, and through development of improved capabilities for accident response
The effect of work accidents on the efficiency of production in the coal sector
Directory of Open Access Journals (Sweden)
Yaşar Kasap
Full Text Available In comparison with other sectors, mining is one of the sectors with the highest rates of work accidents. Such accidents negatively affect a country's economy by wasting domestic resources and causing losses of both labour force and working days. What distinguishes mining from other branches of industry is that its working environments change continually and the working conditions are particularly harsh. Because of the practice of labour-intensive underground production methods, which leads to an increase in risk factors in terms of work accidents, and the fact that coal is a leading resource in meeting the ever-increasing demand for energy, this study investigated how work accidents affected the efficiency of production in the Turkish Hard Coal Enterprise (TTK between 1987 and 2006. Using data envelopment analysis, the overall sources of technical inefficiency in the years examined were determined. The results from this analysis revealed that the overall technical efficiency was as low as 69.7%, particularly as a result of the disaster in 1992; work accidents therefore had a negative effect on production efficiency. The greatest degree of pure technical inefficiency was found to have occurred in the period between 1992 and 2000, when the highest number of work accidents were noted, whilst the greatest degree of scale inefficiency was found to have occurred between 1987 and 1993. Because TTK has a prominent position among institutions and attaches great importance to workers' health and safety, an increase was noted in efficiency scores after 1993.
The official report of the Fukushima Nuclear Accident Independent Investigation Commission
International Nuclear Information System (INIS)
In October 2011, the Act regarding Fukushima Nuclear Accident Independent Investigation Commission was enacted to investigate the Fukushima accident with the authority to request documents and request the legislative branch to use its investigative powers to obtain any necessary documents or evidence required. In December 2011, chairman and nine other members were appointed. After a six-month investigation, Commission had concluded. 'In order to prevent future disasters, fundamental reforms must take place covering both the structure of electric power industry and the structure of related government and regulatory agencies as well as operation processes, for both normal and emergency situations'. Main parts of report consisted of overview, conclusions and recommendations, and six findings; (1) was the accident preventable?, (2) Escalation of the accident, (3) Emergency response to the accident, (4) Spread of the damage, (5) Organizational issues in accident prevention and response and (6) the legal system. Based on the above findings, Commission made seven recommendations regarding (1) Monitoring of the nuclear regulatory body by the National Diet, (2) Reform the crisis management system, (3) Government responsibility for public health and welfare, (4) Monitoring the operators, (5) Criteria for the new regulatory body, (6) Reforming laws related to nuclear energy and (7) Develop a system of independent investigation commissions. National Diet's thorough debate and deliberate on these recommendation was highly encouraged for the future. (T. Tanaka)
Bibliography for nuclear criticality accident experience, alarm systems, and emergency management
International Nuclear Information System (INIS)
The characteristics, detection, and emergency management of nuclear criticality accidents outside reactors has been an important component of criticality safety for as long as the need for this specialized safety discipline has been recognized. The general interest and importance of such topics receives special emphasis because of the potentially lethal, albeit highly localized, effects of criticality accidents and because of heightened public and regulatory concerns for any undesirable event in nuclear and radiological fields. This bibliography lists references which are potentially applicable to or interesting for criticality alarm, detection, and warning systems; criticality accident emergency management; and their associated programs. The lists are annotated to assist bibliography users in identifying applicable: industry and regulatory guidance and requirements, with historical development information and comments; criticality accident characteristics, consequences, experiences, and responses; hazard-, risk-, or safety-analysis criteria; CAS design and qualification criteria; CAS calibration, maintenance, repair, and testing criteria; experiences of CAS designers and maintainers; criticality accident emergency management (planning, preparedness, response, and recovery) requirements and guidance; criticality accident emergency management experience, plans, and techniques; methods and tools for analysis; and additional bibliographies
Bibliography for nuclear criticality accident experience, alarm systems, and emergency management
Energy Technology Data Exchange (ETDEWEB)
Putman, V.L.
The characteristics, detection, and emergency management of nuclear criticality accidents outside reactors has been an important component of criticality safety for as long as the need for this specialized safety discipline has been recognized. The general interest and importance of such topics receives special emphasis because of the potentially lethal, albeit highly localized, effects of criticality accidents and because of heightened public and regulatory concerns for any undesirable event in nuclear and radiological fields. This bibliography lists references which are potentially applicable to or interesting for criticality alarm, detection, and warning systems; criticality accident emergency management; and their associated programs. The lists are annotated to assist bibliography users in identifying applicable: industry and regulatory guidance and requirements, with historical development information and comments; criticality accident characteristics, consequences, experiences, and responses; hazard-, risk-, or safety-analysis criteria; CAS design and qualification criteria; CAS calibration, maintenance, repair, and testing criteria; experiences of CAS designers and maintainers; criticality accident emergency management (planning, preparedness, response, and recovery) requirements and guidance; criticality accident emergency management experience, plans, and techniques; methods and tools for analysis; and additional bibliographies.
Site restoration: Estimation of attributable costs from plutonium-dispersal accidents
Energy Technology Data Exchange (ETDEWEB)
Chanin, D.I.; Murfin, W.B. [Technadyne Engineering Consultants, Inc., Albuquerque, NM (United States)
A nuclear weapons accident is an extremely unlikely event due to the extensive care taken in operations. However, under some hypothetical accident conditions, plutonium might be dispersed to the environment. This would result in costs being incurred by the government to remediate the site and compensate for losses. This study is a multi-disciplinary evaluation of the potential scope of the post-accident response that includes technical factors, current and proposed legal requirements and constraints, as well as social/political factors that could influence decision making. The study provides parameters that can be used to assess economic costs for accidents postulated to occur in urban areas, Midwest farmland, Western rangeland, and forest. Per-area remediation costs have been estimated, using industry-standard methods, for both expedited and extended remediation. Expedited remediation costs have been evaluated for highways, airports, and urban areas. Extended remediation costs have been evaluated for all land uses except highways and airports. The inclusion of cost estimates in risk assessments, together with the conventional estimation of doses and health effects, allows a fuller understanding of the post-accident environment. The insights obtained can be used to minimize economic risks by evaluation of operational and design alternatives, and through development of improved capabilities for accident response.
Use of casual tree method for investigation of incidents and accidents involving radioactive materials
International Nuclear Information System (INIS)
There are many methodologies used for investigation of accidents to facilitate the search of the factors that cause these events in different areas of industry. These can be called proactive methods, if they are used before the occurrence of the events, or reactive methods that are applied after the occurrence of the incident or accident, and are used as a basis of information to prevent further events. One of these methods is the Causal Tree Method (CTM). The basic idea of this technique is that incidents and accidents result from variations in usual processes. These variations can be related to the individual, the task, the material or the environment. The tree starts with the end event (incident or accident) and works backwards. The facts relating to the end event are used in the construction of the causal tree. The end event is the starting point and only the facts that contributed to the incident or accident should be selected. The analyst has to identify and list the variations and then display them in the analytic tree, showing causal relations. The objective of this paper is to test the application of the CTM method in investigation of incidents and accidents involving radioactive materials, in order to evaluate its efficiency on finding the typical factors causing these events. (author)
Radiological accidents balance in medicine; Bilan des accidents radiologiques en medecine
Energy Technology Data Exchange (ETDEWEB)
Nenot, J.C.
This work deals with the radiological accidents in medicine. In medicine, the radiation accidents on medical personnel and patients can be the result of over dosage and bad focusing of radiotherapy sealed sources. Sometimes, the accidents, if they are unknown during a time enough for the source to be spread and to expose a lot of persons (in the case of source dismantling for instance) can take considerable dimensions. Others accidents can come from bad handling of linear accelerators and from radionuclide kinetics in some therapies. Some examples of accidents are given. (O.L.). 11 refs.
Key Characteristics of Combined Accident including TLOFW accident for PSA Modeling
Energy Technology Data Exchange (ETDEWEB)
Kim, Bo Gyung; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of); Yoon, Ho Joon [Khalifa University of Science, Technology and Research, Abu Dhabi (United Arab Emirates)
The conventional PSA techniques cannot adequately evaluate all events. The conventional PSA models usually focus on single internal events such as DBAs, the external hazards such as fire, seismic. However, the Fukushima accident of Japan in 2011 reveals that very rare event is necessary to be considered in the PSA model to prevent the radioactive release to environment caused by poor treatment based on lack of the information, and to improve the emergency operation procedure. Especially, the results from PSA can be used to decision making for regulators. Moreover, designers can consider the weakness of plant safety based on the quantified results and understand accident sequence based on human actions and system availability. This study is for PSA modeling of combined accidents including total loss of feedwater (TLOFW) accident. The TLOFW accident is a representative accident involving the failure of cooling through secondary side. If the amount of heat transfer is not enough due to the failure of secondary side, the heat will be accumulated to the primary side by continuous core decay heat. Transients with loss of feedwater include total loss of feedwater accident, loss of condenser vacuum accident, and closure of all MSIVs. When residual heat removal by the secondary side is terminated, the safety injection into the RCS with direct primary depressurization would provide alternative heat removal. This operation is called feed and bleed (F and B) operation. Combined accidents including TLOFW accident are very rare event and partially considered in conventional PSA model. Since the necessity of F and B operation is related to plant conditions, the PSA modeling for combined accidents including TLOFW accident is necessary to identify the design and operational vulnerabilities.The PSA is significant to assess the risk of NPPs, and to identify the design and operational vulnerabilities. Even though the combined accident is very rare event, the consequence of combined
Medical consequences of a nuclear plant accident
International Nuclear Information System (INIS)
The report gives background information concerning radiation and the biological medical effects and damages caused by radiation. The report also discusses nuclear power plant accidents and efforts from the medical service in the case of a nuclear power plant accident. (L.F.)
Occupational blood exposure accidents in the Netherlands.
Wijk, P.T.L. van; Schneeberger, P.M.; Heimeriks, K.; Boland, G.J.; Karagiannis, I.; Geraedts, J.; Ruijs, W.L.M.
BACKGROUND: To make proper evaluation of prevention policies possible, data on the incidence and associated medical costs of occupational blood exposure accidents in the Netherlands are needed. METHODS: Descriptive analysis of blood exposure accidents and risk estimates for occupational groups. Cost
Multiple Myeloma in Post Nuclear Accident Crisis
Wiwanitkit, Somsri; Wiwanitkit, Viroj
The problem of 2011 nuclear accident crisis draws attention of physicians and medical scientists around the world. The cancer induction is an important adverse effect of exposure to radionuclide. In this specific article, the multiple myeloma, an important hematological cancer, in the post nuclear accident crisis will be discussed.
76 FR 55079 - Recreational Vessel Accident Reporting
... notice regarding our public dockets in the January 17, 2008 issue of the Federal Register (73 FR 3316... SECURITY Coast Guard Recreational Vessel Accident Reporting AGENCY: Coast Guard, DHS. ACTION: Notice of... to improve the recreational boating accident reporting process. NBSAC recommended that the...
49 CFR 659.33 - Accident notification.
... 49 Transportation 7 2010-10-01 2010-10-01 false Accident notification. 659.33 Section 659.33 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL TRANSIT ADMINISTRATION... Agency § 659.33 Accident notification. (a) The oversight agency must require the rail transit agency...
Light-water reactor accident classification
International Nuclear Information System (INIS)
The evolution of existing classifications and definitions of light-water reactor accidents is considered. Licensing practice and licensing trends are examined with respect to terms of art such as Class 8 and Class 9 accidents. Interim definitions, consistent with current licensing practice and the regulations, are proposed for these terms of art
Radiological accident 'The Citadel' medical aspects
International Nuclear Information System (INIS)
The work exposes the medical actions carried out in the mitigation of the consequences of the accident and its main results. In a facility of storage of radioactive waste in Caracas, Venezuela, it was happened a radiological accident. This event caused radioactive contamination of the environment, as well as the irradiation and radioactive contamination of at least 10 people involved in the fact, in its majority children. Cuban institutions participated in response to the accident. Among the decisions adopted by the team of combined work Cuban-Venezuelan, we find the one of transferring affected people to Cuba, for their dosimetric and medical evaluation. Being designed a work strategy to develop the investigations to people affected by the radiological accident, in correspondence with the circumstances, magnitude and consequences of the accident. The obtained main results are: 100% presented affectations in its health, not associate directly to the accident, although the accident influenced in its psychological state. In 3 of studied people they were detected radioactive contamination with Cesium -137 with dose among 2.01 X 10-4 Sv up to 2.78 X 10-4 Sv. This accident demonstrated the necessity to have technical capacities to face these events and the importance of the international solidarity. (author)
Accidents of bus drivers : an epidemiological approach
M.L.I. Pokorny (Mirko); D.H.J. Blom (Dick)
textabstractIn the history of accident research much emphasis has been laid on general statistics, different types of case studies concentrating on various personal factor-s, circumstantial influences etc. Often, in certain waves, the unequal initial liability theory (the accident proneness concept;
48 CFR 36.513 - Accident prevention.
... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Accident prevention. 36.513 Section 36.513 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION SPECIAL... prevention. (a) The contracting officer shall insert the clause at 52.236-13, Accident Prevention,...
Global estimates of fatal occupational accidents.
Takala, J
Data on occupational accidents are not available from all countries in the world. Furthermore, underreporting, limited coverage by reporting and compensation schemes, and non-harmonized accident recording and notification systems undermine efforts to obtain worldwide information on occupational accidents. This paper presents a method and new estimated global figures of fatal accidents at work by region. The fatal occupational accident rates reported to the International Labour Office are extended to the total employed workforce in countries and regions. For areas not covered by the reported information, rates from other countries that have similar or comparable conditions are applied. In 1994, an average estimated fatal occupational accident rate in the whole world was 14.0 per 100,000 workers, and the total estimated number of fatal occupational accidents was 335,000. The rates are different for individual countries and regions and for separate branches of economic activity. In conclusion, fatal occupational accident figures are higher than previously estimated. The new estimates can be gradually improved by obtaining and adding data from countries where information is not yet available. Sectoral estimates for at least key economic branches in individual countries would further increase the accuracy.
Structural and containment response to LMFBR accidents
International Nuclear Information System (INIS)
The adequacy of the containment of fast reactors has been traditionally evaluated by analyzing the response of the containment to a spectrum of core disruptive accidents. The current approach in the U.S. is to consider fast reactor response to accidents in terms of four lines of assurance (LOAs). Thus, LOA-1 is to prevent accidents, LOA-2 is to limit core damage, LOA-3 is to control accident progression and LOA-4 is to attenuate radiological consequences. Thus, the programs on the adequacy of containment response fall into LOA-3. Significant programs to evaluate the response of the containment to core disruptive accidents and, thereby, to assure control of accident progression are in progress. These include evaluating the mechanical response of the primary system to core disruptive accidents and evaluating the thermal response of the reactor structures to core melting, including the effects this causes on the secondary containment. The analysis of structural response employs calculated pressure-volume-time loading functions. The results of the analyses establish the response of the containment to the prescribed loadings. The analysis of thermal response requires an assessment of the distribution and state of the fuel, fission products and activated materials from accident initiation to final disposition in a stable configuration
Post-Traumatic Stress After a Traffic Accident
... Stress Disorder | Post-traumatic Stress After a Traffic Accident Each year more than 6 million traffic accidents occur in the United States. If you've been in an accident, you might have experienced many different feelings at ...
Commercial SNF Accident Release Fractions
Energy Technology Data Exchange (ETDEWEB)
J. Schulz
The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release fractions are used to support the preclosure licensing basis for the repository. The total release fraction is defined as the fraction of total commercial SNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. Radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses; this subset of the total release fraction is referred to as the respirable release fraction. Accidents may involve waste forms characterized as: (1) bare unconfined intact fuel assemblies, (2) confined intact fuel assemblies, or (3) canistered failed commercial SNF. Confined intact commercial SNF assemblies at the repository are contained in shipping casks, canisters, or waste packages. Four categories of failed commercial SNF are identified: (1) mechanically and cladding-penetration damaged commercial SNF, (2) consolidated/reconstituted assemblies, (3) fuel rods, pieces, and debris, and (4) nonfuel components. It is assumed that failed commercial SNF is placed into waste packages with a mesh screen at each end (CRWMS M&O 1999). In contrast to bare unconfined fuel assemblies, the
Commercial SNF Accident Release Fractions
International Nuclear Information System (INIS)
The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release fractions are used to support the preclosure licensing basis for the repository. The total release fraction is defined as the fraction of total commercial SNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. Radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses; this subset of the total release fraction is referred to as the respirable release fraction. Accidents may involve waste forms characterized as: (1) bare unconfined intact fuel assemblies, (2) confined intact fuel assemblies, or (3) canistered failed commercial SNF. Confined intact commercial SNF assemblies at the repository are contained in shipping casks, canisters, or waste packages. Four categories of failed commercial SNF are identified: (1) mechanically and cladding-penetration damaged commercial SNF, (2) consolidated/reconstituted assemblies, (3) fuel rods, pieces, and debris, and (4) nonfuel components. It is assumed that failed commercial SNF is placed into waste packages with a mesh screen at each end (CRWMS M andO 1999). In contrast to bare unconfined fuel assemblies, the
Severe accidents in Nuclear Power Plants
International Nuclear Information System (INIS)
For the assessment of the safety of nuclear power plants it is of great importance the analyses of severe accidents since they allow to estimate the possible failure models of the containment, and also permit knowing the magnitude and composition of the radioactive material that would be released to the environment in case of an accident upon population and the environment. This paper presents in general terms the basic principles for conducting the analysis of severe accidents, the fundamental sources in the generation of radionuclides and aerosols, the transportation and deposition processes, and also makes reference to de main codes used in the modulation of severe accidents. The final part of the paper contents information on how severe accidents are dialed with the regulatory point view in different countries
General Aspects of the JCO Criticality Accident
International Nuclear Information System (INIS)
A criticality accident occurred on September 30, 1999, at a uranium processing plant of JCO Company in Tokaimura. Delayed criticality continued for approximately 20 hours after the first few prompt critical peaks. Two employees subsequently died. Nearby residents were evacuated or told to remain indoors. This accident was at Level 4 on the International Nuclear Event Scale. A table of radiation exposures resulting from the accident is given. Besides dealing with health physics, the investigation committee's final report covered technical observations and the nature of the accident. The direct causes of the accident were found to be violation of rules and technical specifications and deviation from licensing conditions; some of these were permitted by the company itself, and fatal mistakes were made by employees on the job without consulting with authorized persons. Many recommendations to revise government regulations on licensing of nuclear fuel handling were discussed in the report
The Fukushima Daiichi Accident Study Information Portal
Energy Technology Data Exchange (ETDEWEB)
Shawn St. Germain; Curtis Smith; David Schwieder; Cherie Phelan
This paper presents a description of The Fukushima Daiichi Accident Study Information Portal. The Information Portal was created by the Idaho National Laboratory as part of joint NRC and DOE project to assess the severe accident modeling capability of the MELCOR analysis code. The Fukushima Daiichi Accident Study Information Portal was created to collect, store, retrieve and validate information and data for use in reconstructing the Fukushima Daiichi accident. In addition to supporting the MELCOR simulations, the Portal will be the main DOE repository for all data, studies and reports related to the accident at the Fukushima Daiichi nuclear power station. The data is stored in a secured (password protected and encrypted) repository that is searchable and accessible to researchers at diverse locations.
