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Bomb-Pulse Chlorine-36 at the Proposed Yucca Mountain Repository Horizon: An Investigation of Previous Conflicting Results and Collection of New Data
Science Conference Proceedings (OSTI)
Previous studies Los Alamos National Laboratory (LANL) found elevated ratios of chlorine-36 to total chloride (36Cl/Cl) in samples of rock collected from the Exploratory Studies Facility (ESF) at Yucca Mountain (YM). The data were interpreted as an indication that fluids containing �bomb-pulse� 36Cl reached the repository horizon in the ~50 years since the peak period of above-ground nuclear testing. Due to the significance of 36Cl data to conceptual models of unsaturated zone flow, the United States Geological Survey (USGS) implemented a study to validate the LANL findings. The USGS drilled new boreholes at select locations across zones where bomb-pulse ratios had previously been identified. The drill cores were analyzed at Lawrence Livermore National Laboratory (LLNL). Because consensus was not reached between the USGS/LLNL and LANL on several fundamental points including the presence or absence of bomb-pulse 36Cl, an evaluation by the University of Nevada, Las Vegas (UNLV), was initiated. The overall objectives of the UNLV study were to investigate the source of the validation study�s conflicting results, and to obtain additional data on bomb-pulse isotopes at the repository horizon. UNLV engaged in discussions with previous investigators, reviewed reports, and analyzed archived samples. UNLV also collected new samples of rock from the ESF, soil profiles from the surface of YM, and samples of seep water from inside the ESF. Samples were analyzed for 36Cl/Cl ratios, and 99Tc and 129I in select samples. A column experiment was conducted mimicking the passage of bomb-pulse 36Cl through YM tuff. The work faced several obstacles including an extended shutdown of the tunnel. Only one sample yielded a background corrected 36Cl/Cl ratio that was higher than the accepted bomb-pulse threshold (1250 x 10-15). Specimen 01034214 obtained from the Drill Hole Wash fault (19+33) had a ratio of 1590 � 80 (1?) x10-15, whereas the other separate sample from this fault zone yielded 1160 � 50 (1?) x 10-15. Three samples collected from Alcove 6 averaged 490 � 100 (1?) x10-15; a sample from Sundance Fault resulted in a ratio of 920 � 60 (1?) x10-15, and a sample from the Bow Ridge Fault produced 530 � 20 (1?) x10-15. The results are significant because: 1) they tend to be lower than LANL data for comparable samples, albeit in agreement with the range of data produced in the area, and 2) they show that a bomb-pulse 36Cl/Cl ratio was measured in rock collected at the repository horizon level by a second and independent group of investigators (UNLV). Because of time UNLV was not able to replicate the results, and these few data points are insufficient to draw major and definitive conclusions. Leachates of soil samples collected from the surface above the ESF yielded several ratios with bomb-pulse 36Cl, particularly for samples encompassing the wetting front. Soil samples collected above the south ramp, where there was limited soil coverage due to a large amount of rock outcrop, had relatively large ratios ranging from 2170 � 110 (1?) x10-15 to 5670 � 350 (1?) x10-15. Soil samples from profiles from above the north ramp ranged from 820 � 70 (1?) x10-15 to 2390 � 160 (1?) x10-15, which compare favorably with previous measurements near the site. Water seepage into the ESF south ramp and 36Cl standards made from NIST material were also analyzed. The standards were produced to have nominal 36Cl/Cl ratios (10-15) of 500, 2,500 and 10,000 and the results showed good agreement with the calculated ratios. The seepage samples ranged between 680 � 40 (1?) x10-15 to 1110 � 40 (1?) x10-15, consistent with that found for modern meteoric water, with a small bomb-pulse component. Bomb-pulse 36Cl may not have been incorporated in this fast-path water because the surface above the infiltration zone consists mostly of outcrop and the flow pathways have probably mostly been leached. 99Tc was measured in five of nine leaches of ESF rock but poor analytical recoveries and lack of data overlap with 36Cl limit interpretations of these data
Cizdziel, James
Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and
E-Print Network (OSTI)
conditions [EN 12-457, TCLP], carbonated and not carbonated, at 90 days. In this paper, the leaching test they exist (for instance TCLP limits, quality of water, and waste acceptance criteria for landfill reduced the toxicity of both mortar leachates since the concentrations below 12.5% led to an absence
Mailhes, Corinne
Disaster and Failure Studies Repository
... Phase 2 will include a pilot repository of data collected from the 2010 Chile earthquake. This is scheduled to be completed in late 2012. ...
Gross Alpha and Gross Beta Measurements in Coal Combustion Product Leachate
The objective of this report was to provide information to help interpret gross alpha and gross beta concentrations in coal combustion product (CCP) leachate. This objective was accomplished by chemically characterizing 15 field leachate samples that were collected at three CCP management facilities. The leachate samples were analyzed for gross alpha and gross beta concentrations and for the potential individual alpha and beta emitters in solution. Gross alpha concentrations at the three sites ranged fro...
Information Repository
NLE Websites -- All DOE Office Websites (Extended Search)
Information Repository Index Permit Renewal Application (Parts A and B) Submissions, September 2009, Department of Energy CBFOWashington TRU Solutions Administrative Completeness...