Methodological guidelines for developing accident modification functions
DEFF Research Database (Denmark)
Elvik, Rune
This paper proposes methodological guidelines for developing accident modification functions. An accident modification function is a mathematical function describing systematic variation in the effects of road safety measures. The paper describes ten guidelines. An example is given of how to use...... the guidelines. The importance of exploratory analysis and an iterative approach in developing accident modification functions is stressed. The example shows that strict compliance with all the guidelines may be difficult, but represents a level of stringency that should be strived for. Currently the...... main limitations in developing accident modification functions are the small number of good evaluation studies and the often huge variation in estimates of effect. It is therefore still not possible to develop accident modification functions for very many road safety measures. © 2015 Elsevier Ltd. All...
[Clinical examinations for the traffic accident patients].
Hitosugi, Masahito
Traffic accident is a leading cause of unintentional death and about six-thousands annually died in Japan. As about one-million of persons suffer from traffic injuries, most of them seek medical attention. Therefore, medical staffs have to find the injuries accurately and treat immediately. Furthermore, the cause of accident should also be considered; why the accident was occurred, human error of the driver? To solve these problems, clinical examinations were needed. Medical staffs have to understand the characteristics of the traffic injuries: severe and multiple blunt injuries, popular injuries can be estimated with considering the pattern of the accident. Because some of the accidents are occurred when the driver is under the influence of alcohol and other drugs, screening of these subjects should be performed. Because the public is largely unaware of the preventable nature of traffic injuries, in addition to diagnose and treat accurately, we medical staffs have to attend on the primary prevention of the traffic injuries.
Review of Severe Accident Phenomena in LWR and Related Severe Accident Analysis Codes
Directory of Open Access Journals (Sweden)
Muhammad Hashim
Full Text Available Firstly, importance of severe accident provision is highlighted in view of Fukushima Daiichi accident. Then, extensive review of the past researches on severe accident phenomena in LWR is presented within this study. Various complexes, physicochemical and radiological phenomena take place during various stages of the severe accidents of Light Water Reactor (LWR plants. The review deals with progression of the severe accidents phenomena by dividing into core degradation phenomena in reactor vessel and post core melt phenomena in the containment. The development of various computer codes to analyze these severe accidents phenomena is also summarized in the review. Lastly, the need of international activity is stressed to assemble various severe accidents related knowledge systematically from research organs and compile them on the open knowledge base via the internet to be available worldwide.
Risk-based Analysis of Construction Accidents in Iran During 2007-2011-Meta Analyze Study
AMIRI, Mehran; ARDESHIR, Abdollah; FAZEL ZARANDI, Mohammad Hossein
Abstract Background The present study aimed to investigate the characteristics of occupational accidents and frequency and severity of work related accidents in the construction industry among Iranian insured workers during the years 20072011. Methods The Iranian Social Security Organization (ISSO) accident database containing 21,864 cases between the years 2007-2011 was applied in this study. In the next step, Total Accident Rate (TRA), Total Severity Index (TSI), and Risk Factor (RF) were defined. The core of this work is devoted to analyzing the data from different perspectives such as age of workers, occupation and construction phase, day of the week, time of the day, seasonal analysis, regional considerations, type of accident, and body parts affected. Results Workers between 15-19 years old (TAR=13.4%) are almost six times more exposed to risk of accident than the average of all ages (TAR=2.51%). Laborers and structural workers (TAR=66.6%) and those working at heights (TAR=47.2%) experience more accidents than other groups of workers. Moreover, older workers over 65 years old (TSI=1.97%> average TSI=1.60%), work supervisors (TSI=12.20% >average TSI=9.09%), and night shift workers (TSI=1.89% >average TSI=1.47%) are more prone to severe accidents. Conclusion It is recommended that laborers, young workers, weekend and night shift workers be supervised more carefully in the workplace. Use of Personal Protective Equipment (PPE) should be compulsory in working environments, and special attention should be undertaken to people working outdoors and at heights. It is also suggested that policymakers pay more attention to the improvement of safety conditions in deprived and cold western regions. PMID:26005662
Medical Issues Associated with Radiotherapy Accidents: Some Examples and Lessons Learned
International Nuclear Information System (INIS)
Over the past one hundred years and longer, since the discovery of ionizing radiations, radiotherapy has made great contributions to controlling human cancer. Clinical practice has improved most dramatically over the past decade as a result of better tools/computers for the identification of clinical cancer target volumes and with more precision delivery of the radiation, with the consequent sparing of normal tissues. Unfortunately, however, radiotherapy accidents, resulting in serious physical, functional and even emotional injury to cancer patients, do occur. It is, therefore, appropriate that this symposium review some of these accidents, as an attempt to better understand how to incorporate better preventive measures and to develop better medical management of the outcomes. Prevention of such accidents is, of course, always the most important way to minimize the complex medical and social issues resulting from such accidents, which always affect the patient, their families and friends, as well as the morale of the caregiver staff. As such accidents are never planned, it is important, when they do occur, to capture and record as much information as possible. The REAC/TS has for the past 40 years maintained a radiation accident registry for this purpose. The REAC/TS registry is far from complete; data from it are used as a basis for this discussion. Our worldwide registry data consist of many types of radiation accident, including industrial, nuclear power plant and medical sources, as is shown. However, it is noteworthy that the most common cause of death listed in this registry in the United States of America is due to the misuse or misadministration of medical sources, as is noted in the 'circled' group. A brief review and discussion of several of the more severe radiotherapy accidents listed in the REAC/TS registry (involving both sealed and unsealed radiotherapy sources) are presented and discussed
National registration of accidents in Iceland.
Olafsson, O; Axelsson, J
Community based registration of accidents has been employed in Iceland from 1987. A form developed in the emergency ward at the city Hospital of Reykjavik has been used for the registration. The following issues have been registered: the type and the seriousness of the injury, treatment, place of accident and time of accident. Health centres in Iceland have been computerized from 1976. At the time being about half of the health centres participate in the registration with the information included in the form as the source. Every health center has its well defined district. The accidents among the inhabitants in each district is registered, while accidents among other people, e.g. tourists, is registered separately. At this moment 183,000 out of a total number of 259,000 inhabitants are covered by the registration, i.e. 71% of the population. In 1989 the frequency of accidents was 198 per 100,000 inhabitants. 26% of the accidents occurred at home, 11% at work, 9% during physical activity, 6% was traffic accidents, whereas the same proportion occurred at school. This registration system has been created as a result of annual conferences on accidents arranged by the Director General of public health since 1984. Representatives for the following parties have been invited; medical doctors working in hospitals and health centres, clinical nurses, physiotherapists, the National Insurance Service, other insurance companies, rescue and ambulance personal, fire departments, the Automobile Association, the communication Council. Local communities members of the parliament, voluntary organizations, e.g. Red Cross, the Sea Rescue Service and the Aviation Board. This activity has stimulated measures aiming at preventing accidents in several local communities.(ABSTRACT TRUNCATED AT 250 WORDS) PMID:1285816
[Cerebral vascular accidents in French Polynesia].
Gras, C; Papouin, G; Prigent, D; Beaugendre, E; Lionet, P; Brodin, S; Legall, R; Marjou, F; Spiegel, A; Gendron, Y
The authors report on the results of a survey on cardiovascular accidents hospitalized between 01 April 1990 and 31 January 1991 carried out in the Services of Medicine and Cardiology in the Territorial Hospital Center of Papeete. This survey was: 56 cardiovascular accidents: 1/4 (hemorrhagic and 3/4 (42) ischemic. Mean age 59 (extremes 23-86). 36 males (64%); 20 females (36%). 50 Polynesians; 6 Chinese people. Among the risk factors recorded, 38 (68%) were hypertensed patients; 17 (30%) were due to tabagism and 15 (25%) to diabetes; 3 (5%) are known to be carriers of a hypercholesterolemia. 59% of the patients had no case history; 25% the cardiovascular accidents have been observed in patients with cardiopathy; 12.5% are recurrent cardiovascular accidents. Clinically, 5 transient ischemic accidents (12%) out of 42 cardiovascular ischemic accidents. High arterial tension was recognized in 12/14 (86%) of hemorrhagic cardiovascular accidents and in 26/42 (62%) of ischemic cardiovascular accidents. In 42 ischemic cardiovascular accidents, 31 patients suffered from cardiopathy (74%) of which 15 (36%) presented an embolic cardiopathy. Interest of echography and electrocardiogram are discussed. Ultrasonic exam of carotid vessels was found abnormal in almost half of the cases when utilized (12/26). Finally, etiological diagnosis was certain in 17 cases, of presumption in 16 cases, and in 9 cases, it was not possible to precise any cardiovascular etiology. Tomodensitometric tests are discussed. 86% of the ischemic cardiovascular accident were treated with anticoagulants/thrombocyte antiagglutination. 24% of the patients died, 50% recovered incompletely and 26% completely. PMID:1602953
Directory of Open Access Journals (Sweden)
Woro Riyadina
Full Text Available Occupational Accident and Injury on Industrial Workers in Jakarta Pulo Gadung Industrial Estate. Occupational accidents are stil high. There were 17 workers death each workday. Human factor is main caused risk factor of occupational accident. The objective of study to determine type of accidents and injuries related with accident at workplace in Pulogadung Industrial Estare. The study was operational research with cross sectional design. The study conducted 950 industrial workers at seven companies in 2006. Respondents were industrial workers who were worked in Jakarta Pulogadung industrial estate. Data collected based on interview with questionnaire and analyzed with statistic analysis. Result showed that industrial workers have ever been accident at workplace 29.9% with injury on hinge-hip-upper leg (40.2%, head (24,8% and hand ankle (14.3%. Type of injuries were excoriasi (37.2%, superficial (29.6% and an eyes injury (14.8%. Occupational accident often occurence on steel industry (11.2% with an eyes injury (10%, spare part industry (8.2% with pierced (6.1% andi garment industries (3.7% with pierced (43.1%. Occupational aacident correlated with male workers OR 3.25 (95% CI 2.29–4.62, moderate level of activity OR 2.08 (95% CI 1.48–2.92, distres OR 1.36 (95% CI 1.03–1.80, painful OR 1.50 (95%CI 1.13–1.98, and using safety tools OR 1.50 (95% CI 1.13–1.98. Physical condition correlated with occupational accident such as noisy OR 2.24 (95% CI 1.66–3.03, heat OR 2.19 (95%CI 1.63–2.93, close OR 2.32 (95%CI 1.57–3.41, extreme scent OR 2.01 (95%CI 1.42–2.85, dusty OR 1.87 (95%CI 1.41–2.48 and smoky OR 2.40 (95%CI 1.77–3.25.
Populations protection and territories management in nuclear emergency and post-accident situation
International Nuclear Information System (INIS)
for the management of post-accident consequences: agricultural activities and exit of the emergency stage (B. Cessac); 18 - presentation of the operational means of the GIE Groupe Intra (A. Cochard); 19 - synthetical presentation of the studies of post-accident management conditions in the milk industry (G. Machenaud); 20 - reconstruction of doses received by exposed populations (J.R. Jourdain); 21 - organisation of the health monitoring of populations after a radiological accident - presentation taken from the recommendations of the Codirpa's working group 'health stakes' (P. Pirard); 22 - losses indemnification in case of nuclear accident (M. Leger); 23 - post nuclear accident communication - reflections of the Codirpa's working group 'communication' (E. Bouchot); 24 - the ANCCLI's permanent group 'territories - post-accident' (M. Demet); 25 - experience feedback from the local information commission (CLI) 'Marcoule-Gard' in the management of a post-accident situation (J.P. Charre); 26 - commitment of intervening parties in the preparation to accident and post-accident situations: European experiences (T. Schneider); 27 - socio-cognitive exposure and risk assessment - the radio waves case (M. Poumadere). (J.S.)
Understanding accident investigators : a study of the required skills and behaviours for effective UK inspectors of accidents
Flaherty, Sarah
In the UK, accidents associated with maritime, aviation and rail transport are conducted by the Inspectors of Accidents at the Marine, Air and Rail Accident Investigation Branches. A review of current academic literature provides little insight into the qualities and attributes essential for the role of accident investigator. A wealth of material exists about accidents themselves but as yet, a study into the profile of the accident investigator has not been conducted. This research soug...
The Kychtym accident or the story of a secret catastrophe
International Nuclear Information System (INIS)
This paper analyses the causes, the circumstances and the environmental consequences of the Kychtym catastrophe (Ural, USSR) that occurred in September 29, 1957 in the fuel recycle plant of the Tcheliabinsk military-industrial complex. A brief description of the separation process and of the installations used is given to understand the conclusions of the inquiry carried out by Russian and foreign experts. The violent redox reaction between nitrates and acetates that occurred, was due to a lack of cooling in the fission products storage ponds. The catastrophe produced a huge strontium 90-rich radioactive cloud which led to a 9000 to 15000 km2 surface contamination. A comparison with the PUREX separation process used in France is given to evaluate the risk of such industrial accidents in French fuel recycle centers. (J.S.). 1 fig., 2 photos
Elevated dioxin levels in chloracne cases twenty years after the Seveso, Italy accident
Energy Technology Data Exchange (ETDEWEB)
Baccarelli, A.; Pesatori, A.C.; Consonni, D.; Bonzini, M.; Giacomini, S.M.; Bertazzi, P.A. [EPOCA Research Center, Univ. of Milan (Italy); Mocarelli, P. [Dept. of Lab. Medicine, Univ. of Milan-Bicocca, Desio (Italy); Patterson, D.G. Jr. [Centers for Disease Control and Prevention, Atlanta, GA (United States); Caporaso, N.E.; Landi, M.T. [Div. of Cancer Epidemiology and Genetics, National Cancer Inst., NIH, DHHS, Bethesda, MD (United States)
In July 1976, an industrial accident contaminated a residential area surrounding Seveso, Italy, with high levels of 2,3,7,8-Tetrachlorodibenzo-p-dioxin (TCDD). The exposure was acute, relatively pure, and affected more than 45,000 men, women, and children. By February 1978, 193 chloracne cases, mostly children, had been identified in the exposed population. Twenty years after, we conducted a case-control study on subjects diagnosed with chloracne and control subjects, who had not developed chloracne after the accident, to evaluate their TCDD plasma levels, as well as the exposure-response relationship and possible determinants of susceptibility to TCDD effects in this population.
The role of the United States Food Safety and Inspection Service after the Chernobyl accident
International Nuclear Information System (INIS)
The Food Safety and Inspection Service (FSIS) of the United States Department of Agriculture (USDA) inspects domestic and imported meat and poultry food products to assure the public that they are safe, wholesome, not economically adulterated and properly labeled. The Service also monitors the activities of meat and poultry plants and related activities in allied industries, and establishes standards and approves labels for meat and poultry products. As part of its responsibility, shortly after the Chernobyl accident occurred, FSIS developed a plan to assess this accident's impact on domestically produced and imported meat and poultry
Advance of Hazardous Operation Robot and its Application in Special Equipment Accident Rescue
Zeng, Qin-Da; Zhou, Wei; Zheng, Geng-Feng
A survey of hazardous operation robot is given out in this article. Firstly, the latest researches such as nuclear industry robot, fire-fighting robot and explosive-handling robot are shown. Secondly, existing key technologies and their shortcomings are summarized, including moving mechanism, control system, perceptive technology and power technology. Thirdly, the trend of hazardous operation robot is predicted according to current situation. Finally, characteristics and hazards of special equipment accident, as well as feasibility of hazardous operation robot in the area of special equipment accident rescue are analyzed.
Accidents in Canada: mortality and hospitalization.
Riley, R; Paddon, P
For Canadians under 45, accidents are the leading cause of both death and hospitalization. For the Canadian population as a whole, accidents rank fourth as a cause of death, after cardiovascular disease (CVD), cancer and respiratory disease. This article analyzes accident mortality and hospitalization in Canada using age-specific rates, age-standardized mortality rates (ASMR), and potential years of life lost (PYLL). The six major causes of accidental death for men are motor vehicle traffic accidents (MVTA), falls, drowning, fires, suffocation and poisoning. For women, the order is slightly different: MVTA, falls, fires, suffocation, poisoning and drowning. From 1971 to 1986, age-standardized mortality rates (ASMR) for accidents decreased by 44% for men and 39% for women. The largest decrease occurred in the under 15 age group. Accidents accounted for 11.5% of total hospital days in 1985, and 8% of hospital discharges. Because young people have the highest rates of accidental death, potential years of life lost (PYLL) are almost as high for accidents as for cardiovascular disease, although CVD deaths outnumbered accidental deaths by almost five to one in 1985.
Monitoring Severe Accidents Using AI Techniques
International Nuclear Information System (INIS)
It is very difficult for nuclear power plant operators to monitor and identify the major severe accident scenarios following an initiating event by staring at temporal trends of important parameters. The objective of this study is to develop and verify the monitoring for severe accidents using artificial intelligence (AI) techniques such as support vector classification (SVC), probabilistic neural network (PNN), group method of data handling (GMDH) and fuzzy neural network (FNN). The SVC and PNN are used for event classification among the severe accidents. Also, GMDH and FNN are used to monitor for severe accidents. The inputs to AI techniques are initial time-integrated values obtained by integrating measurement signals during a short time interval after reactor scram. In this study, 3 types of initiating events such as the hot-leg LOCA, the cold-leg LOCA and SGTR are considered and it is verified how well the proposed scenario identification algorithm using the GMDH and FNN models identifies the timings when the reactor core will be uncovered, when CET will exceed 1200 .deg. F and when the reactor vessel will fail. In cases that an initiating event develops into a severe accident, the proposed algorithm showed accurate classification of initiating events. Also, it well predicted timings for important occurrences during severe accident progression scenarios, which is very helpful for operators to perform severe accident management
Road accidents and business cycles in Spain.