Bomb-Pulse Chlorine-36 At The Proposed Yucca Mountain Repository Horizon: An Investigation Of Previous Conflicting Results And Collection Of New Data
Previous studies by scientists at Los Alamos National Laboratory (LANL) found elevated ratios of chlorine-36 to total chloride ({sup 36}Cl/Cl) in samples of rock collected from the Exploratory Studies Facility (ESF) and the Enhanced Characterization of the Repository Block (ECRB) at Yucca Mountain as the tunnels were excavated. The data were interpreted as an indication that fluids containing 'bomb-pulse' {sup 36}Cl reached the repository horizon in the {approx}50 years since the peak period of above-ground nuclear testing. Moreover, the data support the concept that so-called fast pathways for infiltration not only exist but are active, possibly through a combination of porous media, faults and/or other geologic features. Due to the significance of {sup 36}Cl data to conceptual models of unsaturated zone flow and transport, the United States Geological Survey (USGS) was requested by the Department of Energy (DOE) to design and implement a study to validate the LANL findings. The USGS chose to drill new boreholes at select locations across zones where bomb-pulse ratios had previously been identified. The drill cores were analyzed at Lawrence Livermore National Laboratory (LLNL) for {sup 36}Cl/Cl using both active and passive leaches, with the USGS/LLNL concluding that the active leach extracted too much rock-Cl and the passive leach did not show bomb-pulse ratios. Because consensus was not reached between the USGS/LLNL and LANL on several fundamental points, including the conceptual strategy for sampling, interpretation and use of tritium ({sup 3}H) data, and the importance and interpretation of blanks, in addition to the presence or absence of bomb-pulse {sup 36}Cl, an evaluation by an independent entity, the University of Nevada, Las Vegas (UNLV), using new samples was initiated. This report is the result of that study. The overall objectives of the UNLV study were to investigate the source or sources of the conflicting results from the previous validation study, and to obtain additional data to determine whether or not there are bomb-pulse isotopes at the repository horizon. To that en4 we have engaged in discussions with previous investigators, reviewed reports, and analyzed archived samples. We have also collected new samples of rock from the ESF, soil profiles from the surface of Yucca Mountain, and opportunistic samples of seep water from inside the south ramp of the ESF.
J. Cizdziel
WSDOT Test Method T 127 Preparation of Leachate Sample for Testing Toxicity of HECP Effluents 1. Scope This test method outlines the procedure for collecting leachate from a HECP sample. 2. References 2.1 EPA-821-R-02-012 Methods for Measuring Acute Toxic
3.1 Lay cheesecloth over clean topsoil 3.2 Apply the HECP to the cheesecloth at the following coverage: 3.2.1 HECP Long-Term or Moderate-Term Mulch 3,500 lbs per acre in two lifts with no more than 2000 # per acre in any one lift. 3.2.2 HECP Short-Term Mulch 2000 # per acre minimum, or manufacturer�s recommended rate may be used. 3.3 Allow material to cure for 48 hours 3.4 Pull cheesecloth up with mat of HECP, brush off any soil 3.5 Cut HECP into squares and provide 1.02 pounds of HECP to the laboratory. 4. Preparation of the Leachate (done by the laboratory) 4.1 Allow hydromulch product to soak in water for one hour 4.2 Remove hydromulch sheet from water 4.3 Filter water through a 60 micron filter � water may be pre-filtered through a 35 mesh and then a 120 mesh before using the 230 mesh/63 micron filter. Note: Leachate not immediately used for testing should be stored at 4 � C in the dark until
unknown authors
3 Information Repository Documents 3 Information Repository Documents WIPP Annual Waste Minimization Report Transmittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report, dated November 14, 2013 Class 1 Permit Modifications and NMED Responses Class 1 Modification, August 29, 2013 WIPP Hazardous Waste Facility Permit EPA I.D. Number NM4890139088. (1. revise a course outline; 2. revise table and panel figures to include Panel 7; 3. update description related to Type B Packages; and 4. update TRUPACT-II and HalfPACT figures) JE Kieling, NMED dated October 13, 2013 Fee Assessment Class 1 Permit Modification WIPP Hazardous Waste Facility Permit EPA I.D. Number NM4890139088-TSDF (Revise a Course Outline; Revise Table and Panel Figures to Include Panel 7; Update Descriptions Related to Type B Packages; and Update TRUPACT-ll and HalfPACT Figures) JM Kieling, NMED dated September 23, 2013
DFT repositories and informatics
... includes: Establishing best practices for future and current practitioners,; Developing data-sharing tools and repositories,; ...
Repository performance confirmation.