Rodríguez-López, Jesús; Marrero, Gustavo A; González, Rosa Marina; Leal-Linares, Teresa
This paper explores the causes behind the downturn in road accidents in Spain across the last decade. Possible causes are grouped into three categories: Institutional factors (a Penalty Point System, PPS, dating from 2006), technological factors (active safety and passive safety of vehicles), and macroeconomic factors (the Great recession starting in 2008, and an increase in fuel prices during the spring of 2008). The PPS has been blessed by incumbent authorities as responsible for the decline of road fatalities in Spain. Using cointegration techniques, the GDP growth rate, the fuel price, the PPS, and technological items embedded in motor vehicles appear to be statistically significantly related with accidents. Importantly, PPS is found to be significant in reducing fatal accidents. However, PPS is not significant for non-fatal accidents. In view of these results, we conclude that road accidents in Spain are very sensitive to the business cycle, and that the PPS influenced the severity (fatality) rather than the quantity of accidents in Spain. Importantly, technological items help explain a sizable fraction in accidents downturn, their effects dating back from the end of the nineties.
On the application of near accident data to risk analysis of major accidents
International Nuclear Information System (INIS)
Major accidents are low frequency high consequence events which are not well supported by conventional statistical methods due to data scarcity. In the absence or shortage of major accident direct data, the use of partially related data of near accidents – accident precursor data – has drawn much attention. In the present work, a methodology has been proposed based on hierarchical Bayesian analysis and accident precursor data to risk analysis of major accidents. While hierarchical Bayesian analysis facilitates incorporation of generic data into the analysis, the dependency and interaction between accident and near accident data can be encoded via a multinomial likelihood function. We applied the proposed methodology to risk analysis of offshore blowouts and demonstrated its outperformance compared to conventional approaches. - Highlights: • Probabilistic risk analysis is applied to model major accidents. • Two-stage Bayesian updating is used to generate informative distributions. • Accident precursor data are used to develop likelihood function. • A multinomial likelihood function is introduced to model dependencies among data
Investigation of Qom Rural Area Water Network Accident in 2010 and Minimization Approaches of Accident Frequencies
Directory of Open Access Journals (Sweden)
Hossein Jafari Mansoorian
Full Text Available Background & Aims of the Study : Accidents in water networks can lead to increase the uncounted water, costs of repair, maintenance, restoration and enter water contaminants to water network. The aim of this study is to survey the accidents of Qom rural water network and choose the right approaches to reduce the number of accidents. Materials & Methods: In this cross-sectional study, four sector of Qom province (Markazi, Dastjerd, Kahak and Qahan, were assessed over a period of 8 months (July – January 2010. This study was conducted through questionnaire of Ministry of Energy. Results: The total number of accidents was 763. The highest number of accidents in the four sectors was related to Markazi sector with 228 accidents. According to the time of the accident, the highest and lowest number of accident was related to September (19.7% and November (6.8%, respectively. According to the location of the accident on network, the highest and lowest number of accident was related to distribution network (64% and connections (17.5% and transmission pipe (18.34%, respectively. According to the type of the accident, the highest and lowest number of accident was related to breaking (47.8% and gasket failure (1.2%, respectively. Considering with the pipes' material, the highest and lowest number of accident was related to polyethylene pipes (93% and steel and cast iron pipes (0.5%, 0.5%, respectively. Conclusions: Due to the high break rate of Polyethylene pipes, it is recommended to be placed in priority of leak detection and rehabilitation. .
Accidents in radiotherapy: Lack of quality assurance?
International Nuclear Information System (INIS)
About 150 radiological accidents, involving more than 3000 patients with adverse effects, 15 patient's fatalities and about 5000 staff and public exposures have been collected and analysed. Out of 67 analysed accidents in external beam therapy 22% has been caused by wrong calculation of the exposure time or monitor units, 13% by inadequate review of patient's chart, 12% by mistakes in the anatomical area to be treated. The remaining 35% can be attributed to 17 different causes. The most common mistakes in brachytherapy were wrong activities of sources used for treatment (20%), inadequate procedures for placement of sources applicators (14%), mistakes in calculating the treatment time (12%), etc. The direct and contributing causes of radiological accidents have been deduced from each event, when it was possible and categorized into 9 categories: mistakes in procedures (30%), professional mistakes (17%), communication mistakes (15%), lack of training (8.5%), interpretation mistakes (7%), lack of supervision (6%), mistakes in judgement (6%), hardware failures (5%), software and other mistakes (5.5%). Three types of direct and contributing causes responsible for almost 62% of all accidents are directly connected to the quality assurance of treatment. The lessons learnt from the accidents are related to frequencies of direct and contributing factors and show that most of the accident are caused by lack, non-application of quality assurance (QA) procedures or by underestimating of QA procedures. The international system for collection of accidents and dissemination of lessons learnt from the different accidents, proposed by IAEA, can contribute to better practice in many radiotherapy departments. Most of the accidents could have been avoided, had a comprehensive QA programme been established and properly applied in all radiotherapy departments, whatever the size. (author)
Dutch National Plan combat nuclear accidents
International Nuclear Information System (INIS)
This document presents the Dutch National Plan combat nuclear accidents (NPK). Ch. 2 discusses some important starting points which are determining for the framework and the performance of the NPK, in particular the accident typology which underlies the plan. Also the new accident-classification system for the Dutch nuclear power plants, the standardization for the measures to be taken and the staging around nuclear power plants are pursued. In ch. 3 the legal framework of the combat nuclear accidents is described. In particular the Nuclear-power law, the Accident law and the Municipality law are pursued. Also the role of province and municipality are described. Ch. 4 deals with the role of the owner/licensee of the object where the accident occurs, in the combat of accident. In ch. 5 the structure of the nuclear-accident combat at national level is outlined, subdivided in alarm phase, combat phase and the winding-up phase. In ch.'s 6-12 these phases are elaborated more in detail. In ch.'s 10-13 the measures to be taken in nuclear accidents, are described. These measures are distinguished with regard to: protection of the population and medical aspects, water economy, drinking-water supply, agriculture and food supply. Ch. 14 describes the responsibility of the burgomaster. Ch.'s 15 and 16 present an overview of the personnel, material, procedural and juridical modifications and supplements of existing structures which are necessary with regard to the new and modified parts of the structure. Ch. 17 indicates how by means of the appropriate education and exercise it can be achieved that all personnel, services and institutes concerned possess the knowledge and experience necessary for the activities from the NKP to be executed as has been described. Ch. 18 contains a survey of activities to be performed and a proposal how these can be realized. (H.W.). figs.; tabs
Estimation of the economic impacts of Three Mile Island nuclear power plant accident
International Nuclear Information System (INIS)
The Three Mile Island nuclear power plant accident had an immediate negative impact on the economy of the seven-country area which surrounds the plant site. In order to estimate the social effect of the nuclear power plant accident economically, immediate and short term economical impacts on some industrial classification have been evaluated. The economical effect to Metropolitan Edison Co., the circumstantial payment of the insurance and the lawsuit for the compensation for damages, etc. have been estimated at dollar 90 million for the manufacturing and nonmanufacturing industry, dollar 5 million for the tourist industry and dollar 50,000 for agriculture. The total loss for the state and country governments is about dollar 90,000. Metropolitan Edison Co. expended also dollar 111 million for the substitute energy and dollar 760 million for the decontamination cost. Since the lawsuit for the compensation for damages is still continuing, the total impacts cost is calculated more than a billion dollar. (author)
Systematic approach for assessment of accident risks in chemical and nuclear processing; Abordagem sistematica para avaliacao de riscos de acidentes em instalacoes de processamento quimico e nuclear
Energy Technology Data Exchange (ETDEWEB)
Senne Junior, Murillo
The industrial accidents which occurred in the last years, particularly in the 80's, contributed a significant way to draw the attention of the government, industry and the society as a whole to the mechanisms for preventing events that could affect people's safety and the environment quality. Techniques and methods extensively used the nuclear, aeronautic and war industries so far were adapted to performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. The risk analysis in industrial facilities is carried out through the evaluation of the probability or frequency of the accidents and their consequences. However, no systematized methodology that could supply the tools for identifying possible accidents likely to take place in an installation is available in the literature. Neither existing are methodologies for the identification of the models for evaluation of the accidents' consequences nor for the selection of the available techniques for qualitative or quantitative analysis of the possibility of occurrence of the accident being focused. The objective of this work is to develop and implement a methodology for identification of the risks of accidents in chemical and nuclear processing facilities as well as for the evaluation of their consequences on persons. For the development of the methodology, the main possible accidents that could occur in such installations were identified and the qualitative and quantitative techniques available for the identification of the risks and for the evaluation of the consequences of each identified accidents were selected. The use of the methodology was illustrated by applying it in two case examples adapted from the literature, involving accidents with inflammable, explosives, and radioactive materials. The computer code MRA - Methodology for Risk Assessment was developed using DELPHI, version 5.0, with the purpose of
Containment severe accident management - selected strategies
International Nuclear Information System (INIS)
The OECD Nuclear Energy Agency (NEA) organized in June 1994, in collaboration with the Swedish Nuclear Power Inspectorate (SKI), a Specialist Meeting on Selected Containment Severe Accident Management Strategies, to discuss their feasibility, effectiveness, benefits and drawbacks, and long-term impact. The meeting focused on water reactors, mainly on existing systems. The technical content covered topics such as general aspects of accident management strategies in OECD Member countries, hydrogen management techniques and other containment accident management strategies, surveillance and protection of the containment function. The main conclusions of the meeting are summarized in the paper. (author)
The epidemiology of bicyclist's collision accidents
DEFF Research Database (Denmark)
Larsen, L. B.
The number of bicyclists injured in the road traffic in collision accidents and treated at the emergency room at Odense University Hospital has increased 66% from 1980 to 1989. The aim of this study was to examine the epidemiology of bicyclist's collision accidents and identify risk groups...... of collision accidents with motor vehicles it is necessary to separate the bicyclists from the 'hard road traffic' especially at crossings. Preventive measures must also be directed at the bicyclists. Information must be given to warn the bicyclists against the risks, not only for collisions with motor...
Psychosocial risks and hydrocarbon leaks : an exploration of their relationship in the Norwegian oil and gas industry
Bergh, L.I.V.; Ringstad, A.J.; Leka, S.; Zwetsloot, G.I.J.M.
Hydrocarbon leaks have a major accident potential in the oil and gas industry. Over the years the oil and gas industry in Norway has worked hard to find means to prevent hydrocarbon leaks and is today able to report significant progress. In this context, the exploration of accidents in light of huma
Development of Methodology for Spent Fuel Pool Severe Accident Analysis Using MELCOR Program
Energy Technology Data Exchange (ETDEWEB)
Kim, Won-Tae; Shin, Jae-Uk [RETech. Co. LTD., Yongin (Korea, Republic of); Ahn, Kwang-Il [KAERI, Daejeon (Korea, Republic of)
The general reason why SFP severe accident analysis has to be considered is that there is a potential great risk due to the huge number of fuel assemblies and no containment in a SFP building. In most cases, the SFP building is vulnerable to external damage or attack. In contrary, low decay heat of fuel assemblies may make the accident processes slow compared to the accident in reactor core because of a great deal of water. In short, its severity of consequence cannot exclude the consideration of SFP risk management. The U.S. Nuclear Regulatory Commission has performed the consequence studies of postulated spent fuel pool accident. The Fukushima-Daiichi accident has accelerated the needs for the consequence studies of postulated spent fuel pool accidents, causing the nuclear industry and regulatory bodies to reexamine several assumptions concerning beyond-design basis events such as a station blackout. The tsunami brought about the loss of coolant accident, leading to the explosion of hydrogen in the SFP building. Analyses of SFP accident processes in the case of a loss of coolant with no heat removal have studied. Few studies however have focused on a long term process of SFP severe accident under no mitigation action such as a water makeup to SFP. USNRC and OECD have co-worked to examine the behavior of PWR fuel assemblies under severe accident conditions in a spent fuel rack. In support of the investigation, several new features of MELCOR model have been added to simulate both BWR fuel assembly and PWR 17 x 17 assembly in a spent fuel pool rack undergoing severe accident conditions. The purpose of the study in this paper is to develop a methodology of the long-term analysis for the plant level SFP severe accident by using the new-featured MELCOR program in the OPR-1000 Nuclear Power Plant. The study is to investigate the ability of MELCOR in predicting an entire process of SFP severe accident phenomena including the molten corium and concrete reaction. The
Ophidic accident and twin pregnancy
Directory of Open Access Journals (Sweden)
Saavedra-Orozco Héctor
Full Text Available Introduction: around of 3000 types of snakes are known, from which just 15% arevenomous. Depending of the environmental, geographical and socio-demographiccharacteristics, there are significant differences in the incidence of cases of ophidicaccidents. Colombia reports 6 by each 100.000 habitants, 2.300 cases/year, with amortality of 5.6%. In a pregnant woman it is a rare event, between 1.4% and 4%, andit usually complicates seriously to the mother and to the product of the gestation. Theprevious thing will depend of the opportunity with which the suitable management isfulfilled and of the severity of the poisoning. Nowadays it isn´t clear the security of theantiophidic serum for the product, it has been related with miscarriage in early stagesof pregnancy and fetal death at the end of the pregnancy. Nevertheless, its appropriateadministration is the unique effective measure to avoid serious consequences andmaternal death.Clinical case: patient of 16 years old, G2 C1, with diagnosis of diamniotic dichorionic twinpregnancy of 36 weeks and ophidic accident of bothropic type of 16 hours of evolution.Right inferior limb with pain, edema grade III, blush, heat, formation of flictenas andecchymosis in its distal third. Laboratory tests indicate prolongation of the clotting time,elevated transaminases and elevated creatinine. It is considered the presence of severepoisoning and management with antiophidic serum is initiated. The pregnancy is finishedby cesarean as a result of maternal renal and hepatic dysfunction, and postoperativecare in UCI. The products are born with severe respiratory depression; they are carriedto neonatal intensive care unit with good evolution and hospital expenditure to thefive days. Next day to the cesarean, the patient presents compartment syndrome,for which fasciotomy is fulfilled. When the patient gets adequate recovery, it is donea cutaneous hanging tatter and after 27 days of hospitalization one gives exit withadequate
Estimating the Influence of Accident Related Factors on Motorcycle Fatal Accidents using Logistic Regression (Case Study: Denpasar-Bali
Directory of Open Access Journals (Sweden)
Wedagama D.M.P.
Full Text Available In Denpasar the capital of Bali Province, motorcycle accident contributes to about 80% of total road accidents. Out of those motorcycle accidents, 32% are fatal accidents. This study investigates the influence of accident related factors on motorcycle fatal accidents in the city of Denpasar during period 2006-2008 using a logistic regression model. The study found that the fatality of collision with pedestrians and right angle accidents were respectively about 0.44 and 0.40 times lower than collision with other vehicles and accidents due to other factors. In contrast, the odds that a motorcycle accident will be fatal due to collision with heavy and light vehicles were 1.67 times more likely than with other motorcycles. Collision with pedestrians, right angle accidents, and heavy and light vehicles were respectively accounted for 31%, 29%, and 63% of motorcycle fatal accidents.
An Application of CICCT Accident Categories to Aviation Accidents in 1988-2004
Evans, Joni K.
Interventions or technologies developed to improve aviation safety often focus on specific causes or accident categories. Evaluation of the potential effectiveness of those interventions is dependent upon mapping the historical aviation accidents into those same accident categories. To that end, the United States civil aviation accidents occurring between 1988 and 2004 (n=26,117) were assigned accident categories based upon the taxonomy developed by the CAST/ICAO Common Taxonomy Team (CICTT). Results are presented separately for four main categories of flight rules: Part 121 (large commercial air carriers), Scheduled Part 135 (commuter airlines), Non-Scheduled Part 135 (on-demand air taxi) and Part 91 (general aviation). Injuries and aircraft damage are summarized by year and by accident category.
Accident evolution and barrier function and accident evolution management modeling of nuclear power plant incidents
International Nuclear Information System (INIS)
Every analysis of an accident or an incident is founded on a more or less explicit model of what an accident is. On a general level, the current approach models an incident or accident in a nuclear power plant as a failure to maintain a stable state with all variables within their ranges of stability. There are two main sets of subsystems in continuous interaction making up the analyzed system, namely the human-organizational and the technical subsystems. Several different but related approaches can be chosen to model an accident. However, two important difficulties accompany such modeling: the high level of system complexity and the very infrequent occurrence of accidents. The current approach acknowledges these problems and focuses on modeling reported incidents/accidents or scenarios selected in probabilistic risk assessment analyses to be of critical importance for the safety of a plant
Two serious accidents at the A-1 NPP. Analysis of the accidents the A-1 NPP
International Nuclear Information System (INIS)
In this presentation author describes the nuclear reactor A-1 in Jaslovske Bohunice (Slovakia). Author analyzes two reactor accidents which took off at this reactor. The first accident proceeded on January 5, 1976 during exchange of fuel elements when coolant - carbon dioxide - escaped. The second serious accident became on February 22, 1977 again during exchange of spent fuel elements. At this accident moderator - heavy water penetrated into the primary circuit of the reactor. Heavy water was subsequently removed from the reservoirs into the reserve tank in order not to leak out into the primary circuit. Inserting fuel element was melted. This accident was evaluated as grade 4 on seven-grade the international INES scale. A crash course and course parameters of the both accidents are analyzed.
Investigation of Qom Rural Area Water Network Accident in 2010 and Minimization Approaches of Accident Frequencies
Hossein Jafari Mansoorian; Ahmad Reza Yari; Mohsen Ansari; Shahram Nazari; Mohamad Saberi Bidgoli; Gharib Majidi
Background & Aims of the Study : Accidents in water networks can lead to increase the uncounted water, costs of repair, maintenance, restoration and enter water contaminants to water network. The aim of this study is to survey the accidents of Qom rural water network and choose the right approaches to reduce the number of accidents. Materials & Methods: In this cross-sectional study, four sector of Qom province (Markazi, Dastjerd, Kahak and Qahan), were assessed over a period of 8 mon...
National emergency plan for nuclear accidents
International Nuclear Information System (INIS)
The national emergency plan for nuclear accidents is a plan of action designed to provide a response to accidents involving the release or potential release of radioactive substances into the environment, which could give rise to radiation exposure to the public. The plan outlines the measures which are in place to assess and mitigate the effects of nuclear accidents which might pose a radiological hazard in ireland. It shows how accident management will operate, how technical information and monitoring data will be collected, how public information will be provided and what measures may be taken for the protection of the public in the short and long term. The plan can be integrated with the Department of Defence arrangements for wartime emergencies
MELCOR analysis of the TMI-2 accident
Energy Technology Data Exchange (ETDEWEB)
Boucheron, E.A.