SciTech Connect
Repository performance confirmation links the technical bases of repository science and societal acceptance. This paper explores the myriad aspects of what has been labeled performance confirmation in U.S. programs, which involves monitoring as a collection of distinct activities combining technical and social significance in radioactive waste management. This paper is divided into four parts: (1) A distinction is drawn between performance confirmation monitoring and other testing and monitoring objectives; (2) A case study illustrates confirmation activities integrated within a long-term testing and monitoring strategy for Yucca Mountain; (3) A case study reviews compliance monitoring developed and implemented for the Waste Isolation Pilot Plant; and (4) An approach for developing, evaluating and implementing the next generation of performance confirmation monitoring is presented. International interest in repository monitoring is exhibited by the European Commission Seventh Framework Programme 'Monitoring Developments for Safe Repository Operation and Staged Closure' (MoDeRn) Project. The MoDeRn partners are considering the role of monitoring in a phased approach to the geological disposal of radioactive waste. As repository plans advance in different countries, the need to consider monitoring strategies within a controlled framework has become more apparent. The MoDeRn project pulls together technical and societal experts to assimilate a common understanding of a process that could be followed to develop a monitoring program. A fundamental consideration is the differentiation of confirmation monitoring from the many other testing and monitoring activities. Recently, the license application for Yucca Mountain provided a case study including a technical process for meeting regulatory requirements to confirm repository performance as well as considerations related to the preservation of retrievability. The performance confirmation plan developed as part of the Yucca Mountain license application identified a broad suite of monitoring activities. A revision of the plan was expected to winnow the number of activities down to a manageable size. As a result, an objective process for the next stage of performance confirmation planning was developed as an integral part of an overarching long-term testing and monitoring strategy. The Waste Isolation Pilot Plant compliance monitoring program at once reflects its importance to stakeholders while demonstrating adequate understanding of relevant monitoring parameters. The compliance criteria were stated by regulation and are currently monitored as part of the regulatory rule for disposal. At the outset, the screening practice and parameter selection were not predicated on a direct or indirect correlation to system performance metrics, as was the case for Yucca Mountain. Later on, correlation to performance was established, and the Waste Isolation Pilot Plant continues to monitor ten parameters originally identified in the compliance certification documentation. The monitoring program has proven to be effective for the technical intentions and societal or public assurance. The experience with performance confirmation in the license application process for Yucca Mountain helped identify an objective, quantitative methodology for this purpose. Revision of the existing plan would be based on findings of the total system performance assessment. Identification and prioritization of confirmation activities would then derive from performance metrics associated with performance assessment. Given the understanding of repository performance confirmation, as reviewed in this paper, it is evident that the performance confirmation program for the Yucca Mountain project could be readily re-engaged if licensing activities resumed.
Hansen, Francis D.
Suggests lattice ZipData No Repository CRAN
Description A collection of artificial and real-world machine learning benchmark problems, including, e.g., several data sets from the UCI repository.
Friedrich Leisch; Evgenia Dimitriadou; Maintainer Friedrich Leisch
Environmental Impacts of Repository
Energy.gov (U.S. Department of Energy (DOE)) Indexed Site
~~"'"""""""""'l.. _ _ 4 Environmental Impacts of Repository Construction, Operation and Monitoring, and Closure 4-iii Environmental Impacts of Repository Construction, Operations, Monitoring, and Closure TABLE OF CONTENTS Section Page 4. Environmental Impacts of Repository Construction, Operations, Monitoring, and Closure ..............4-1 4.1 Preclosure Environmental Impacts of Construction, Operations, Monitoring, and Closure of a Repository ...............................................................................................................................4-3 4.1.1 Impacts to Land Use and Ownership .......................................................................................4-4
Using tire chips as a leachate drainage layer
Old tires represent a potentially cost-effective construction material that can be used in the installation of leachate drainage and collection systems. In fact, recent studies show that using shredded tires in conjunction with granular soil materials can even enhance the long-term performance of these systems. A typical design using shredded tire chips involves the placement of a minimum 1-foot-thick layer of chips on a granular soil layer overlaying the composite liner system. However, implementation of this design is not as simple as it looks. Protecting the liner from wire protruding from the tire chips derived from belted tires is essential. Because tire chips tend to clump together, placement and spreading also must be in relatively thick lifts and performed by low-ground-pressure equipment. In addition, a significant volume reduction in the tire chip layer can be anticipated as a result of normal loadings from the overlying waste. Equivalent internal friction angles and cohesiveness for the tire chips should be estimated for factors of safety against side-slope failure. Despite theses concerns, however,the advantages of constructing a tire-chip drainage layer often can outweigh the disadvantages, as long as the chips` long-term permeability characteristics and resistance to clogging -- a result of biological activity -- are at least equal to that of typical granular soil materials commonly used in leachate drainage and collection systems.
Duffy, D.P. [RMT, Inc., Ann Arbor, MI (United States)
Collection Collection and Analysis of Expressed Sequence Tags Derived from Laser Capture Microdissected Switchgrass (Panicum virgatum L. Alamo) Vascular Tissues Avinash C. Srivastava & Karuppaiah Palanichelvam & Junying Ma & Jarrod Steele & Elison B. Blancaflor & Yuhong Tang # Springer Science+Business Media, LLC. 2010 Abstract Switchgrass is a perennial C4 grass that thrives in a wide range of North American habitats and is an emerging crop for the production of lignocellulosic biofuels. Lignin is an integral component of secondary plant cell walls that provides structural rigidity to the cell wall but it interferes with the conversion of cellulose to fermentable sugars by prevent- ing chemical access to cellulose. Thus, one strategy for improving production of cellulosic ethanol is the down- regulation of lignin in plants. To achieve this goal, it is important
Leachate storage transport tanker loadout piping
This report shows the modifications to the W-025 Trench No. 31 leachate loadout discharge piping, and also the steps involved in installing the discharge piping, including dimensions and welding information. The installation of the discharge pipe should be done in accordance to current pipe installation standards. Trench No. 31 is a radioactive mixed waste land disposal facility.
Whitlock, R.W.
Metal speciation in landfill leachates with a focus on the influence of organic matter
Highlights: > This study characterises the heavy-metal content in leachates collected from eight landfills in France. > Most of the metals are concentrated in the <30 kDa fraction, while Pb, Cu and Cd are associated with larger particles. > Metal complexation with OM is not sufficient to explain apparent supersaturation of metals with sulphide minerals. - Abstract: This study characterises the heavy-metal content in leachates collected from eight landfills in France. In order to identify heavy metal occurrence in the different size fractions of leachates, a cascade filtration protocol was applied directly in the field, under a nitrogen gas atmosphere to avoid metal oxidation. The results of analyses performed on the leachates suggest that most of the metals are concentrated in the <30 kDa fraction, while lead, copper and cadmium show an association with larger particles. Initial speciation calculations, without considering metal association with organic matter, suggest that leachate concentrations in lead, copper, nickel and zinc are super-saturated with respect to sulphur phases. Speciation calculations that account for metal complexation with organic matter, considered as fulvic acids based on C1(s) NEXAFS spectroscopy, show that this mechanism is not sufficient to explain such deviation from equilibrium conditions. It is therefore hypothesized that the deviation results also from the influence of biological activity on the kinetics of mineral phase precipitation and dissolution, thus providing a dynamic system. The results of chemical analyses of sampled fluids are compared with speciation calculations and some implications for the assessment of metal mobility and natural attenuation in a context of landfill risk assessment are discussed.
Claret, Francis, E-mail: firstname.lastname@example.com [BRGM, 3 avenue C. Guillemin, BP 6009, 45060 Orleans (France); Tournassat, Christophe; Crouzet, Catherine; Gaucher, Eric C. [BRGM, 3 avenue C. Guillemin, BP 6009, 45060 Orleans (France); Schaefer, Thorsten [Karlsruhe Institute of Technology (KIT), Institute for Nuclear Waste Disposal (INE), P.O. Box 3640, 76021 Karlsruhe (Germany); Freie Universitaet Berlin, Institute of Geological Sciences, Department of Earth Sciences, Hydrogeology Group, D-12249 Berlin (Germany); Braibant, Gilles; Guyonnet, Dominique [BRGM, 3 avenue C. Guillemin, BP 6009, 45060 Orleans (France)
Metal Speciation in Landfill Leachates with a Focus on the Influence of Organic Matter
This study characterizes the heavy-metal content in leachates collected from eight landfills in France. In order to identify heavy metal occurrence in the different size fractions of leachates, a cascade filtration protocol was applied directly in the field, under a nitrogen gas atmosphere to avoid metal oxidation. The results of analyses performed on the leachates suggest that most of the metals are concentrated in the <30 kDa fraction, while lead, copper and cadmium show an association with larger particles. Initial speciation calculations, without considering metal association with organic matter, suggest that leachate concentrations in lead, copper, nickel and zinc are super-saturated with respect to sulphur phases. Speciation calculations that account for metal complexation with organic matter, considered as fulvic acids based on C1(s) NEXAFS spectroscopy, show that this mechanism is not sufficient to explain such deviation from equilibrium conditions. It is therefore hypothesized that the deviation results also from the influence of biological activity on the kinetics of mineral phase precipitation and dissolution, thus providing a dynamic system. The results of chemical analyses of sampled fluids are compared with speciation calculations and some implications for the assessment of metal mobility and natural attenuation in a context of landfill risk assessment are discussed.
F Claret; C Tournassat; C Crouzet; E Gaucher; T Sch�fer; G Braibant; D Guyonnet
Effect of leachate recirculation on landfill gas production and leachate quality: A controlled laboratory study
This report summarizes the results of a laboratory study conducted during 1992-1994 at Argonne National Laboratory. The study examined biogas production and leachate chemistry in parallel anaerobic assays run under either leachate recycle or leachate drainage regimes over a period of 400 days. A standardized synthetic refuse (paper, grass, food) was used in an experimental design which evaluated two elevated moisture contents and two added soils. All assays were conducted in vitro in 125 mL serum bottles. Four recycle/drainage events were completed during the 400 days of this experiment. Sufficient replicates (10 or 20) for each trial were included in the experimental design to permit destructive sampling of assay solids after each recycle/drainage event. Changes in the chemistry of solid, liquid, and gaseous phases were evaluated during the decomposition process. Analyses included major gases (CH{sub 4}, CO{sub 2}, O{sub 2}, N{sub 2}), selected chemical constituents of leachate (Cl-C5 carboxylic acids, total organic carbon, Kjeldahl nitrogen, total phosphorus, iron, zinc, and chloride), leachate pH and conductivity, and selected solids analysis (gravimetric moisture content, volatile solids, total carbon, cellulose, hemicellulose, and lignin).
Bogner, J.; Spokas, K.
Characterization of Field Leachates at Coal Combustion Product Management Sites
A large amount of laboratory-generated leachate data has been produced over the last two decades to estimatecoal combustion product (CCP) leachate concentrations, and a variety of leaching methods have been used. No one method, however, has been shown to accurately represent field leaching conditions. In fact, little work has been performed to systematically evaluate field-generated leachates representative of a range of coal types, combustion systems, and management methods, and only limited work has be...
Microbial nitrogen transformation potential in surface run-off leachate from a tropical landfill
Highlights: Black-Right-Pointing-Pointer Microbial nitrogen transformations can alleviate toxic ammonium discharge. Black-Right-Pointing-Pointer Aerobic ammonium oxidation was rate-limiting in Indonesian landfill leachate. Black-Right-Pointing-Pointer Organic nitrogen ammonification was most dominant. Black-Right-Pointing-Pointer Anaerobic nitrate reduction and ammonium oxidation potential were also high. Black-Right-Pointing-Pointer A two-stage aerobic-anaerobic nitrogen removal system needs to be implemented. - Abstract: Ammonium is one of the major toxic compounds and a critical long-term pollutant in landfill leachate. Leachate from the Jatibarang landfill in Semarang, Indonesia, contains ammonium in concentrations ranging from 376 to 929 mg N L{sup -1}. The objective of this study was to determine seasonal variation in the potential for organic nitrogen ammonification, aerobic nitrification, anaerobic nitrate reduction and anaerobic ammonium oxidation (anammox) at this landfilling site. Seasonal samples from leachate collection treatment ponds were used as an inoculum to feed synthetic media to determine potential rates of nitrogen transformations. Aerobic ammonium oxidation potential (<0.06 mg N L{sup -1} h{sup -1}) was more than a hundred times lower than the anaerobic nitrogen transformation processes and organic nitrogen ammonification, which were of the same order of magnitude. Anaerobic nitrate oxidation did not proceed beyond nitrite; isolates grown with nitrate as electron acceptor did not degrade nitrite further. Effects of season were only observed for aerobic nitrification and anammox, and were relatively minor: rates were up to three times higher in the dry season. To completely remove the excess ammonium from the leachate, we propose a two-stage treatment system to be implemented. Aeration in the first leachate pond would strongly contribute to aerobic ammonium oxidation to nitrate by providing the currently missing oxygen in the anaerobic leachate and allowing for the growth of ammonium oxidisers. In the second pond the remaining ammonium and produced nitrate can be converted by a combination of nitrate reduction to nitrite and anammox. Such optimization of microbial nitrogen transformations can contribute to alleviating the ammonium discharge to surface water draining the landfill.