This paper describes the analysis of the Three Mile Island-2 (TMI-2) standard problem that was performed with MELCOR. The MELCOR computer code is being developed by Sandia National Laboratories for the Nuclear Regulatory Commission for the purpose of analyzing severe accident in nuclear power plants. The primary role of MELCOR is to provide realistic predictions of severe accident phenomena and the radiological source team. The analysis of the TMI-2 standard problem allowed for comparison of the model predictions in MELCOR to plant data and to the results of more mechanistic analyses. This exercise was, therefore valuable for verifying and assessing the models in the code. The major trends in the TMI-2 accident are reasonably well predicted with MELCOR, even with its simplified modeling. Comparison of the calculated and measured results is presented and, based on this comparison, conclusions can be drawn concerning the applicability of MELCOR to severe accident analysis. 5 refs., 10 figs., 3 tabs.
Safety analysis of surface haulage accidents
Energy Technology Data Exchange (ETDEWEB)
Randolph, R.F.; Boldt, C.M.K.
Research on improving haulage truck safety, started by the U.S. Bureau of Mines, is being continued by its successors. This paper reports the orientation of the renewed research efforts, beginning with an update on accident data analysis, the role of multiple causes in these accidents, and the search for practical methods for addressing the most important causes. Fatal haulage accidents most often involve loss of control or collisions caused by a variety of factors. Lost-time injuries most often involve sprains or strains to the back or multiple body areas, which can often be attributed to rough roads and the shocks of loading and unloading. Research to reduce these accidents includes improved warning systems, shock isolation for drivers, encouraging seatbelt usage, and general improvements to system and task design.
Iodine release characteristic in reactor accidents
International Nuclear Information System (INIS)
The author describes the chemical behavior for the iodine release from the fuel element in nuclear reactor accidents, partition coefficient in the water and air and the release characteristic in time. The research of the iodine release was suggested
Internal dose assessment in radiation accidents
International Nuclear Information System (INIS)
Although numerous models have been developed for occupational and medical internal dosimetry, they may not be applicable to an accident situation. Published dose coefficients relate effective dose to intake, but if acute deterministic effects are possible, effective dose is not a useful parameter. Consequently, dose rates to the organs of interest need to be computed from first principles. Standard bioassay methods may be used to assess body contents, but, again, the standard models for bioassay interpretation may not be applicable because of the circumstances of the accident and the prompt initiation of decorporation therapy. Examples of modifications to the standard methodologies include adjustment of biological half-times under therapy, such as in the Goiania accident, and the same effect, complicated by continued input from contaminated wounds, in the Hanford 241Am accident. (author)
Crediting Tritium Deposition in Accident Analysis
Energy Technology Data Exchange (ETDEWEB)
Murphy, C.E. Jr.
This paper describes the major aspects of tritium dispersion phenomenology, summarizes deposition attributes of the computer models used in the DOE Complex for tritium dispersion, and recommends an approach to account for deposition in accident analysis.
Deterministic analyses of severe accident issues
International Nuclear Information System (INIS)
Severe accidents in light water reactors involve complex physical phenomena. In the past there has been a heavy reliance on simple assumptions regarding physical phenomena alongside of probability methods to evaluate risks associated with severe accidents. Recently GE has developed realistic methodologies that permit deterministic evaluations of severe accident progression and of some of the associated phenomena in the case of Boiling Water Reactors (BWRs). These deterministic analyses indicate that with appropriate system modifications, and operator actions, core damage can be prevented in most cases. Furthermore, in cases where core-melt is postulated, containment failure can either be prevented or significantly delayed to allow sufficient time for recovery actions to mitigate severe accidents
Medical Planning and Care in Radiation Accidents
International Nuclear Information System (INIS)
As part of a broad effort intended to mitigate the consequences of radiation accidents, the United States Atomic Energy Commission has developed a program to train physicians and to orient hospital staffs in the treatment of accident victims. Seminars have been conducted to date for approximately 120 physicians on medical planning and care in radiation accidents. This paper presents the scope and specific topics covered in the seminars, together with an analysis of. experience gained during development and presentation of the seminars. More recently the program has been expanded to encompass orientation of hospital administrators and other para-medical personnel on the handling and admittance of victims of radiation accidents. The latter problem is the subject of a new color film premiered at the Symposium. (author)
Fast detections of the accident. Radiological consequences
International Nuclear Information System (INIS)
This paper shows how the contamination due to the accident of Chernobylsk has been discovered in Sweden. The Swedish national Institute of radio-protection describes in detail the measurements done, and the decisions of radioprotection which have been taken
Review of models applicable to accident aerosols
International Nuclear Information System (INIS)
Estimations of potential airborne-particle releases are essential in safety assessments of nuclear-fuel facilities. This report is a review of aerosol behavior models that have potential applications for predicting aerosol characteristics in compartments containing accident-generated aerosol sources. Such characterization of the accident-generated aerosols is a necessary step toward estimating their eventual release in any accident scenario. Existing aerosol models can predict the size distribution, concentration, and composition of aerosols as they are acted on by ventilation, diffusion, gravity, coagulation, and other phenomena. Models developed in the fields of fluid mechanics, indoor air pollution, and nuclear-reactor accidents are reviewed with this nuclear fuel facility application in mind. The various capabilities of modeling aerosol behavior are tabulated and discussed, and recommendations are made for applying the models to problems of differing complexity
10 CFR 835.1304 - Nuclear accident dosimetry.
... 10 Energy 4 2010-01-01 2010-01-01 false Nuclear accident dosimetry. 835.1304 Section 835.1304... Nuclear accident dosimetry. (a) Installations possessing sufficient quantities of fissile material to... nuclear accident is possible, shall provide nuclear accident dosimetry for those individuals. (b)...
46 CFR 4.03-1 - Marine casualty or accident.
... 46 Shipping 1 2010-10-01 2010-10-01 false Marine casualty or accident. 4.03-1 Section 4.03-1... AND INVESTIGATIONS Definitions § 4.03-1 Marine casualty or accident. Marine casualty or accident means— (a) Any casualty or accident involving any vessel other than a public vessel that— (1) Occurs...
40 CFR 68.42 - Five-year accident history.
... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Five-year accident history. 68.42... (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Hazard Assessment § 68.42 Five-year accident history. (a) The owner or operator shall include in the five-year accident history all accidental releases...
14 CFR 415.41 - Accident investigation plan.
... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Accident investigation plan. 415.41 Section... Launch Range § 415.41 Accident investigation plan. An applicant must file an accident investigation plan... reporting and responding to launch accidents, launch incidents, or other mishaps, as defined by § 401.5...
33 CFR 173.55 - Report of casualty or accident.
... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Report of casualty or accident... (CONTINUED) BOATING SAFETY VESSEL NUMBERING AND CASUALTY AND ACCIDENT REPORTING Casualty and Accident Reporting § 173.55 Report of casualty or accident. (a) The operator of a vessel shall submit the casualty...
33 CFR 401.81 - Reporting an accident.
... 33 Navigation and Navigable Waters 3 2010-07-01 2010-07-01 false Reporting an accident. 401.81... an accident. (a) Where a vessel on the Seaway is involved in an accident or a dangerous occurrence, the master of the vessel shall report the accident or occurrence, pursuant to the requirements of...
49 CFR 382.209 - Use following an accident.
... 49 Transportation 5 2010-10-01 2010-10-01 false Use following an accident. 382.209 Section 382.209... ALCOHOL USE AND TESTING Prohibitions § 382.209 Use following an accident. No driver required to take a post-accident alcohol test under § 382.303 shall use alcohol for eight hours following the accident,...
36 CFR 1004.4 - Report of motor vehicle accident.
... accident. 1004.4 Section 1004.4 Parks, Forests, and Public Property PRESIDIO TRUST VEHICLES AND TRAFFIC SAFETY § 1004.4 Report of motor vehicle accident. (a) The operator of a motor vehicle involved in an accident resulting in property damage, personal injury or death shall report the accident to the...
49 CFR 655.44 - Post-accident testing.
... Safety Administration rule 49 CFR 389.303(a)(1) or (b)(1). (ii) The employer shall also drug and alcohol... 49 Transportation 7 2010-10-01 2010-10-01 false Post-accident testing. 655.44 Section 655.44... of Testing § 655.44 Post-accident testing. (a) Accidents. (1) Fatal accidents. (i) As soon...
Modeling secondary accidents identified by traffic shock waves.
Junhua, Wang; Boya, Liu; Lanfang, Zhang; Ragland, David R
The high potential for occurrence and the negative consequences of secondary accidents make them an issue of great concern affecting freeway safety. Using accident records from a three-year period together with California interstate freeway loop data, a dynamic method for more accurate classification based on the traffic shock wave detecting method was used to identify secondary accidents. Spatio-temporal gaps between the primary and secondary accident were proven be fit via a mixture of Weibull and normal distribution. A logistic regression model was developed to investigate major factors contributing to secondary accident occurrence. Traffic shock wave speed and volume at the occurrence of a primary accident were explicitly considered in the model, as a secondary accident is defined as an accident that occurs within the spatio-temporal impact scope of the primary accident. Results show that the shock waves originating in the wake of a primary accident have a more significant impact on the likelihood of a secondary accident occurrence than the effects of traffic volume. Primary accidents with long durations can significantly increase the possibility of secondary accidents. Unsafe speed and weather are other factors contributing to secondary crash occurrence. It is strongly suggested that when police or rescue personnel arrive at the scene of an accident, they should not suddenly block, decrease, or unblock the traffic flow, but instead endeavor to control traffic in a smooth and controlled manner. Also it is important to reduce accident processing time to reduce the risk of secondary accident. PMID:26687540
Light water reactor severe accident seminar. Seminar presentation manual
International Nuclear Information System (INIS)
The topics covered in this manual on LWR severe accidents were: Evolution of Source Term Definition and Analysis, Current Position on Severe Accident Phenomena, Current Position on Fission Product Behavior, Overview of Software Models Used in Severe Accident Analysis, Overview of Plant Specific Source Terms and Their Impact on Risk, Current Applications of Severe Accident Analysis, and Future plans
Assessment of accident risks in the CRBRP. Volume 2. Appendices
Energy Technology Data Exchange (ETDEWEB)
Appendices to Volume I include core-related accident-sequence definition, CRBRP risk-assessment sequence-probability determinations, failure-probability data, accident scenario evaluation, radioactive material release analysis, ex-core accident analysis, safety philosophy and design features, calculation of reactor accident consequences, sensitivity study, and risk from fires.
48 CFR 852.236-87 - Accident prevention.
... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Accident prevention. 852... Accident prevention. As prescribed in 836.513, insert the following clause: Accident Prevention (SEP 1993....236-13, Accident Prevention. However, only the Contracting Officer may issue an order to stop all...
46 CFR 196.30-5 - Accidents to machinery.
... 46 Shipping 7 2010-10-01 2010-10-01 false Accidents to machinery. 196.30-5 Section 196.30-5... Reports of Accidents, Repairs, and Unsafe Equipment § 196.30-5 Accidents to machinery. (a) In the event of an accident to a boiler, unfired pressure vessel, or machinery tending to render the further use...
46 CFR 97.30-5 - Accidents to machinery.
... 46 Shipping 4 2010-10-01 2010-10-01 false Accidents to machinery. 97.30-5 Section 97.30-5 Shipping... Reports of Accidents, Repairs, and Unsafe Equipment § 97.30-5 Accidents to machinery. (a) In the event of an accident to a boiler, unfired pressure vessel, or machinery tending to render the further use...
46 CFR 78.33-5 - Accidents to machinery.
... 46 Shipping 3 2010-10-01 2010-10-01 false Accidents to machinery. 78.33-5 Section 78.33-5 Shipping... Accidents, Repairs, and Unsafe Equipment § 78.33-5 Accidents to machinery. (a) In the event of an accident to a boiler, unfired pressure vessel, or machinery tending to render the further use of the...
APRI-6. Accident Phenomena of Risk Importance
Energy Technology Data Exchange (ETDEWEB)
Garis, Ninos; Ljung, J (eds.) (Swedish Radiation Safety Authority, Stockholm (Sweden)); Agrenius, Lennart (ed.) (Agrenius Ingenjoersbyraa AB, Stockholm (Sweden))
Since the early 1980s, nuclear power utilities in Sweden and the Swedish Radiation Safety Authority (SSM) collaborate on the research in severe reactor accidents. In the beginning focus was mostly on strengthening protection against environmental impacts after a severe reactor accident, for example by develop systems for the filtered relief of the reactor containment. Since the early 90s, this focus has shifted to the phenomenological issues of risk-dominant significance. During the years 2006-2008, the partnership continued in the research project APRI-6. The aim was to show whether the solutions adopted in the Swedish strategy for incident management provides adequate protection for the environment. This is done by studying important phenomena in the core melt estimating the amount of radioactivity that can be released to the atmosphere in a severe accident. To achieve these objectives the research has included monitoring of international research on severe accidents and evaluation of results and continued support for research of severe accidents at the Royal Inst. of Technology (KTH) and Chalmers University. The follow-up of international research has promoted the exchange of knowledge and experience and has given access to a wealth of information on various phenomena relevant to events in severe accidents. The continued support to KTH has provided increased knowledge about the possibility of cooling the molten core in the reactor tank and the processes associated with coolability in the confinement and about steam explosions. Support for Chalmers has increased knowledge of the accident chemistry, mainly the behavior of iodine and ruthenium in the containment after an accident.
Conclusions on severe accident research priorities
International Nuclear Information System (INIS)
Highlights: • Estimation of research priorities related to severe accident phenomena. • Consideration of new topics, partly linked to the severe accidents at Fukushima. • Consideration of results of recent projects, e.g. SARNET, ASAMPSA2, OECD projects. - Abstract: The objectives of the SARNET network of excellence are to define and work on common research programs in the field of severe accidents in Gen. II–III nuclear power plants and to further develop common tools and methodologies for safety assessment in this area. In order to ensure that the research conducted on severe accidents is efficient and well-focused, it is necessary to periodically evaluate and rank the priorities of research. This was done at the end of 2008 by the Severe Accident Research Priority (SARP) group at the end of the SARNET project of the 6th Framework Programme of European Commission (FP6). This group has updated this work in the FP7 SARNET2 project by accounting for the recent experimental results, the remaining safety issues as e.g. highlighted by Level 2 PSA national studies and the results of the recent ASAMPSA2 FP7 project. These evaluation activities were conducted in close relation with the work performed under the auspices of international organizations like OECD or IAEA. The Fukushima-Daiichi severe accidents, which occurred while SARNET2 was running, had some effects on the prioritization and definition of new research topics. Although significant progress has been gained and simulation models (e.g. the ASTEC integral code, jointly developed by IRSN and GRS) were improved, leading to an increased confidence in the predictive capabilities for assessing the success potential of countermeasures and/or mitigation measures, most of the selected research topics in 2008 are still of high priority. But the Fukushima-Daiichi accidents underlined that research efforts had to focus still more to improve severe accident management efficiency
Severe accident testing of electrical penetration assemblies
International Nuclear Information System (INIS)
This report describes the results of tests conducted on three different designs of full-size electrical penetration assemblies (EPAs) that are used in the containment buildings of nuclear power plants. The objective of the tests was to evaluate the behavior of the EPAs under simulated severe accident conditions using steam at elevated temperature and pressure. Leakage, temperature, and cable insulation resistance were monitored throughout the tests. Nuclear-qualified EPAs were produced from D. G. O'Brien, Westinghouse, and Conax. Severe-accident-sequence analysis was used to generate the severe accident conditions (SAC) for a large dry pressurized-water reactor (PWR), a boiling-water reactor (BWR) Mark I drywell, and a BWR Mark III wetwell. Based on a survey conducted by Sandia, each EPA was matched with the severe accident conditions for a specific reactor type. This included the type of containment that a particular EPA design was used in most frequently. Thus, the D. G. O'Brien EPA was chosen for the PWR SAC test, the Westinghouse was chosen for the Mark III test, and the Conax was chosen for the Mark I test. The EPAs were radiation and thermal aged to simulate the effects of a 40-year service life and loss-of-coolant accident (LOCA) before the SAC tests were conducted. The design, test preparations, conduct of the severe accident test, experimental results, posttest observations, and conclusions about the integrity and electrical performance of each EPA tested in this program are described in this report. In general, the leak integrity of the EPAs tested in this program was not compromised by severe accident loads. However, there was significant degradation in the insulation resistance of the cables, which could affect the electrical performance of equipment and devices inside containment at some point during the progression of a severe accident. 10 refs., 165 figs., 16 tabs
Severe accident testing of electrical penetration assemblies
Energy Technology Data Exchange (ETDEWEB)
Clauss, D.B. (Sandia National Labs., Albuquerque, NM (USA))
This report describes the results of tests conducted on three different designs of full-size electrical penetration assemblies (EPAs) that are used in the containment buildings of nuclear power plants. The objective of the tests was to evaluate the behavior of the EPAs under simulated severe accident conditions using steam at elevated temperature and pressure. Leakage, temperature, and cable insulation resistance were monitored throughout the tests. Nuclear-qualified EPAs were produced from D. G. O'Brien, Westinghouse, and Conax. Severe-accident-sequence analysis was used to generate the severe accident conditions (SAC) for a large dry pressurized-water reactor (PWR), a boiling-water reactor (BWR) Mark I drywell, and a BWR Mark III wetwell. Based on a survey conducted by Sandia, each EPA was matched with the severe accident conditions for a specific reactor type. This included the type of containment that a particular EPA design was used in most frequently. Thus, the D. G. O'Brien EPA was chosen for the PWR SAC test, the Westinghouse was chosen for the Mark III test, and the Conax was chosen for the Mark I test. The EPAs were radiation and thermal aged to simulate the effects of a 40-year service life and loss-of-coolant accident (LOCA) before the SAC tests were conducted. The design, test preparations, conduct of the severe accident test, experimental results, posttest observations, and conclusions about the integrity and electrical performance of each EPA tested in this program are described in this report. In general, the leak integrity of the EPAs tested in this program was not compromised by severe accident loads. However, there was significant degradation in the insulation resistance of the cables, which could affect the electrical performance of equipment and devices inside containment at some point during the progression of a severe accident. 10 refs., 165 figs., 16 tabs.
Nuclear accident impact on the ecological environment
International Nuclear Information System (INIS)
This article reviewed the eco-environmental behavior of radionuclides released into the environment by nuclear explosion and nuclear accidents, especially of several key radionuclides with biological significance, including 137Cs, 95Zr, 90Sr, 131I, 3H and 14C, in order to correctly understand the case of nuclear accidents and its pollution, maintain the social stable, and provide suitable measures for environmental protection and safety. (author)
Chernobylsk accident (Causes and Consequences)- Part 2
International Nuclear Information System (INIS)
The causes and consequences of the nuclear accident at Chernobylsk-4 reactor are shortly described. The informations were provided by Russian during the specialist meeting, carried out at seat of IAEA. The Russian nuclear panorama; the site, nuclear power plant characteristics and sequence of events; the immediate measurements after accident; monitoring/radioactive releases; environmental contamination and ecological consequences; measurements of emergency; recommendations to increase the nuclear safety; and recommendations of work groups, are presented. (M.C.K.)