Mangimbulude, Jubhar C. [Faculty of Biology, Universitas Kristen Satya Wacana, Jl Diponegoro 52-60, Salatiga 50711 (Indonesia); Straalen, Nico M. van [Department of Ecological Science, Faculty of Earth and Life Sciences, VU University Amsterdam, De Boelelaan 1085, NL-1081 HV, Amsterdam (Netherlands); Roeling, Wilfred F.M., E-mail: email@example.com [Department of Molecular Cell Physiology, Faculty of Earth and Life Sciences, VU University Amsterdam, De Boelelaan 1085, NL-1081 HV, Amsterdam (Netherlands)
Impact of nitrate-enhanced leachate recirculation on gaseous releases from a landfill bioreactor cell
This study evaluates the impact of nitrate injection on a full scale landfill bioreactor through the monitoring of gaseous releases and particularly N{sub 2}O emissions. During several weeks, we monitored gas concentrations in the landfill gas collection system as well as surface gas releases with a series of seven static chambers. These devices were directly connected to a gas chromatograph coupled to a flame ionisation detector and an electron capture detector (GC-FID/ECD) placed directly on the field. Measurements were performed before, during and after recirculation of raw leachate and nitrate-enhanced leachate. Raw leachate recirculation did not have a significant effect on the biogas concentrations (CO{sub 2}, CH{sub 4} and N{sub 2}O) in the gas extraction network. However, nitrate-enhanced leachate recirculation induced a marked increase of the N{sub 2}O concentrations in the gas collected from the recirculation trench (100-fold increase from 0.2 ppm to 23 ppm). In the common gas collection system however, this N{sub 2}O increase was no more detectable because of dilution by gas coming from other cells or ambient air intrusion. Surface releases through the temporary cover were characterized by a large spatial and temporal variability. One automated chamber gave limited standard errors over each experimental period for N{sub 2}O releases: 8.1 {+-} 0.16 mg m{sup -2} d{sup -1} (n = 384), 4.2 {+-} 0.14 mg m{sup -2} d{sup -1} (n = 132) and 1.9 {+-} 0.10 mg m{sup -2} d{sup -1} (n = 49), during, after raw leachate and nitrate-enhanced leachate recirculation, respectively. No clear correlation between N{sub 2}O gaseous surface releases and recirculation events were evidenced. Estimated N{sub 2}O fluxes remained in the lower range of what is reported in the literature for landfill covers, even after nitrate injection.
Tallec, G.; Bureau, C. [Cemagref, UR HBAN, Parc de Tourvoie, BP44, F-92163 Antony (France); Peu, P.; Benoist, J.C. [Cemagref, UR GERE, 17 Avenue de Cucille, CS 64427, F-35044 Rennes (France); Lemunier, M. [Suez-Environnement, CIRADE, 38 Av. Jean Jaures, 78440 Gargenville (France); Budka, A.; Presse, D. [SITA France, 132 Rue des 3 Fontanot, 92000 Nanterre Cedex (France); Bouchez, T. [Cemagref, UR HBAN, Parc de Tourvoie, BP44, F-92163 Antony (France)], E-mail: firstname.lastname@example.com
Supercritical water oxidation of landfill leachate
Highlights: > Thermal analysis of NH{sub 3} in supercritical water oxidation reaction. > Research on the catalytic reaction of landfill leachate by using response surface method. > Kinetic research of supercritical water oxidation of NH{sub 3} with and without MnO{sub 2} catalyst. - Abstract: In this paper, ammonia as an important ingredient in landfill leachate was mainly studied. Based on Peng-Robinson formulations and Gibbs free energy minimization method, the estimation of equilibrium composition and thermodynamic analysis for supercritical water oxidation of ammonia (SCWO) was made. As equilibrium is reached, ammonia could be totally oxidized in SCW. N{sub 2} is the main product, and the formation of NO{sub 2} and NO could be neglected. The investigation on SCWO of landfill leachate was conducted in a batch reactor at temperature of 380-500 deg. C, reaction time of 50-300 s and pressure of 25 MPa. The effect of reaction parameters such as oxidant equivalent ratio, reaction time and temperature were investigated. The results showed that COD and NH{sub 3} conversion improved as temperature, reaction time and oxygen excess increased. Compared to organics, NH{sub 3} is a refractory compound in supercritical water. The conversion of COD and NH{sub 3} were higher in the presence of MnO{sub 2} than that without catalyst. The interaction between reaction temperature and time was analyzed by using response surface method (RSM) and the results showed that its influence on the NH{sub 3} conversion was relatively insignificant in the case without catalyst. A global power-law rate expression was regressed from experimental data to estimate the reaction rate of NH{sub 3}. The activation energy with and without catalyst for NH{sub 3} oxidation were 107.07 {+-} 8.57 kJ/mol and 83.22 {+-} 15.62 kJ/mol, respectively.
Wang Shuzhong, E-mail: firstname.lastname@example.com [School of Energy and Power Engineering of Xi' an Jiao Tong University, Xi'an 710049 (China); Guo Yang [School of Energy and Power Engineering of Xi' an Jiao Tong University, Xi'an 710049 (China); Chen Chongming [Hebei Electric Power Research Institute, Shijizhuang, Hebei 050021 (China); Zhang Jie; Gong Yanmeng; Wang Yuzhen [School of Energy and Power Engineering of Xi' an Jiao Tong University, Xi'an 710049 (China)
Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2009
This document reports the findings of the groundwater and leachate monitoring and sampling at the Environmental restoration Disposal Facility for calendar year 2009. The purpose of this annual monitoring report is to evaluate the conditions of and identify trends for groundwater beneath the ERDF and report leachate results in fulfillment of the requirements specified in the ERDF ROD and the ERDF Amended ROD.
R.L. Weiss, B.L. Lawrence, D.W. Woolery
Repository seals requirements study
The Yucca Mountain Site Characterization Project, managed by the Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M and O) is conducting investigations to support the Viability Assessment and the License Application for a high-level nuclear waste repository at Yucca Mountain, Nevada. The sealing subsystem is part of the Yucca Mountain Waste Isolation System. The Yucca Mountain Site Characterization Project is currently evaluating the role of the sealing subsystem (shaft, ramp and exploratory borehole seals) in achieving the overall performance objectives for the Waste Isolation System. This report documents the results of those evaluations. This report presents the results of a repository sealing requirements study. Sealing is defined as the permanent closure of the shafts, ramps, and exploratory boreholes. Sealing includes those components that would reduce potential inflows above the repository, or that would divert flow near the repository horizon to allow vertical infiltration to below the repository. Sealing of such features as emplacement drifts was not done in this study because the current capability to calculate fracture flow into the drifts is not sufficiently mature. The objective of the study is to provide water or air flow performance based requirements for shafts, ramps, and exploratory boreholes located near the repository. Recommendations, as appropriate, are provided for developing plans, seals component testing, and other studies relating to sealing.
Suggests e1071, scatterplot3d ZipData No Repository CRAN
Friedrich Leisch; Maintainer Friedrich Leisch
Colloidal products and actinide species in leachate from spent nuclear fuel
Two well-characterized types of spent nuclear fuel (ATM-103 and ATM-106) were subjected to unsaturated leach tests with simulated groundwater at 90{degrees}C. The actinides present in the leachate were determined at the end of two successive periods of {approximately}60 days and after an acid strip done at the end of the second period. Both colloidal and soluble actinide species were detected in the leachates which had pHs ranging from 4 to 7. The uranium phases identified in the colloids were schoepite and soddyite. In addition, the actinide release behavior of the two fuels appeared to be different for both the total amount of material released and the relative amount of each isotope released. This paper will focus on the detection and identification of the colloidal species observed in the leachate that was collected after each of the first two successive testing periods of approximately 60 days each. In addition, preliminary values for the total actinide release for these two periods are reported.
Finn, P.A.; Buck, E.C.; Gong, M.; Hoh, J.C.; Emery, J.W.; Hafenrichter, L.D.; Bates, J.K.
Darshan � Updated data repository documentation
Updated data repository documentation June 18th, 2013 The documentation for the public ALCF IO Data Repository has been updated. Please note that there is a new technical report...
Normalized Access to Ontology Repositories
Ontology repositories, such as NCBO Bioportal, ONKI and Cupboard, help finding and using ontologies on the Semantic Web. However, currently each ontology repository constitutes a separate island with its own user interface, APIs, users, ontology languages ...
Kim Viljanen; Jouni Tuominen; Eetu Makela; Eero Hyvonen
Biological treatment of leachate from a Superfund site
Studies were completed on treating a leachate from New Lyme, Ohio. The leachate was transported to Cincinnati, Ohio, where a pilot-sized rotating biological contactor (RBC) was used for a treatment evaluation. The biomass was developed on the RBC discs with primary effluent from the City of Cincinnati's Mill Creek Sewage Treatment Facility. Experiments were then conducted to determine the effectiveness of treating a hazardous waste leachate and to provide information on the following: the rate of organics removal; the final effluent quality; the fate of priority pollutants and specific organic compounds; and the loss of volatiles via stripping in the RBC. The paper reports on the results from these experiments and the applicability of an RBC to treat a hazardous-waste leachate from a Superfund site.
Opatken, E.J.; Howard, H.K.; Bond, J.J.
Repository seals requirement study
The Yucca Mountain Site Characterization Project, managed by the Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M and O) is conducting investigations to support the Viability Assessment and the License Application for a high-level nuclear waste repository at Yucca Mountain, Nevada. The sealing subsystem is part of the Yucca Mountain Waste Isolation System. The Yucca Mountain Site Characterization Project is currently evaluating the role of the sealing subsystem (shaft, ramp and exploratory borehole seals) in achieving the overall performance objectives for the Waste Isolation System. This report documents the results of those evaluations. The objective of the study is to provide water or air flow performance based requirements for shafts, ramps, and exploratory boreholes located near the repository. Recommendations, as appropriate, are provided for developing plans, seals component testing, and other studies relating to sealing.