Vehicle accidents related to sleep: a review
Horne, J.; Reyner, L.
Falling asleep while driving accounts for a considerable proportion of vehicle accidents under monotonous driving conditions. Many of these accidents are related to work--for example, drivers of lorries, goods vehicles, and company cars. Time of day (circadian) effects are profound, with sleepiness being particularly evident during night shift work, and driving home afterwards. Circadian factors are as important in determining driver sleepiness as is the duration of the drive, but only ...
Personality characteristics of the child accident repeater
Manheimer, Dean I.; Mellinger, Glen D
From 8874 boys and girls aged 4 to 18 in Berkeley-Oakland, California, 684 were selected to represent high-, intermediateor low-accident-liability children, based on records of medically attended injuries. Using data from intensive interviews with mothers supplemented with school records, we found a statistically significant relation between accident liability and indexes of extraversion, daring, roughhousing, and other traits tending to expose children to hazards. Similar relations held for ...
Accident analysis in nuclear power plants
International Nuclear Information System (INIS)
The way the philosophy of Safety in Depth can be verified through the analysis of simulated accidents is shown. This can be achieved by verifying that the integrity of the protection barriers against the release of radioactivity to the environment is preserved even during accident conditions. The simulation of LOCA is focalized as an example, including a study about the associated environmental radiological consequences. (Author)
Safety culture and accident analysis-A socio-management approach based on organizational safety social capital
International Nuclear Information System (INIS)
One of the biggest challenges for organizations in today's competitive business environment is to create and preserve a self-sustaining safety culture. Typically, Key drivers of safety culture in many organizations are regulation, audits, safety training, various types of employee exhortations to comply with safety norms, etc. However, less evident factors like networking relationships and social trust amongst employees, as also extended networking relationships and social trust of organizations with external stakeholders like government, suppliers, regulators, etc., which constitute the safety social capital in the Organization-seem to also influence the sustenance of organizational safety culture. Can erosion in safety social capital cause deterioration in safety culture and contribute to accidents? If so, how does it contribute? As existing accident analysis models do not provide answers to these questions, CAMSoC (Curtailing Accidents by Managing Social Capital), an accident analysis model, is proposed. As an illustration, five accidents: Bhopal (India), Hyatt Regency (USA), Tenerife (Canary Islands), Westray (Canada) and Exxon Valdez (USA) have been analyzed using CAMSoC. This limited cross-industry analysis provides two key socio-management insights: the biggest source of motivation that causes deviant behavior leading to accidents is 'Faulty Value Systems'. The second biggest source is 'Enforceable Trust'. From a management control perspective, deterioration in safety culture and resultant accidents is more due to the 'action controls' rather than explicit 'cultural controls'. Future research directions to enhance the model's utility through layering are addressed briefly
Analysis 320 coal mine accidents using structural equation modeling with unsafe conditions of the rules and regulations as exogenous variables.
Zhang, Yingyu; Shao, Wei; Zhang, Mengjia; Li, Hejun; Yin, Shijiu; Xu, Yingjun
Mining has been historically considered as a naturally high-risk industry worldwide. Deaths caused by coal mine accidents are more than the sum of all other accidents in China. Statistics of 320 coal mine accidents in Shandong province show that all accidents contain indicators of "unsafe conditions of the rules and regulations" with a frequency of 1590, accounting for 74.3% of the total frequency of 2140. "Unsafe behaviors of the operator" is another important contributory factor, which mainly includes "operator error" and "venturing into dangerous places." A systems analysis approach was applied by using structural equation modeling (SEM) to examine the interactions between the contributory factors of coal mine accidents. The analysis of results leads to three conclusions. (i) "Unsafe conditions of the rules and regulations," affect the "unsafe behaviors of the operator," "unsafe conditions of the equipment," and "unsafe conditions of the environment." (ii) The three influencing factors of coal mine accidents (with the frequency of effect relation in descending order) are "lack of safety education and training," "rules and regulations of safety production responsibility," and "rules and regulations of supervision and inspection." (iii) The three influenced factors (with the frequency in descending order) of coal mine accidents are "venturing into dangerous places," "poor workplace environment," and "operator error." PMID:27085591
Analysis 320 coal mine accidents using structural equation modeling with unsafe conditions of the rules and regulations as exogenous variables.
Zhang, Yingyu; Shao, Wei; Zhang, Mengjia; Li, Hejun; Yin, Shijiu; Xu, Yingjun
Mining has been historically considered as a naturally high-risk industry worldwide. Deaths caused by coal mine accidents are more than the sum of all other accidents in China. Statistics of 320 coal mine accidents in Shandong province show that all accidents contain indicators of "unsafe conditions of the rules and regulations" with a frequency of 1590, accounting for 74.3% of the total frequency of 2140. "Unsafe behaviors of the operator" is another important contributory factor, which mainly includes "operator error" and "venturing into dangerous places." A systems analysis approach was applied by using structural equation modeling (SEM) to examine the interactions between the contributory factors of coal mine accidents. The analysis of results leads to three conclusions. (i) "Unsafe conditions of the rules and regulations," affect the "unsafe behaviors of the operator," "unsafe conditions of the equipment," and "unsafe conditions of the environment." (ii) The three influencing factors of coal mine accidents (with the frequency of effect relation in descending order) are "lack of safety education and training," "rules and regulations of safety production responsibility," and "rules and regulations of supervision and inspection." (iii) The three influenced factors (with the frequency in descending order) of coal mine accidents are "venturing into dangerous places," "poor workplace environment," and "operator error."
Safety culture and accident analysis--a socio-management approach based on organizational safety social capital.
Rao, Suman
One of the biggest challenges for organizations in today's competitive business environment is to create and preserve a self-sustaining safety culture. Typically, the key drivers of safety culture in many organizations are regulation, audits, safety training, various types of employee exhortations to comply with safety norms, etc. However, less evident factors like networking relationships and social trust amongst employees, as also extended networking relationships and social trust of organizations with external stakeholders like government, suppliers, regulators, etc., which constitute the safety social capital in the Organization--seem to also influence the sustenance of organizational safety culture. Can erosion in safety social capital cause deterioration in safety culture and contribute to accidents? If so, how does it contribute? As existing accident analysis models do not provide answers to these questions, CAMSoC (Curtailing Accidents by Managing Social Capital), an accident analysis model, is proposed. As an illustration, five accidents: Bhopal (India), Hyatt Regency (USA), Tenerife (Canary Islands), Westray (Canada) and Exxon Valdez (USA) have been analyzed using CAMSoC. This limited cross-industry analysis provides two key socio-management insights: the biggest source of motivation that causes deviant behavior leading to accidents is 'Faulty Value Systems'. The second biggest source is 'Enforceable Trust'. From a management control perspective, deterioration in safety culture and resultant accidents is more due to the 'action controls' rather than explicit 'cultural controls'. Future research directions to enhance the model's utility through layering are addressed briefly.
Conditions for radiation protection in industrial radiography
The leaflet specifies radiation protection requirements for industrial radiography in Norway. The regulations are directed towards companies using or distributing sealed radioactive sources, x-ray equipment or accelerators in non-destructive material testing (NDT). Technical requirements to the equipment, as well as administrative requirements for use, licensing, qualifications, handling of accidents etc. are given. (Author)
PWR pressure vessel integrity during overcooling accidents
International Nuclear Information System (INIS)
Pressurized water reactors are susceptible to certain types of hypothetical accidents that under some circumstances, including operation of the reactor beyond a critical time in its life, could result in failure of the pressure vessel as a result of propagation of crack-like defects in the vessel wall. The accidents of concern are those that result in thermal shock to the vessel while the vessel is subjected to internal pressure. Such accidents, referred to as pressurized thermal shock or overcooling accidents (OCA), include a steamline break, small-break LOCA, turbine trip followed by stuck-open bypass valves, the 1978 Rancho Seco and the TMI accidents and many other postulated and actual accidents. The source of cold water for the thermal shock is either emergency core coolant or the normal primary-system coolant. ORNL performed fracture-mechanics calculations for a steamline break in 1978 and for a turbine-trip case in 1980 and concluded on the basis of the results that many more such calculations would be required. To meet the expected demand in a realistic way a computer code, OCA-I, was developed that accepts primary-system temperature and pressure transients as input and then performs one-dimensional thermal and stress analyses for the wall and a corresponding fracture-mechanics analysis for a long axial flaw. The code is briefly described, and its use in both generic and specific plant analyses is discussed
The development of severe accident analysis technology
Energy Technology Data Exchange (ETDEWEB)
Kim, Heuy Dong; Cho, Sung Won; Kim, Sang Baek; Park, Jong Hwa; Lee, Kyu Jung; Park, Lae Joon; Hu, Hoh; Hong, Sung Wan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
The objective of the development of severe accident analysis technology is to understand the severe accident phenomena such as core melt progression and to provide a reliable analytical tool to assess severe accidents in a nuclear power plant. Furthermore, establishment of the accident management strategies for the prevention/mitigation of severe accidents is also the purpose of this research. The study may be categorized into three areas. For the first area, two specific issues were reviewed to identify the further research direction, that is the natural circulation in the reactor coolant system and the fuel-coolant interaction as an in-vessel and an ex-vessel phenomenological study. For the second area, the MELCOR and the CONTAIN codes have been upgraded, and a validation calculation of the MELCOR has been performed for the PHEBUS-B9+ experiment. Finally, the experimental program has been established for the in-vessel and the ex-vessel severe accident phenomena with the in-pile test loop in KMRR and the integral containment test facilities, respectively. (Author).
Radiological accidents, scenarios, planning and answers
International Nuclear Information System (INIS)
Radiological accidents, scenarios and the importance of a good planning to prevent and control these types of accidents are presented. The radiation can be only one of the risks in an accident, most of dominant radiological risks are not radiological (fire, toxic gases, etc.). The common causes of radiological accidents, potential risks such as external irradiation, internal contamination and the environment pollution are highlighted. In addition, why accidents happen and how they evolve is explained. It describes some incidents with the radiation occurred in Costa Rica from 1993 to 2007. The coordination of emergency management in Costa Rica in relation to a radiological accident, and some mechanisms of action that have practiced in other places are focuses. Among the final considerations are the need to finalize the national plan for radiological emergencies as a tool of empowerment for the teams of emergency care and the availability of information. Likewise the processes of communication, coordination and cooperation to avoid chaos, confusion and crisis are also highlighted
Severe accident management concept for LWRS
International Nuclear Information System (INIS)
Although the advanced built-in engineered safety features and the highly trained personnel have led to extremely low probabilities of core melt accidents, there is a common understanding that even for such very unlikely accidents the plant operators must have the ability and means to mitigate the consequences of such events. This paper outlines a concept for the management of severe accidents based on 1) Computer simulations. 2) Various strategies based on core and containment damage states. 3) Calculational Aids. 4) Procedures. 5) Technical basis report. 6) Training. 7) Drills. The major benefit of this concept is the fact that there is no dedicated operating manual for severe accidents; rather the required mitigative strategies and measures are incorporated into existing accident management manuals leading to truly integrated accident management at the plant. At present this concept is going to be implemented in the NPP Geogen. Although this approach is primarily developed for existing PWRs it is also applicable to other LWRs including new NPP designs. Specific features of the plant can be taken into account by an adaptation of the concept. (authors)
President's Commission and the normal accident
International Nuclear Information System (INIS)
This chapter incorporates the major points of an analysis of the accident at Three Mile Island that I prepared in September 1979. In contrast to the findings of the President's Commission (1979), I did not view the accident as the result of operator error, an inept utility, or a negligent Nuclear Regulatory Commission but as a consequence of the complexity and interdependence that characterize the system itself. I argued that the accident was inevitable-that is, that it could not have been prevented, foreseen, or quickly terminated, because it was incomprehensible. It resembled other accidents in nuclear plants and in other high risk, complex and highly interdependent operator-machine systems; none of the accidents were caused by management or operator ineptness or by poor government regulation, though these characteristics existed and should have been expected. I maintained that the accident was normal, because in complex systems there are bound to be multiple faults that cannot be avoided by planning and that operators cannot immediately comprehend
Truck accident involving unirradiated nuclear fuel
International Nuclear Information System (INIS)
In the early morning of Dec. 16, 1991, a severe accident occurred when a passenger vehicle traveling in the wrong direction collided with a tractor trailer carrying 24 unirradiated nuclear fuel assemblies in 12 containers on Interstate I-91 in Springfield, Massachusetts. This paper documents the mechanical circumstances of the accident and assesses the physical environment to which the containers were exposed and the response of the containers and their contents. The accident involved four impacts where the truck was struck by the car, impacted on the center guardrail, impacted on the outer concrete barrier and came to rest against the center guardrail. The impacts were followed by a fire that began in the engine compartment, spread to the tractor and cab, and eventually spread to the trailer and payload. The fire lasted for about three hours and the packages were involved in the fire for about two hours. As a result of the fire, the tractor-trailer was completely destroyed and the packages were exposed to flames with temperatures between 1,300 F and 1,800 F. The fuel assemblies remained intact during the accident and there was no release of any radioactive material during the accident. This was a very severe accident; however, the injuries were minor and at no time was the public health and safety at risk
Directory of Open Access Journals (Sweden)
O. Gamankova
Full Text Available The paper deals with the peculiarities of financial provision of public and private accident insurance. Analyzes the methodology of forming insurance premium rates in private accident insurance. The study examines the practice of reforming the financial security of the state social insurance against accidents. The results show need to implement scientifically proven approach to determining premium rates in the state social insurance based on mathematical statistics and actuarial calculations to ensure that such conditions on the one hand, can insure the risk, and the other - to provide the insurer the ability to perform insurance obligations' commitments. One of the promising areas of improvement Accident Insurance determines to define increasing the role of the private sector to create and attraction of investments, financing, reduce costs, and provision of insurance services on insurance against accidents at a qualitatively higher level. The results show the need to consider the usefulness of a mixed provision of services to accident insurance under state or non-state system, and the viability and effectiveness of the combination of these systems.
Severe accident risks from external events
Institute of Scientific and Technical Information of China (English)
Randall O Gauntt
This paper reviews the early development of design requirements for seismic events in USA early developing nuclear electric generating fleet.Notable safety studies,including WASH-1400,Sandia Siting Study and the NUREG-1150 probabilistic risk study,are briefly reviewed in terms of their relevance to extreme accidents arising from seismic and other severe accident initiators.Specific characteristic about the nature of severe accidents in nuclear power plant (NPP) are reviewed along with present day state-of-art analysis methodologies (methods for estimation of leakages and consequences of releases (MELCOR) and MELCOR accident consequence code system (MACCS)) that are used to evaluate severe accidents and to optimize mitigative and protective actions against such accidents.It is the aim of this paper to make nuclear operating nations aware of the risks that accompany a much needed energy resource and to identify some of the tools,techniques and landmark safety studies that serve to make the technology safer and to maintain vigilance and adequate safety culture for the responsible management of this valuable but unforgiving technology.
On applying safety archetypes to the Fukushima accident to identify nonlinear influencing factors
International Nuclear Information System (INIS)
Nuclear power plants are typically characterized as high reliable organizations. In other words, they are organizations defined as relatively error free over a long period of time. Another relevant characteristic of the nuclear industry is that safety efforts are credited to design. However, major accidents, like the Fukushima accident, have shown that new tools are needed to identify latent deficiencies and help improve their safety level. Safety archetypes proposed elsewhere (e. g., safety issues stalled in the face of technological advances and eroding safety) consonant with International Atomic Energy Agency (IAEA) efforts are used to examine different aspects of accidents in a systemic perspective of the interaction between individuals, technology and organizational factors. Safety archetypes can help consider nonlinear interactions. Effects are rarely proportional to causes and what happens locally in a system (near the current operating point) often does not apply to distant regions (other system states), so that one has to consider the so-called nonlinear interactions. This is the case, for instance, with human probability failure estimates and safety level identification. In this paper, we discuss the Fukushima accident in order to show how archetypes can highlight nonlinear interactions of factors that influenced it and how to maintain safety levels in order to prevent other accidents. The initial evaluation of the set of archetypes suggested in the literature showed that at least four of them are applicable to the Fukushima accident, as is inferred from official reports on the accident. These are: complacency (that is, the effects of complacency on safety), decreased safety awareness, fixing on symptoms and not the real causes and eroding safety. (author)
On applying safety archetypes to the Fukushima accident to identify nonlinear influencing factors
Energy Technology Data Exchange (ETDEWEB)
Sousa, A.L., E-mail: firstname.lastname@example.com [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Ribeiro, A.C.O., E-mail: email@example.com [Bayer Crop Science Brasil S.A., Belford Roxo, RJ (Brazil); Duarte, J.P., E-mail: firstname.lastname@example.com [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Escola Politecnica. Departamento de Engenharia Nuclear; Frutuoso e Melo, P.F., E-mail: firstname.lastname@example.com [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COOPE/UFRJ), RJ (Brazil). Programa de Engenharia Nuclear
Nuclear power plants are typically characterized as high reliable organizations. In other words, they are organizations defined as relatively error free over a long period of time. Another relevant characteristic of the nuclear industry is that safety efforts are credited to design. However, major accidents, like the Fukushima accident, have shown that new tools are needed to identify latent deficiencies and help improve their safety level. Safety archetypes proposed elsewhere (e. g., safety issues stalled in the face of technological advances and eroding safety) consonant with International Atomic Energy Agency (IAEA) efforts are used to examine different aspects of accidents in a systemic perspective of the interaction between individuals, technology and organizational factors. Safety archetypes can help consider nonlinear interactions. Effects are rarely proportional to causes and what happens locally in a system (near the current operating point) often does not apply to distant regions (other system states), so that one has to consider the so-called nonlinear interactions. This is the case, for instance, with human probability failure estimates and safety level identification. In this paper, we discuss the Fukushima accident in order to show how archetypes can highlight nonlinear interactions of factors that influenced it and how to maintain safety levels in order to prevent other accidents. The initial evaluation of the set of archetypes suggested in the literature showed that at least four of them are applicable to the Fukushima accident, as is inferred from official reports on the accident. These are: complacency (that is, the effects of complacency on safety), decreased safety awareness, fixing on symptoms and not the real causes and eroding safety. (author)
Accidents in nuclear facilities: classification, incidence and impact; Accidentes en instalaciones nucleares: clasificacion, incidencia e impacto
Energy Technology Data Exchange (ETDEWEB)
Galicia A, J. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (Mexico); Paredes G, L. C., E-mail: firstname.lastname@example.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)
A general analysis of the 146 accidents reported officially in nuclear facilities from 1945 to 2012 is presented, among them some took place in: power or research nuclear reactors, critical and subcritical nuclear assemblies, handling of nuclear materials inside laboratories belonging to institutes or universities, in radiochemistry industrial plants and nuclear fuel factories. In form graph the incidence of these accidents is illustrated classified for; category, decades, geographical localization, country classification before the OECD, failure type, and the immediate or later victims. On the other hand, the main learned lessons of the nuclear accidents of Three Mile Island, Chernobyl and Fukushima are stood out, among those that highlight; the human factors, the necessity of designs more innovative and major technology for the operation, control and surveillance of the nuclear facilities, to increase the criterions of nuclear, radiological and physics safety applied to these facilities, the necessity to carry out probabilistic analysis of safety more detailed for cases of not very probable accidents and their impact, to revalue the selection criterions of the sites for nuclear locations, the methodology of post-accident sites recovery and major instrumentation for parameters evaluation and the radiological monitoring among others. (Author)
Trend of Elevator-Related Accidents in Tehran
Ali Khaji; Syyed Mohammad Ghodsi
Background: Elevator-related accidents are uncommon, but can cause significant injury. However, little data exist on these types of accidents. To compile and analyze accident data involving elevators in an effort to eliminate or at least significantly reduce such accidents. Methods: In this retrospective study we investigated 1,819 cases of elevator-related accidents during a four-year period (1999-2003) in Tehran. The data were obtained from the Tehran Safety Services & Fire Fighting Organ...