Office of Legacy Management (LM)
MONTICELLO NPL SITES MONTICELLO NPL SITES FFA QUARTERLY REPORT: October 1 - December 31, 2007 DOE Site Manager: Jalena Maestas 1.0 MMTS Activities/Status Repository and Pond 4 * Monthly and quarterly inspection of the repository identified no problems that have not been addressed. (inspection checklists attached). * Monthly inspection of Pond 4 identified no unacceptable conditions. * Pond 4 leachate detection and removal systems continue to operate at normal levels (leachate pumping summary attached). * Repository leachate collection and removal system (LCRS) and leachate collection system (LDS) continue to operate at normal and acceptable levels (leachate pumping summary attached). * Portions of repository cover were planted with rabbitbrush seedlings to repair areas
Chemotoxicity of nuclear waste repositories
In this paper published studies on chemotoxicity of nuclear waste repositories are reviewed. According to these studies, radiotoxicity is of primary concern. However, there also is a risk, primarily from genotoxic chemical substances, which could eventually reach the biosphere. Possible chemotoxic effects should be studied as an integral part of the risk assessment and risk management of repositories for nuclear waste.
Buchheim, B. (Nordostschweizerische Kraftwerke-AG, Parkstrasse 23, CH-5401 Baden (CH)); Persson, L. (Swedish Radiation Protection Inst., P.O. Box 60204, S-104 01 Stockholm (SE))
Business Case Slide 7: High-Volume: Repository - Diagram
Diagram Previous Slide Next Slide Table of Contents High-Volume: Repository - Diagram Repository Tunnel Components...
Chemical Constituents in Coal Combustion Product Leachate: Boron
This report profiles the element boron as it occurs in leachate at coal combustion product management sites. Included are discussions of boron's occurrence in soils and water, concentrations in coal combustion products (CCPs), CCP leaching characteristics, effects on human health and ecology, geochemistry, and treatment options for removal from water.
NREL's Field Data Repository Supports Accurate Home Energy Analysis (Fact Sheet), Building America: Technical Highlight, Building Technologies Program (BTP)
Field Data Field Data Repository Supports Accurate Home Energy Analysis The Residential Buildings Research Group at the National Renewable Energy Laboratory (NREL) has developed a repository of research-level residential building characteristics and historical energy use data to support ongoing efforts to improve the accuracy of residential energy analysis tools and the efficiency of energy assessment processes. The Field Data Repository currently includes data collected from historical programs where residential building characteristics (building geometry, insulation levels, equipment types, etc.), generally collected through energy audits, have been connected to measured energy use. With an emphasis on older homes, the repository contains datasets from Home Energy Rating System
aDORe: A Modular, Standards-Based Digital Object Repository
This paper describes the aDORe repository architecture designed and implemented for ingesting, storing, and accessing a vast collection of Digital Objects at the Research Library of the Los Alamos National Laboratory. The aDORe architecture is highly ...
Herbert Van De Sompel; Jeroen Bekaert; Xiaoming Liu; Luda Balakireva; Thorsten Schwander
\\Chemical Constituents in Coal Combustion Product Leachate: Selenium
Selenium is a common constituent in coal and coal combustion products (CCPs) and can be found in CCP leachate. The chemical profile provided here assembles and summarizes existing information on selenium�s environmental characteristics, which are focused on conditions associated with CCP management. Extensive references provide a means for obtaining more detailed information on specific subject areas. The following topics are covered: 1) occurrence and sources of selenium; 2) environmental ...
Composition of Toxic Leachate and Unstable Compost to Produce Biodegradable Material
Abstract: This paper reports a study of mixing two materials that were toxic leachate and unstable compost, aiming to produce biodegradable material. Various low levels of BOD/COD of leachate were mixed with various high levels of C/N of unstable compost. CO2 evolution test was performed to measure the degree of biodegradable materials. The leachate contained BOD and COD that were more than 100 and 500 mg LG 1 respectively and represented by BOD/COD ratio of less than 0.1. The compost characterized by C/N ratio in the range of 15-20. Results showed that leachate and compost mixture produced biodegradable material. A mixture containing 20 % leachate and 80 % compost produced high level of biodegradable material. Key words: Toxic leachate % Unstable compost % Biodegradable material
Sarwoko Mangkoedihardjo; Yulia Maghriba; Rachmat Boedisantoso
MONTICELLO NPL SITES FFA QUARTERLY REPORT: October 1
October 1 October 1 - December 31,2006 DOE Project Coordinator: Art KJeinrath 1.0 MMTS Activities Repository and Pond 4 * Monthly and quarterly inspection of the repository identified no problems other than shmb damage by voles (inspection checklists attached) * Monthly inspection ofPond 4 identified no unacceptable conditions. * Pond 4 leachate detection and removal systems operated at normal levels (leachate pumping summary attached). * Repository leachate collection and removal system (LCRS) and leachate collection system (LOS) operated at normal levels (leachate pumping summary attached). Former Millsite * As a follow-up to the 2004 audit, DOE inspector general requested information regarding restoration expenditures by DOE. * No other major activity to report
Brine Migration Experimental Studies for Salt Repositories | Department of
Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Experiments were used to examine water content in Permian salt samples (Salado Formation) collected from the WIPP site. The profile of water release and movement is recognized as a function of temperature from 30 to 275 oC using classical gravimetric methods to measure weight loss as a result of heating. The amount of water released from heating the salt was found to be correlated with the salts accessory mineral content (clay, other secondary minerals lost up to 3 wt % while pure halite salt lost less than 0.5 wt % water). Water released from salt at lower temperature was reversible and is attributed to clay hydration and dehydration processes. The analysis
West Valley low-level radioactive waste site revisited: Microbiological analysis of leachates
DOE Green Energy (OSTI)
The abundance and types of microorganisms in leachate samples from the West Valley low-level radioactive waste disposal site were enumerated. This study was undertaken in support of the study conducted by Ecology and Environment, Inc., to assess the extent of radioactive gas emissions from the site. Total aerobic and anaerobic bacteria were enumerated as colony forming units (CFU) by dilution agar plate technique, and denitrifiers, sulfate-reducers and methanogens by the most probable number technique (MPN). Of the three trenches 3, 9, and 11 sampled, trench 11 contained the most number of organisms in the leachate. Concentrations of carbon-14 and tritium were highest in trench 11 leachate. Populations of aerobes and anaerobes in trench 9 leachate were one order of magnitude less than in trench 11 leachate while the methanogens were three orders of magnitude greater than in trench 11 leachate. The methane content from trench 9 was high due to the presence of a large number of methanogens; the gas in this trench also contained the most radioactivity. Trench 3 leachate contained the least number of microorganisms. Comparison of microbial populations in leachates sampled from trenches 3 and 9 during October 1978 and 1989 showed differences in the total number of microbial types. Variations in populations of the different types of organisms in the leachate reflect the changing nutrient conditions in the trenches. 14 refs., 3 figs., 4 tabs.