Report on the radiological accident in Goiania, Goias, Brazil
International Nuclear Information System (INIS)
The report describes the radiological accident occured in Goiania, Brazil, in september 1987. The following aspects concerning the accident are presented in specific chapters: 1- evaluation of the accident and the first aids, 2- attendance to the victims of Goiania radiological accident, 3- decontamination, 4- radioactive wastes arising from the accident, 5- working personnel and technical cooperation, 6- equipments and 7- radiation protection: limits and recommendations
Lockout/tagout accident investigation.
White, James R
When I was in boot camp, our drill instructor told us that assume makes an ass out of u and me. It was true then, and it is true today. In this instance, assumptions came into play several times, both by the worker and by the companies involved. The good news is that it did not result in a fatality, but that does not relieve the pain and suffering that the employee had to endure. This same type of scenario is likely repeated at many job sites throughout the United States. Multiple contractors, dozens--maybe hundreds--of workers, power system equipment and devices; all of these have to be taken into consideration when performing maintenance activities. It can become a blur. People are people, and people make mistakes. That is why we have OSHA regulations, NFPA 70E, company procedures, policies, etc. Most if not all of us have either been involved in accidents or know people who have been. It's not like it's a secret that people make mistakes, but talk to some and they seem to think only others have that failing. Safety is not about just any one procedure or rule. It's about slowing down, making a plan, and executing that plan. There are plenty of tools available to help us: policies, procedures, codes, standards, federal regulations, and state and local laws. I am not about to say that the worker involved in this incident was not taking safety seriously, but he failed to follow some fundamental safety rules like test-before-touch. If he had taken just that one step, there would be nothing to write about. PMID:25188988
RETRAC, Reactor Core Accident Simulation
International Nuclear Information System (INIS)
1 - Description of program or function: The RETRAC code uses a set of coupled neutron point-kinetics equations and thermal-hydraulic conservation laws to simulate nuclear reactor core behaviour under transient or accident conditions. The reactor core is represented by single equivalent unit cells composed of three regions: fuel, clad, and moderator (coolant). 2 - Method of solution: At each time step, core thermal power is calculated by solving a set of six delayed neutron group kinetics equations with adjusted reactivity feedbacks. The numerical resolution is performed by using the Runge-Kutta-Gill method. The externally inserted reactivity is specified in the input data file, whereas Doppler, fuel, clad, and water temperature reactivity feedbacks are calculated by the code itself. Core cooling is treated as a homogeneous one-dimensional fluid flow through a representative unit cell composed of three successive regions: fuel, clad, and coolant. Several flow regime models are considered for both single- and two-phase states of the coolant. The conservation laws are solved by the method of characteristics coupled with an implicit finite difference scheme to ensure stability and convergence of the numerical algorithm. Validation tests of the RETRAC code were performed by using the International Atomic Energy Agency 10-MW benchmark cores, for protected transients. Further assessment studies are in progress using experimental data. 3 - Restrictions on the complexity of the problem: The RETRAC code uses steady-state thermal-hydraulic correlations. Their use is not always justified, but it seems to be quite useful in quasi-steady cases such as as loss-of-flow transients
Severe accident management. Optimized guidelines and strategies
International Nuclear Information System (INIS)
The highest priority for mitigating the consequences of a severe accident with core melt lies in securing containment integrity, as this represents the last barrier against fission product release to the environment. Containment integrity is endangered by several physical phenomena, especially highly transient phenomena following high-pressure reactor pressure vessel failure (like direct containment heating or steam explosions which can lead to early containment failure), hydrogen combustion, quasi-static over-pressure, temperature failure of penetrations, and basemat penetration by core melt. Each of these challenges can be counteracted by dedicated severe accident mitigation hardware, like dedicated primary circuit depressurization valves, hydrogen recombiners or igniters, filtered containment venting, containment cooling systems, and core melt stabilization systems (if available). However, besides their main safety function these systems often have also secondary effects that need to be considered. Filtered containment venting causes (though limited) fission product release into the environment, primary circuit depressurization leads to loss of coolant, and an ex-vessel core melt stabilization system as well as hydrogen igniters can generate high pressure and temperature loads on the containment. To ensure that during a severe accident any available systems are used to their full beneficial extent while minimizing their potential negative impact, AREVA has implemented a severe accident management for German nuclear power plants. This concept makes use of extensive numerical simulations of the entire plant, quantifying the impact of system activations (operational systems, safety systems, as well as dedicated severe accident systems) on the accident progression for various scenarios. Based on the knowledge gained, a handbook has been developed, allowing the plant operators to understand the current state of the plant (supported by computational aids), to predict
Development of severe accident management advisory and training simulator (SAMAT)
International Nuclear Information System (INIS)
The most operator support systems including the training simulator have been developed to assist the operator and they cover from normal operation to emergency operation. For the severe accident, the overall architecture for severe accident management is being developed in some developed countries according to the development of severe accident management guidelines which are the skeleton of severe accident management architecture. In Korea, the severe accident management guideline for KSNP was recently developed and it is expected to be a central axis of logical flow for severe accident management. There are a lot of uncertainties in the severe accident phenomena and scenarios and one of the major issues for developing a operator support system for a severe accident is the reduction of these uncertainties. In this paper, the severe accident management advisory system with training simulator, SAMAT, is developed as all available information for a severe accident are re-organized and provided to the management staff in order to reduce the uncertainties. The developed system includes the graphical display for plant and equipment status, the previous research results by knowledge-base technique, and the expected plant behavior using the severe accident training simulator. The plant model used in this paper is oriented to severe accident phenomena and thus can simulate the plant behavior for a severe accident. Therefore, the developed system may make a central role of the information source for decision-making for a severe accident management, and will be used as the training simulator for severe accident management
Learning lessons from accidents with a human and organisational factors perspective: deficiencies and failures of operating experience feedback systems
International Nuclear Information System (INIS)
This paper aims at reminding the failures of operating experience feedback (OEF) systems through the lessons of accidents and provides a framework for improving the efficiency of OEF processes. The risk is for example to miss lessons from other companies and industrial sectors, or to miss the implementation of adequate corrective actions with the risk to repeat accidents. Most of major accidents have been caused by a learning failure or other organisational factors as a contributing cause among several root causes. Some of the recurring organisational factors are: -) poor recognition of critical components, of critical activities or deficiency in anticipation and detection of errors, -) excessive production pressure, -) deficiency of communication or lack of quality of dialogue, -) Excessive formalism, -) organisational complexity, -) learning deficiencies (OEF, closing feedback loops, lack of listening of whistle-blowers). Some major accidents occurred in the nuclear industry. Although the Three Mile Island accident has multiple causes, in particular, an inappropriate design of the man-machine interface, it is a striking example of the loss of external lessons from incidents. As for Fukushima it is too early to have established evidence on learning failures. The systematic study and organisational analysis of OEF failures in industrial accidents whatever their sector has enabled us to provide a framework for OEF improvements. Five key OEF issues to improve in priority: 1) human and organisational factors analysis of the root causes of the events, 2) listening to the field staff, dissenting voices and whistle-blowers, 3) monitoring of the external events that provide generic lessons, 4) building an alive memory through a culture of accidents with people who become experiences pillars, and 5) the setting of external audit or organisational analysis of the OEF system by independent experts. The paper is followed by the slides of the presentation
Exploring Environmental Effects of Accidents During Marine Transport of Dangerous Goods by Use of Accident Descriptions
DEFF Research Database (Denmark)
Rømer, Hans Gottberg; Haastrup, P.; Petersen, H J Styhr
On the basis of 1776 descriptions of water transport accidents involving dangerous goods, environmental problems in connection with releases of this kind are described and discussed. It was found that most detailed descriptions of environmental consequences concerned oil accidents, although most...
Energy Technology Data Exchange (ETDEWEB)
Buckley, R.; Hunter, C.
The United States Forest Service-Savannah River (USFS) routinely performs prescribed fires at the Savannah River Site (SRS), a Department of Energy (DOE) facility located in southwest South Carolina. This facility covers {approx}800 square kilometers and is mainly wooded except for scattered industrial areas containing facilities used in managing nuclear materials for national defense and waste processing. Prescribed fires of forest undergrowth are necessary to reduce the risk of inadvertent wild fires which have the potential to destroy large areas and threaten nuclear facility operations. This paper discusses meteorological observations and numerical model simulations from a period in early 2002 of an incident involving an early-morning multicar accident caused by poor visibility along a major roadway on the northern border of the SRS. At the time of the accident, it was not clear if the limited visibility was due solely to fog or whether smoke from a prescribed burn conducted the previous day just to the northwest of the crash site had contributed to the visibility. Through use of available meteorological information and detailed modeling, it was determined that the primary reason for the low visibility on this night was fog induced by meteorological conditions.
Emergency medical management of radiation accident. Lessons learned from the JCO criticality accident
International Nuclear Information System (INIS)
A criticality accident occurred at the JCO nuclear fuel processing plant in Tokai-mura, Japan at 10:35 am on September 30, 1999. Three workers while working nearby were exposed to high doses of radiation, especially rich in neutron. They suffered from the acute radiation syndrome and two of them were still under medical treatment. This criticality accident taught us significant lessons of radiation protection for the personnels, e.g. physicians, nurses and firemen who are expected to rescue radiation-exposed patients in radiation accidents. In this article, medical management of radiation accident, e.g. treatment of patient, with high-dosed radiation-exposure and with internal contamination of radioactive nuclides and estimation of individual radiation dose, were briefly explained. The Japanese Association for Medical Management of Radiation Accident was founded on August 29, 1997, in order to promote the mutual communication of physicians who have to be engaged in treatment of radiation-exposed patients. (author)
Pilot program: NRC severe reactor accident incident response training manual: Severe reactor accident overview
International Nuclear Information System (INIS)
This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Severe Reactor Accident Overview is the second in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assesment. Each volume serves, respectively, as the text for a course of instruction in a series of courses. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text
Iodine behaviour in severe accidents
Energy Technology Data Exchange (ETDEWEB)
Dutton, L.M.C.; Grindon, E.; Handy, B.J.; Sutherland, L. [NNC Ltd., Knutsford (United Kingdom); Bruns, W.G.; Sims, H.E. [AEA Technology, Harwell (United Kingdom); Dickinson, S. [AEA Technology, Winfrith (United Kingdom); Hueber, C.; Jacquemain, D. [IPSN/CEA, Cadarache, Saint Paul-Lez-Durance (France)
A description is given of analyses which identify which aspects of the modelling and data are most important in evaluating the release of radioactive iodine to the environment following a potential severe accident at a PWR and which identify the major uncertainties which affect that release. Three iodine codes are used namely INSPECT, IODE and IMPAIR, and their predictions are compared with those of the PSA code MAAP. INSPECT is a mechanistic code which models iodine behaviour in the aqueous aerosol, spray water and sump water, and the partitioning of volatile species between the aqueous phases and containment gas space. Organic iodine is not modelled. IODE and IMPAIR are semi-empirical codes which do not model iodine behaviour in the aqueous aerosol, but model organic iodine. The fault sequences addressed are based on analyses for the Sizewell `B` design. Two types of sequence have been analysed.: (a) those in which a major release of fission products from the primary circuit to the containment occur, e.g. a large LOCAS, (b) those where the release by-passes the containment, e.g. a leak into the auxiliary building. In the analysis of the LOCA sequences where the pH of the sump is controlled to be a value of 8 or greater, all three codes predict that the oxidation of iodine to produce gas phase species does not make a significant contribution to the source term due to leakage from the reactor building and that the latter is dominated by iodide in the aerosol. In the case where the pH of the sump is not controlled, it is found that the proportion of gas phase iodine increases significantly, although the cumulative leakage predicted by all three codes is not significantly different from that predicted by MAAP. The radiolytic production of nitric acid could be a major factor in determining the pH, and if the pH were reduced, the codes predict an increase in gas phase iodine species leaked from the containment. (author) 4 figs., 7 tabs., 13 refs.
Locating causes of accidents in the social organisation of building workers and some wider implications: An approach from Cultural Theory
International Nuclear Information System (INIS)
This paper overviews and re-interprets accident causation in the British Building and Construction Industry (BCI), chosen because its accident rate is high. The paper, a preliminary report of ongoing work, suggests why incidences vary widely between different sites and workgroups. Explanation appears to lie not in variant technical complexity but variant social organisation. Four archetypal forms of organisation are identified derived from Cultural Theory via social anthropology that avoid personality explanations, and focus on micro social organisation. Different kinds of micro social organisation are known to differentially influence attitudes to authority and risk-taking, views of time, filtering of information and deviance. This approach focuses on the social side of socio-technical systems when most commentators over-emphasise the technical and it is also appropriate to more technologically complex industries. The paper concludes with a plea to collect accident statistics with emphasis on micro social components and offers a method - LISTORG - to order the social dimensions involved. (author)
ESTRO Breur Gold Medal Award Lecture 2001: Irradiation accidents - lessons for oncology?
International Nuclear Information System (INIS)
Considering the number of radioactive sources in use all over the world (both in industry and Medicine), irradiation accidents are exceedingly rare, as demonstrated by the main databases registering such cases: UNSCEAR, IAEA, REAC/TS (Oak Ridge, USA), the German group in Ulm and the Paris Institut Curie. The precise causes of most accidents have been openly analyzed, allowing to reduce the risk of subsequent identical accidental exposures. In addition, a rapid retrospective overview shows that positive lessons could be drawn from such accidents: - Lessons for patient management: one should keep in mind that the first ever allogeneic bone marrow transplantations were performed in 1958, on scientists from Yugoslavia who had been severely irradiated in a nuclear Research laboratory. Apart from what was learned from such accidents for the management of severe aplasia, the treatment of superficial accidental exposures has also benefited radiotherapy patients in certain specific situations. - Lessons for technology: the efforts to improve safety in nuclear plants are well known; the (successful) efforts to reduce the once-elevated risks when changing the therapeutic Cobalt 60 sources are less well known. Today, most irradiation accidents (by far) are related to misuse or loss of radioactive sources from industrial radiography sets. However, here again, various technological improvements significantly reduced the risks. - Lessons for radiobiology: the need for more and more sophisticated biological dosimetry has led to studies allowing better understanding of the short- and long-term effects of radiation on human cells. Analyses of samples taken in areas which were heavily accidentally irradiated also helped to identify, in particular, the cardinal role of TGF beta and TNF alpha in the development of fibrosis and necrosis after irradiation. - Lessons for prevention of accidents in radiotherapy: only three large-scale accidents involving external radiotherapy have been
Safety and reliability in industrial organizations - The key factors
International Nuclear Information System (INIS)
A survey-based technique has been developed that measures and generates comparative data on important organizational, work group, and job-level variables that are directly related to on-the-job accidents. This paper describes the results of an analysis of data from more than 2,700 employees in the chemical, oil, construction, and wood products industries. These analyses indicate that several key variables are significantly related to accidents in the workplace
Alternative evacuation strategies for nuclear power accidents
International Nuclear Information System (INIS)
In the U.S., current protective-action strategies to safeguard the public following a nuclear power accident have remained largely unchanged since their implementation in the early 1980s. In the past thirty years, new technologies have been introduced, allowing faster computations, better modeling of predicted radiological consequences, and improved accident mapping using geographic information systems (GIS). Utilizing these new technologies, we evaluate the efficacy of alternative strategies, called adaptive protective action zones (APAZs), that use site-specific and event-specific data to dynamically determine evacuation boundaries with simple heuristics in order to better inform protective action decisions (rather than relying on pre-event regulatory bright lines). Several candidate APAZs were developed and then compared to the Nuclear Regulatory Commission's keyhole evacuation strategy (and full evacuation of the emergency planning zone). Two of the APAZs were better on average than existing NRC strategies at reducing either the radiological exposure, the population evacuated, or both. These APAZs are especially effective for larger radioactive plumes and at high population sites; one of them is better at reducing radiation exposure, while the other is better at reducing the size of the population evacuated. - Highlights: • Developed framework to compare nuclear power accident evacuation strategies. • Evacuation strategies were compared on basis of radiological and evacuation risk. • Current strategies are adequate for smaller scale nuclear power accidents. • New strategies reduced radiation exposure and evacuation size for larger accidents
NASA Medical Response to Human Spacecraft Accidents
Patlach, Robert
This slide presentation reviews NASA's role in the response to spacecraft accidents that involve human fatalities or injuries. Particular attention is given to the work of the Mishap Investigation Team (MIT), the first response to the accidents and the interface to the accident investigation board. The MIT does not investigate the accident, but the objective of the MIT is to gather, guard, preserve and document the evidence. The primary medical objectives of the MIT is to receive, analyze, identify, and transport human remains, provide assistance in the recovery effort, and to provide family Casualty Coordinators with latest recovery information. The MIT while it does not determine the cause of the accident, it acts as the fact gathering arm of the Mishap Investigation Board (MIB), which when it is activated may chose to continue to use the MIT as its field investigation resource. The MIT membership and the specific responsibilities and tasks of the flight surgeon is reviewed. The current law establishing the process is also reviewed.
Severe accident insights from the Brunswick IPE
Energy Technology Data Exchange (ETDEWEB)
Miller, G.L. (Carolina Power and Light Company, Raleigh, NC (United States))
Insights gained from the development of the level-2 analysis for a Brunswick individual plant examination (IPE) have led to severe accident insights that take advantage of the unique design of the containment structure. The Brunswick steam electric plant (BSEP) consists of two General Electric BWR-4 boiling water reactors (BWRS) with Mark I containments. The containments are unique among BWR Mark I's because the construction of the drywell and torus is reinforced concrete with steel liners. The typical Mark I is a steel shell construction. Both units are rated at 2436 MW(thermal) and [approximately]760 MW(electric). The Brunswick IPE, representing both units, was submitted to the US Nuclear Regulatory Commission in August 1992 (Ref. 1). The estimated mean core damage frequency (CDF) for the level-1 IPE is 2.7 x 10[sup [minus]5]/yr. Station blackout accident sequences contribute 66% to the overall CDF. Transient initiated sequences that involve loss of decay heat removal contribute 30% to the overall CDF. Accident sequences involving anticipated transients without scram (3%), transients with loss of high-pressure injection (I%), loss-of-coolant accidents (LOCAs) (< 1 %), and interfacing LOCAs (< 1 %) constituted the remainder of the accident sequences, which were above the analytical truncation level of 1 X 10 [sup [minus]8]/yr.
Industrial Radiography Safety in Australia
International Nuclear Information System (INIS)
cumbersome and often exceeds the prescribed OH and S single person lifting limits. The role of industrial radiography has expanded to inspect not only welds and castings, so that it now includes inspection of assembled and processed goods ranging from automotive air-bags to canned food. It is also used in security systems at airports and other facilities. Almost all these applications use cabinet systems which are rarely the subject of serious radiation incidents or accidents. Gamma ray inspection no longer uses radium. The most common radio-isotopes in use now are Cobalt 60 and Iridium 192. Their freedom from the need for an electrical power supply; their high radiation energy and the ability to place a source in positions of limited physical access, ensures the ongoing attraction of the method. The useful activity ranges of typical sources vary according to their application and the effect on total inspection costs. Common source activities in Australia range between 185 and 370 GBq for Cobalt 60; and between 1500 and 3700 GBq for Iridium 192. Outside Australia however there are recent reports of routine industrial radiography using more than 5500 GBq of Iridium 192. Thus it can be appreciated that any radiation accidents involving these high activity sources have the potential for significant radiation doses. Personal Dose Data: ARPANSA and its predecessor, the Australian Radiation Laboratory, has been providing a personal radiation monitoring service for some time, and releases a summary report every few years (ARPANSA/TR 139, ARL/TR 121, ARL/TR 107). The selected data shown in Table 2 indicate a downward trend in occupational doses received by industrial radiographers working in open site situations, which are potentially the most hazardous. This trend is encouraging, especially when the number of industrial radiographers is increasing. A comparison of the ARPANSA data indicate that whilst the average Australian industrial radiographer's annual dose is higher than the
Preliminary Investigation of Candidate Materials for Use in Accident Resistant Fuel
Energy Technology Data Exchange (ETDEWEB)
Jason M. Harp; Paul A. Lessing; Blair H. Park; Jakeob Maupin
As part of a Collaborative Research and Development Agreement (CRADA) with industry, Idaho National Laboratory (INL) is investigating several options for accident resistant uranium compounds including silicides, and nitrides for use in future light water reactor (LWR) fuels. This work is part of a larger effort to create accident tolerant fuel forms where changes to the fuel pellets, cladding, and cladding treatment are considered. The goal fuel form should have a resistance to water corrosion comparable to UO2, have an equal to or larger thermal conductivity than uranium dioxide, a melting temperature that allows the material to stay solid under power reactor conditions, and a uranium loading that maintains or improves current LWR power densities. During the course of this research, fuel fabricated at INL will be characterized, irradiated at the INL Advanced Test Reactor, and examined after irradiation at INL facilities to help inform industrial partners on candidate technologies.
Report on the preliminary fact finding mission following the accident at the nuclear fuel processing facility in Tokaimura, Japan
International Nuclear Information System (INIS)
Following the accident on 30 September 1999 at the nuclear fuel processing facility at Tokaimura, Japan, the IAEA Emergency Response Centre received numerous requests for information about the event's causes and consequences from Contact Points under the Conventions on Early Notification of a Nuclear Accident and on Assistance in the Case of a Nuclear Accident or Radiological Emergency. Although the lack of transboundary consequences of the accident meant that action under the Early Notification Convention was not triggered, the Emergency Response Centre issued several advisories to Member States which drew on official reports received from Japan. After discussions with the Government of Japan, the IAEA dispatched a team of three experts from the Secretariat on a fact finding mission to Tokaimura from 13 to 17 October 1999. The present preliminary report by that team documents key technical information obtained during the mission. At this stage, the report can in no way provide conclusive judgements on the causes and consequences of the accident. Investigations are proceeding in Japan and more information is expected to be made available after access has been gained to the building where the accident occurred. Moreover, much of the information already made available will be revised as more accurate assessments are made, for example of the radiation doses to the three individuals who received the highest exposures. Notwithstanding the preliminary nature of this report, it is clear that the accident was not one involving widespread contamination of the environment as in the 1986 Chernobyl accident. Although there was little risk off the site once the accident had been brought under control, the authorities evacuated the population living within a few hundred metres and advised people within about 10 km of the facility to take shelter for a period of about one day. The event at Tokaimura was nevertheless a serious industrial accident. The results of the detailed
Scoping Study Investigating PWR Instrumentation during a Severe Accident Scenario
Energy Technology Data Exchange (ETDEWEB)
Rempe, J. L. [Rempe and Associates, LLC, Idaho Falls, ID (United States); Knudson, D. L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lutz, R. J. [Lutz Nuclear Safety Consultant, LLC, Asheville, NC (United States)
significantly exceeded QE limits for extended time periods for the low frequency STSBO sequence evaluated in this study. It is recognized that the core damage frequency (CDF) of the sequence evaluated in this scoping effort would be considerably lower if evaluations considered new FLEX equipment being installed by industry. Nevertheless, because of uncertainties in instrumentation response when exposed to conditions beyond QE limits and alternate challenges associated with different sequences that may impact sensor performance, it is recommended that additional evaluations of instrumentation performance be completed to provide confidence that operators have access to accurate, relevant, and timely information on the status of reactor systems for a broad range of challenges associated with risk important severe accident sequences.
Occupational Outlook Quarterly, 2012
This article illustrates projected employment change by industry and industry sector over 2010-20 decade. Workers are grouped into an industry according to the type of good produced or service provided by the establishment for which they work. Industry employment projections are shown in terms of numeric change (growth or decline in the total…
With safety more safe. An intelligent data management reduces the risk of accidents and supports the accident management; Mit Sicherheit sicherer. Intelligentes Datenmanagement minimiert das Stoerfallrisiko und unterstuetzt das Stoerfallmanagement
Energy Technology Data Exchange (ETDEWEB)
Wegg, Dirk [Siemens Industry Software GmbH and Co KG, Essen (Germany)
It was not always possible to avoid accidents in industrial plants. Unfortunately, there will be no absolute security. Newest technologies, innovative solutions and effective safety concepts allow a significant reduction of the risk especially for critical applications. An intelligent data management system is an important tool for this reduction of risk.
Pressure Load Analysis during Severe Accidents for the Evaluation of Late Containment Failure in OPR-1000
International Nuclear Information System (INIS)
characterization of the risks than conservative point value estimates. This methodology provides an alternative to simple deterministic analyses and sensitivity studies for use in the containment performance analysis of a level 2 PSA, and provides insight into identify the additional research area to reduce the uncertainties associated with severe accident phenomena by an investigation of the responsible uncertain parameters, and provides a useful tool in establishing risk-informed or severe accident related regulation to the nuclear industry
Pressure Load Analysis during Severe Accidents for the Evaluation of Late Containment Failure in OPR-1000
Energy Technology Data Exchange (ETDEWEB)
Park, S. Y.; Ahn, K. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
characterization of the risks than conservative point value estimates. This methodology provides an alternative to simple deterministic analyses and sensitivity studies for use in the containment performance analysis of a level 2 PSA, and provides insight into identify the additional research area to reduce the uncertainties associated with severe accident phenomena by an investigation of the responsible uncertain parameters, and provides a useful tool in establishing risk-informed or severe accident related regulation to the nuclear industry.
Reconfigurable mobile manipulation for accident response
International Nuclear Information System (INIS)
The need for a telerobotic vehicle with hazard sensing and integral manipulation capabilities has been identified for use in transportation accidents where nuclear weapons are involved. The Accident Response Mobile Manipulation System (ARMMS) platform has been developed to provide remote dexterous manipulation and hazard sensing for the Accident Response Group (ARG) at Sandia National Laboratories. The ARMMS' mobility platform is a military HMMWV [High Mobility Multipurpose Wheeled Vehicle] that is teleoperated over RF or Fiber Optic communication channels. ARMMS is equipped with two high strength Schilling Titan II manipulators and a suite of hazardous gas and radiation sensors. Recently, a modular telerobotic control architecture call SMART (Sandia Modular Architecture for Robotic and Teleoperation) has been applied to ARMMS. SMART enables input devices and many system behaviors to be rapidly configured in the field for specific mission needs. This paper summarizes current SMART developments applied to ARMMS
Agricultural implications of the Fukushima nuclear accident.
Nakanishi, Tomoko M
More than 4 years has passed since the accident at the Fukushima Nuclear Power Plant. Immediately after the accident, 40 to 50 academic staff of the Graduate School of Agricultural and Life Sciences at the University of Tokyo created an independent team to monitor the behavior of the radioactive materials in the field and their effects on agricultural farm lands, forests, rivers, animals, etc. When the radioactive nuclides from the nuclear power plant fell, they were instantly adsorbed at the site where they first touched; consequently, the fallout was found as scattered spots on the surface of anything that was exposed to the air at the time of the accident. The adsorption has become stronger over time, so the radioactive nuclides are now difficult to remove. The findings of our study regarding the wide range of effects on agricultural fields are summarized in this report. PMID:27538845
Fission product behaviour in severe accidents
International Nuclear Information System (INIS)
The understanding of fission product (FP) behaviour in severe accidents is important for source term assessment and accident mitigation measures. For example in accident management the operator needs to know the effect of different actions on the behaviour and release of fission products. At VTT fission product behaviour have been studied in different national and international projects. In this presentation the results of projects in EU funded 4th framework programme Nuclear Fission Safety 1994-1998 are reported. The projects are: fission product vapour/aerosol chemistry in the primary circuit (FI4SCT960020), aerosol physics in containment (FI4SCT950016), revaporisation of test samples from Phebus fission products (FI4SCT960019) and assessment of models for fission product revaporisation (FI4SCT960044). Also results from the national project 'aerosol experiments in the Victoria facility' funded by IVO PE and VTT Energy are reported
Enhanced Accident Tolerant LWR Fuels: Metrics Development
Energy Technology Data Exchange (ETDEWEB)
Shannon Bragg-Sitton; Lori Braase; Rose Montgomery; Chris Stanek; Robert Montgomery; Lance Snead; Larry Ott; Mike Billone
The Department of Energy (DOE) Fuel Cycle Research and Development (FCRD) Advanced Fuels Campaign (AFC) is conducting research and development on enhanced Accident Tolerant Fuels (ATF) for light water reactors (LWRs). This mission emphasizes the development of novel fuel and cladding concepts to replace the current zirconium alloy-uranium dioxide (UO2) fuel system. The overall mission of the ATF research is to develop advanced fuels/cladding with improved performance, reliability and safety characteristics during normal operations and accident conditions, while minimizing waste generation. The initial effort will focus on implementation in operating reactors or reactors with design certifications. To initiate the development of quantitative metrics for ATR, a LWR Enhanced Accident Tolerant Fuels Metrics Development Workshop was held in October 2012 in Germantown, MD. This paper summarizes the outcome of that workshop and the current status of metrics development for LWR ATF.
Monitoring and surveillance in accident situations
International Nuclear Information System (INIS)
The Chernobyl accident, which occurred on 26 April 1986, presented major challenges to the European Community with respect to the practical and regulatory aspects of radiation protection, public information, trade -particularly in food - and international politics. The Chernobyl accident was also a major challenge to the international scientific community which had to evaluate rapidly the radiological consequences of the accident and advise on the introduction at Chernobyl, countermeasures to reduce the consequences of radioactive contamination had been conceived largely in the context of relatively small accidental releases and for application over relatively small areas. Less consideration had been given to the practical implications of applying such measures in the case of a large source and a spread over a very large area
Estimating radiation doses from reactor accidents
International Nuclear Information System (INIS)
In order to plan for emergency response to reactor accidents involving large radiation releases, it is necessary to determine the medical resources, such as diagnostic laboratory tests, hospital facilities and convalescent care, needed to care for a large population exposed to radiation. A determination of the needed medical resources is difficult because of the widely varying sensitivity humans exhibit to radiation exposure and because of the large number of assumptions involved in predicting radiation dispersion. This paper demonstrates a simple method for approximating medical needs in response to a severe reactor accident. The method requires a model for radiation dispersion from the accident and data for population distribution surrounding the reactor. With this information, tables developed in this paper may be used to project medical needs. The needs identified by this methodology may be compared against the actual medical resources of nearby communities to determine the size of the area impacted
A Review of Criticality Accidents 2000 Revision
International Nuclear Information System (INIS)
Criticality accidents and the characteristics of prompt power excursions are discussed. Sixty accidental power excursions are reviewed. Sufficient detail is provided to enable the reader to understand the physical situation, the chemistry and material flow, and when available the administrative setting leading up to the time of the accident. Information on the power history, energy release, consequences, and causes are also included when available. For those accidents that occurred in process plants, two new sections have been included in this revision. The first is an analysis and summary of the physical and neutronic features of the chain reacting systems. The second is a compilation of observations and lessons learned. Excursions associated with large power reactors are not included in this report
Agricultural implications of the Fukushima nuclear accident
Nakanishi, Tomoko M.
More than 4 years has passed since the accident at the Fukushima Nuclear Power Plant. Immediately after the accident, 40 to 50 academic staff of the Graduate School of Agricultural and Life Sciences at the University of Tokyo created an independent team to monitor the behavior of the radioactive materials in the field and their effects on agricultural farm lands, forests, rivers, animals, etc. When the radioactive nuclides from the nuclear power plant fell, they were instantly adsorbed at the site where they first touched; consequently, the fallout was found as scattered spots on the surface of anything that was exposed to the air at the time of the accident. The adsorption has become stronger over time, so the radioactive nuclides are now difficult to remove. The findings of our study regarding the wide range of effects on agricultural fields are summarized in this report. PMID:27538845
Radiological consequences of the Chernobyl reactor accident
International Nuclear Information System (INIS)
The reactor accident at unit 4 of the Chernobyl nuclear power plant in Ukraine has deeply affected the living conditions of millions of people. Especially the health consequences have been of public concern up to the present and also been the subject of sometimes absurd claims. The current knowledge on the radiological consequences of the accident is reviewed. Though an increased hazard for some risk groups with high radiation exposure, e.g., liquidators, still cannot be totally excluded for the future, the majority of the population shows no statistically significant indication of radiation-induced illnesses. The contribution of the Research Center Juelich to the assessment of the post-accidental situation and psychological relief of the population is reported. The population groups still requiring special attention include, in particular, children growing up in highly contaminated regions and the liquidators of the years 1986 and 1987 deployed immediately after the accident. (author)
Assessment of CRBR core disruptive accident energetics
International Nuclear Information System (INIS)
The results of an independent assessment of core disruptive accident energetics for the Clinch River Breeder Reactor are presented in this document. This assessment was performed for the Nuclear Regulatory Commission under the direction of the CRBR Program Office within the Office of Nuclear Reactor Regulation. It considered in detail the accident behavior for three accident initiators that are representative of three different classes of events; unprotected loss of flow, unprotected reactivity insertion, and protected loss of heat sink. The primary system's energetics accommodation capability was realistically, yet conservatively, determined in terms of core events. This accommodation capability was found to be equivalent to an isentropic work potential for expansion to one atmosphere of 2550 MJ or a ramp rate of about 200 $/s applied to a classical two-phase disassembly
Bundled automobile insurance coverage and accidents.
Li, Chu-Shiu; Liu, Chwen-Chi; Peng, Sheng-Chang
This paper investigates the characteristics of automobile accidents by taking into account two types of automobile insurance coverage: comprehensive vehicle physical damage insurance and voluntary third-party liability insurance. By using a unique data set in the Taiwanese automobile insurance market, we explore the bundled automobile insurance coverage and the occurrence of claims. It is shown that vehicle physical damage insurance is the major automobile coverage and affects the decision to purchase voluntary liability insurance coverage as a complement. Moreover, policyholders with high vehicle physical damage insurance coverage have a significantly higher probability of filing vehicle damage claims, and if they additionally purchase low voluntary liability insurance coverage, their accident claims probability is higher than those who purchase high voluntary liability insurance coverage. Our empirical results reveal that additional automobile insurance coverage information can capture more driver characteristics and driving behaviors to provide useful information for insurers' underwriting policies and to help analyze the occurrence of automobile accidents.
Assessment of CRBR core disruptive accident energetics
Energy Technology Data Exchange (ETDEWEB)
Theofanous, T.G.; Bell, C.R.
The results of an independent assessment of core disruptive accident energetics for the Clinch River Breeder Reactor are presented in this document. This assessment was performed for the Nuclear Regulatory Commission under the direction of the CRBR Program Office within the Office of Nuclear Reactor Regulation. It considered in detail the accident behavior for three accident initiators that are representative of three different classes of events; unprotected loss of flow, unprotected reactivity insertion, and protected loss of heat sink. The primary system's energetics accommodation capability was realistically, yet conservatively, determined in terms of core events. This accommodation capability was found to be equivalent to an isentropic work potential for expansion to one atmosphere of 2550 MJ or a ramp rate of about 200 $/s applied to a classical two-phase disassembly.
Internal Accident Report: fill it out!
It is important to report all accidents, near-misses and dangerous situations so that they can be avoided in the future. Reporting these events allows the relevant services to take appropriate action and implement corrective and preventive measures. It should be noted that the routing of the internal accident report was recently changed to make sure that the people who need to know are informed. Without information, corrective action is not possible. Without corrective action, there is a risk that the events will recur. As soon as you experience or see something amiss, fill out an internal accident report! If you have any questions the HSE Unit will be happy to answer them. Contact us at email@example.com. The HSE Unit
A Review of Criticality Accidents 2000 Revision
Energy Technology Data Exchange (ETDEWEB)
Thomas P. McLaughlin; Shean P. Monahan; Norman L. Pruvost; Vladimir V. Frolov; Boris G. Ryazanov; Victor I. Sviridov
Criticality accidents and the characteristics of prompt power excursions are discussed. Sixty accidental power excursions are reviewed. Sufficient detail is provided to enable the reader to understand the physical situation, the chemistry and material flow, and when available the administrative setting leading up to the time of the accident. Information on the power history, energy release, consequences, and causes are also included when available. For those accidents that occurred in process plants, two new sections have been included in this revision. The first is an analysis and summary of the physical and neutronic features of the chain reacting systems. The second is a compilation of observations and lessons learned. Excursions associated with large power reactors are not included in this report.
Reconfigurable mobile manipulation for accident response
Energy Technology Data Exchange (ETDEWEB)
The need for a telerobotic vehicle with hazard sensing and integral manipulation capabilities has been identified for use in transportation accidents where nuclear weapons are involved. The Accident Response Mobile Manipulation System (ARMMS) platform has been developed to provide remote dexterous manipulation and hazard sensing for the Accident Response Group (ARG) at Sandia National Laboratories. The ARMMS' mobility platform is a military HMMWV [High Mobility Multipurpose Wheeled Vehicle] that is teleoperated over RF or Fiber Optic communication channels. ARMMS is equipped with two high strength Schilling Titan II manipulators and a suite of hazardous gas and radiation sensors. Recently, a modular telerobotic control architecture call SMART (Sandia Modular Architecture for Robotic and Teleoperation) has been applied to ARMMS. SMART enables input devices and many system behaviors to be rapidly configured in the field for specific mission needs. This paper summarizes current SMART developments applied to ARMMS.
Mathematical models for steam generator accident simulation
International Nuclear Information System (INIS)
In this contribution, the numerical methods used in the DeBeNe-LMFBR development for the analysis of the hydrodynamic and mechanical consequences of steam generator accidents are presented. At first the definition of the source term, i.e. the water leak rate which has to be assumed in the design basis accident as well as the thermochemistry of the sodium/water-reaction is discussed. Then the computer-codes presently used to describe the hydrodynamic and mechanical consequences of steam generator accidents on the basis of the above mentioned source term are presented. These comprise the code-system SAPHYR and the code PTANER and PISCES. Furthermore, developments which are planned or already under way for future use, such as the BEREPOT-code, are presented. (author)
0-Accidents in Offshore Oil and Gas Production - the Quantitative part
Jensen, Olaf Chresten
According to data from the national authorities and operators, the injury incidence rates of lost time accidents in Danish oil and gas operators have declined significantly over the recent decades. There have been significant annual variations, but the trend points towards a zero-injury level, and this is probably due to the safety programmes applied by the industry. An analysis of the data and methods used by the authorities in five countries shows comparable trends, but incomparable risk le...
Sarnet lecture notes on nuclear reactor severe accident phenomenology
International Nuclear Information System (INIS)
The 'Severe Accident Phenomenology Short Course' is part of the Excellence Spreading activities of the European Severe Accident Research NETwork of Excellence SARNET (project of the EURATOM 6. Framework programme). It was held at Cadarache, 9-13 January 2006. The course was divided in 14 lectures covering all aspects of severe accident phenomena that occur during a scenario. It also included lectures on PSA-2, Safety Assessment and design measures in new LWR plants for severe accident mitigation (SAM). This book presents the lecture notes of the Severe Accident Phenomenology Short Course and condenses the essential knowledge on severe accident phenomenology in 2008. (authors)
MDCT findings in sports and recreational accidents
International Nuclear Information System (INIS)
Background. Sports and recreational accidents involving critical areas of the body occur commonly in the general population. Reports on their demographics and recommendations for screening procedures are, however, few. Purpose. To assess injuries of the craniofacial area, spine, and torso resulting from sports and recreational accidents with multidetector computed tomography (MDCT) as primary imaging method in a Level I trauma center. Material and Methods. All emergency room CT requests over a time span of 105 months were reviewed retrospectively for trauma mechanism and injury. Patients were identified using an electronic picture archiving and communications system (PACS), and MDCT studies interpreted by two radiologists independently. Results. Of a total of 5898 patients, 492 patients (301 boys/men, 191 girls/women, age range 2-76 years, mean 33.5 years, median 29.5 years) with sports or recreational accidents emerged. A total of 102 traumatic findings were diagnosed, thereof 72 (71%) serious. The three most commonly encountered serious injuries were intracranial injury, fractures of facial bones, and vertebral injuries. The three most common injury mechanisms were bicycling, horseback riding, and team ball sports. Patients from recreational activities were on average significantly younger (29.2 years) than those from sports accidents (36.9 years; P < 0.001). Only age groups <21 years and 41-50 years differed in injury severity from the other age groups (P = 0.004 and P = 0.063, respectively). Of all trauma mechanisms, only bicycling had a significantly increased risk of injury (P < 0.001). Conclusion. Injuries in sports and recreational accidents presented with an overall incidence of 21%, of which 71% are serious. The most common mechanisms of injury were bicycling, horseback riding, and team ball sports. The largest incidence of serious injury involved bicycling. Because of the high probability of a serious injury and the high energies that are often involved
MDCT findings in sports and recreational accidents
Energy Technology Data Exchange (ETDEWEB)
Bensch, Frank V; Koivikko, Mika P; Koskinen, Seppo K (Dept. of Radiology, Toeoeloe Hospital, Helsinki (Finland)), email: firstname.lastname@example.com
Background. Sports and recreational accidents involving critical areas of the body occur commonly in the general population. Reports on their demographics and recommendations for screening procedures are, however, few. Purpose. To assess injuries of the craniofacial area, spine, and torso resulting from sports and recreational accidents with multidetector computed tomography (MDCT) as primary imaging method in a Level I trauma center. Material and Methods. All emergency room CT requests over a time span of 105 months were reviewed retrospectively for trauma mechanism and injury. Patients were identified using an electronic picture archiving and communications system (PACS), and MDCT studies interpreted by two radiologists independently. Results. Of a total of 5898 patients, 492 patients (301 boys/men, 191 girls/women, age range 2-76 years, mean 33.5 years, median 29.5 years) with sports or recreational accidents emerged. A total of 102 traumatic findings were diagnosed, thereof 72 (71%) serious. The three most commonly encountered serious injuries were intracranial injury, fractures of facial bones, and vertebral injuries. The three most common injury mechanisms were bicycling, horseback riding, and team ball sports. Patients from recreational activities were on average significantly younger (29.2 years) than those from sports accidents (36.9 years; P < 0.001). Only age groups <21 years and 41-50 years differed in injury severity from the other age groups (P = 0.004 and P = 0.063, respectively). Of all trauma mechanisms, only bicycling had a significantly increased risk of injury (P < 0.001). Conclusion. Injuries in sports and recreational accidents presented with an overall incidence of 21%, of which 71% are serious. The most common mechanisms of injury were bicycling, horseback riding, and team ball sports. The largest incidence of serious injury involved bicycling. Because of the high probability of a serious injury and the high energies that are often involved
Accident progression event tree analysis for postulated severe accidents at N Reactor
International Nuclear Information System (INIS)
A Level II/III probabilistic risk assessment (PRA) has been performed for N Reactor, a Department of Energy (DOE) production reactor located on the Hanford reservation in Washington. The accident progression analysis documented in this report determines how core damage accidents identified in the Level I PRA progress from fuel damage to confinement response and potential releases the environment. The objectives of the study are to generate accident progression data for the Level II/III PRA source term model and to identify changes that could improve plant response under accident conditions. The scope of the analysis is comprehensive, excluding only sabotage and operator errors of commission. State-of-the-art methodology is employed based largely on the methods developed by Sandia for the US Nuclear Regulatory Commission in support of the NUREG-1150 study. The accident progression model allows complex interactions and dependencies between systems to be explicitly considered. Latin Hypecube sampling was used to assess the phenomenological and systemic uncertainties associated with the primary and confinement system responses to the core damage accident. The results of the analysis show that the N Reactor confinement concept provides significant radiological protection for most of the accident progression pathways studied
Accident Safety Design for High Speed Elevator
Directory of Open Access Journals (Sweden)
Tawiwat Veeraklaew
Full Text Available There have been many elevators exist in buildings for such a long time; however, an accident might happen as a free fall due to lacks of maintenance or some other accident such as firing. Although this situation is rarely occurred, many people are still concerned about it. The question here is how to make passengers to feel safe and confident when they are using an elevator, especially, high speed elevator. This problem is studied here in this paper as a free fall spring-mass-damper system with the stiffness and damping coefficient can be computed as minimum jerk of the system with given constraints on trajectories.
Medical aspects of the Chernobyl accident
International Nuclear Information System (INIS)
From 11 to 13 May 1988, the All-Union Scientific Centre of Radiation Medicine convened a Conference on Medical Aspects of the Chernobyl Accident in Kiev. This was the first conference on this subject with international participation held in the Soviet Union. There were 310 specialists representing Soviet scientific establishments and over 60 experts from 23 other countries and international organizations participated in the Conference. Participants at the Conference discussed medical aspects of accident mitigation, including therapeutic, psychological, demographic, epidemiological and dosimetric problems. These proceedings include 29 reports presented by Soviet scientists during the four sessions as well as summaries of discussions and opening addresses. Refs, figs and tabs
The Chernobyl nuclear accident and its consequences
International Nuclear Information System (INIS)
An AAEC Task Group was set up shortly after the accident at the Chernobyl Nuclear Power Plant to monitor and evaluate initial reports and to assess the implications for Australia. The Task Group issued a preliminary report on 9 May 1986. On 25-29 August 1986, the USSR released details of the accident and its consequences and further information has become available from the Nuclear Energy Agency of OECD and the World Health Organisation. The Task Group now presents a revised report summarising this information and commenting on the consequences from the Australian viewpoint
Development of preliminary Nevada transportation accident characteristics
International Nuclear Information System (INIS)
The US DOE, Yucca Mountain Site Characterization Project Office (YMSCPO) has been given the responsibility for characterization of the potential repository site at Yucca Mountain, Nevada, and the analysis of repository-related impacts in the State of Nevada. In support of these responsibilities, the YMSCPO initiated a preliminary study to develop background information on the character of the transportation accidents occurring on the highways and raillines in the State of Nevada. The results of this preliminary study shows that while the transportation accidents in Nevada follow national trends, there are some distinct differences between Nevada and the rest of the Nation. This paper summarizes those results
Accident prevention in SME using ORM
DEFF Research Database (Denmark)
Jørgensen, Kirsten; Duijm, Nijs Jan; Troen, Hanne
Risk perception in SMEs is normally low, and this is closely related to the fact that the chance of a mall enterprise experiencing a serious accident is very small compared to companies that employ a large workforce. This is a fact even though the SMEs together have a higher accident frequency...... compared with large enterprises. To reach the SMEs we must find a way of supporting them, because they normally have neither the time nor the resources to acquire the knowledge and awareness necessary for working with their own safety. The Occupational Risk Model (ORM) developed by the Dutch Workgroup...
Re-visiting the Piper Alpha accident
Dykesteen, Mette Kahrs
The main objective of this thesis has been to re-visit the Piper Alpha accident using the latest version of the FLACS simulation code. In 1988/89 simulations of the gas explosion in the C Module of Piper Alpha were performed by Jan Roar Bakke and Idar Storvik at Christian Michelsen Institute, in conjunction with the investigation after the accident. For these simulations the computer code FLACS was used [1, 2]. In this thesis, the same simulation cases have been looked into, and the results o...
Energy Technology Data Exchange (ETDEWEB)
Woods, Michael; /SLAC
A graduate student received a laser eye injury from a femtosecond Ti:sapphire laser beam while adjusting a polarizing beam splitter optic. The direct causes for the accident included failure to follow safe alignment practices and failure to wear the required laser eyewear protection. Underlying root causes included inadequate on-the-job training and supervision, inadequate adherence to requirements, and inadequate appreciation for dimly visible beams outside the range of 400-700nm. This paper describes how the accident occurred, discusses causes and lessons learned, and describes corrective actions being taken.
The medical investigation of airship accidents.
Stahl, C J; McMeekin, R R; Ruehle, C J; Canik, J J
A review of the autopsy reports for 18 of 21 victims in 3 of the 4 nonrigid Navy airship accidents during the period 1955 to 1966 revealed that the patterns of injury, complicated by postcrash entrapment, immersion, or fire, are similar to the injuries observed in the low-speed, low-altitude crashes of rigid airships and of light aircraft. With the renewed interest in the development of airships for military purposes, there is a need for improved design related to crashworthiness and to aircrew habitability, safety, restraint, and egress in order to enhance the chance for survival in the event of an accident. PMID:3171506
Industrial Chain: Industrial Vertical Definition
Institute of Scientific and Technical Information of China (English)
YifeiDu; GuojunJiang; ShimingLi
Like value chain and supply chain, "industrial chain" becomes the focus of attention. The implication of "industrial chain" has gained a large range of extension. It not only expresses the industrial "chain" structure and relationship of "back and forward"in order or "up and down" in direction, but also it represents a cluster of large scale of firms in an area or colony. It is a network, or a community. Consequently, we conclude that "industrial chain" is a synthesis of industrial chain, industrial cluster, or industrial network.In this article, firstly we will distinguish industry chain from industry. An industry is the collection of firms that have the same attribute, so an industry can be defined by firm collection of certain attribute. We indicate that industrial chain is a kind of vertical and orderly industrial link. It is defined according to a series of specific product or service created. Secondly we analyze the vertical orderly defiinition process from the aspects of social division of labor and requirement division, self-organization system, and value analysis.Non-symmetry and depending on system or community of large scale of industrial units lead to entire industry to "orderly" structure. On the other hand, the draught of diversity and complexity of requirement simultaneously lead to entire industry to be more "orderly". Along with processes of self-organization, industrial will appi'oach the state of more orderly and steady, and constantly make industrial chain upgrade. Each firm or unit, who will gain the value, has to establish channels of value, which we called "industrial value chain". Lastly,we discuss the consequence of vertical and orderly definition, which is exhibited by a certain relationship body. The typical forms of industrial chain include industrial cluster, strategy alliance and vertical integration etc.
Serie temporal de los accidentes laborales atendidos en un hospital de agudos y su relación con la meteorología y la polución atmosférica Time series of industrial accidents attended in an acute hospital care and its relation to meteorology and atmospheric pollution
Directory of Open Access Journals (Sweden)
Brígido Pérez Bermúdez
Full Text Available Introducción: La siniestralidad es un proceso en muchas ocasiones complejo en el que entran diversos factores de riesgo, tanto inherentes al trabajo como a circunstancias exteriores (organización, climatología, etc.. Objetivos: Describir la tendencia y factores relacionados de los accidentes de trabajo (A.T. atendidos en un hospital de agudos de Madrid durante el trienio 2005-07 y su relación con la meteorología y la polución atmosférica. Metodología: Estudio ecológico. Se analizaron los A.T. atendidos en el Servicio de Urgencias del Hospital Universitario de la Princesa de Madrid, durante el trienio 2005-07. Las variables analizadas fueron variables de calendario, climáticas y niveles de contaminación. Se realizó un estudio descriptivo y univariante y se modelizó por medio de una Regresión de Poisson. La medida de asociación fue el Riesgo Relativo con sus Intervalos de Confianza al 95 %. Resultados: La tendencia es estacionaria disminuyendo en el año 2007. El calor es un factor de riesgo, temperaturas superiores a 25 º C. aumenta la siniestralidad un 19 %. La presión atmosférica se comporta como efecto protector. Las variables de contaminación no fueron significativas. Conclusiones: Durante el año 2007, la siniestralidad laboral atendida en el servicio de Urgencias del hospital ha disminuido. Los A.T. tienen una relación con temperaturas elevadas y presión atmosférica.Introduccion: The work accident rate is in several occasions a complex process in wich divers safety factors take place, inherente to the job /profesión as well as external circumstances (organization, climatology, etc Objectives: To describe the tendency and factors wich are linked to the occupational Hazard, admitted toa cute hospital in Madrid during the 2005-2007 triennium and its relations with meteorology and environmental pollution. Methodology: Ecologic study. Occupational injuries admitted in the accident and emergency department at the University
Metrics for the evaluation of light water reactor accident tolerant fuel
International Nuclear Information System (INIS)
The safe, reliable and economic operation of the nation's nuclear power reactor fleet has always been a top priority for the nuclear industry. Continual improvement of technology, including advanced materials and nuclear fuels, remains central to the industry's success. Enhancing the accident tolerance of LWRs became a topic of serious discussion following the 2011 Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex. The overall goal of accident tolerant fuel (ATF) development is to identify alternative fuel system technologies to further enhance the safety, competitiveness, and economics of commercial nuclear power. The complex multiphysics behavior of LWR nuclear fuel in the integrated reactor system makes defining specific material or design improvements difficult; as such, establishing desirable performance attributes is critical in guiding the design and development of fuels and cladding with enhanced accident tolerance. The U.S. Department of Energy is sponsoring multiple teams to develop ATF concepts within multiple national laboratories, universities, and the nuclear industry. Concepts under investigation offer both evolutionary and revolutionary changes to the current nuclear fuel system. This paper summarizes technical evaluation methodology proposed in the U.S. to aid in the optimization and down-selection of candidate ATF designs. This methodology will continue to be refined via input from the research community and industry, such that it is available to support the planned down-selection of ATF concepts in 2016. (author)
Disaster Evacuation from Japan's 2011 Tsunami Disaster and the Fukushima Nuclear Accident
International Nuclear Information System (INIS)
The triple disaster that hit the Tohoku region of Japan on 11 March 2011 triggered a massive human displacement: more than 400,000 people evacuated their homes as a gigantic tsunami induced by a magnitude 9.0 earthquake engulfed the coastal areas, and the following nuclear accident in Fukushima released a large amount of radioactive materials into the atmosphere. This study analyses the disaster response, with a particular focus on evacuation of the population, and social consequences of this complex crisis, based on intensive fieldwork carried out one year after the catastrophe. It reveals that the responses of the Japanese authorities and population were significantly different between a natural disaster and an industrial (man-made) accident. Being prone to both earthquakes and tsunamis, Japan had been preparing itself against such risks for many years. A tsunami alert was immediately issued and the population knew how and where to evacuate. In contrast, the evacuation from the nuclear accident was organised in total chaos, as a severe accident or large-scale evacuation had never been envisaged -let alone exercised- before the disaster. The population was thus forced to flee with no information as to the gravity of the accident or radiation risk. In both cases, the risk perception prior to the catastrophe played a key role in determining the vulnerability of the population at the time of the crisis. While tsunami evacuees are struggling with a slow reconstruction process due to financial difficulties, nuclear evacuees are suffering from uncertainty as to their prospect of return. One year after the accident, the Japanese authorities began to encourage nuclear evacuees to return to the areas contaminated by radiation according to a newly established safety standard. This triggered a vivid controversy within the affected communities, creating a rift between those who trust the government's notion of safety and those who do not. The nuclear disaster has thus

subset: commoncrawl