Gillow, J.B.; Francis, A.J.
Geologic Repository at a Geologic Repository Operations Area at Yucca
On June 3, 2008, the U.S. Department of Energy (DOE) submitted its license application (LA) to the U.S. Nuclear Regulatory Commission (NRC) for a construction authorization for a geologic repository pursuant to Section 114 of the Nuclear Waste Policy Act of 1982, as amended
Mountain Nevada; William J. Boyle
The OAI-PMH static repository and static repository gateway
Although the OAI-PMH specification is focused on making it straightforward for data providers to expose metadata, practice shows that in certain significant situations deployment of OAI-PMH conformant repository software remains problematic. In this ... Keywords: OAI-PMH, metadata harvesting
Patrick Hochstenbach; Henry Jerez; Herbert Van de Sompel
Pathways: augmenting interoperability across scholarly repositories
In the emerging eScience environment, repositories of papers, datasets, software, etc., should be the foundation of a global and natively-digital scholarly communications system. The current infrastructure falls far short of this goal. Cross-repository ...
Simeon Warner; Jeroen Bekaert; Carl Lagoze; Xiaoming Liu; Sandy Payette; Herbert Van de Warner
Enhancing Interactivity of Software and Data Repositories
... virtual repository of reusable mathematical software components (which we ... variety of types, eg, real, complex, symmetric, nonsymmetric, Hermitian. ...
A digital metadata schema repository
The metadata schema of a digital archive describes the structure and attributes of metadata. Analysis and definition of metadata schema for a new digital archive must be carefully performed at the first stage. To ease the task, we implement a metadata ... Keywords: HTML, XML, digital archive, metadata schema repository, native XML database, web-based
Yen-Chun Lin; Hsiang-An Wang; Chien-Chung Huang; Wei Chen
Repository receiving facility design support
This report provides preliminary design criteria and proposed design features to reduce the occupational radiation exposure and the transportation turnaround time during receipt of waste shipments at a Federal high-level nuclear waste repository. A cost/benefit analysis is provided. Much of the data presented in previous reports was revised and upgraded to reflect current estimates of waste generation/receipt volumes so as to provide a baseline comparison case for the cost/benefit analysis. The National Waste Repository in Basalt receiving facility operational manpower requirements, estimated occupational dose exposures and capital cost estimates were revised by scaling factors based on the volume receipts. All capital cost estimates were expressed in terms of 1983 dollars. The repository receiving facility was divided into two main areas. The cask handling facility for unloading shipments of spent fuel high-level vitrified wastes and spent fuel cladding hulls, and the TRU-waste handling facility for unloading 55-, 80-, and 600-drum shipments. In both areas, remote handling techniques were employed as much as practical. Occupational dose estimates were formulated based on an operational time and motion survey for truck and rail shipping packages and reference dose maps for each corresponding package. 9 references, 5 figures, 22 tables.
Cottrell, J.E.; Dabolt, R.J.; Steneck, P.D.
Disaster and Failure Events Data Repository
... Phase 2 � HUB Technology Pilot: Chile Dataset � Develop event-specific, web-based repository ... study teams) Page 7. Phase 2 � Chile Dataset: ...
CoRR - Computing Research Repository
Research Repository (CoRR): new, recent, abs, find By Category: Artificial Intelligence (cs.AI) Computation and Language (cs.CL) Computational Complexity (cs.CC)...
Learning from the future of component repositories
An important aspect of the quality assurance of large component repositories is the logical coherence of component metadata. We argue that it is possible to identify certain classes of such problems by checking relevant properties of the possible future ... Keywords: component repository, quality assurance, speculative analysis
Pietro Abate; Roberto Di Cosmo; Ralf Treinen; Stefano Zacchiroli
Reference repository design concept for bedded salt
A reference design concept is presented for the subsurface portions of a nuclear waste repository in bedded salt. General geologic, geotechnical, hydrologic and geochemical data as well as descriptions of the physical systems are provided for use on generic analyses of the pre- and post-sealing performance of repositories in this geologic medium. The geology of bedded salt deposits and the regional and repository horizon stratigraphy are discussed. Structural features of salt beds including discontinuities and dissolution features are presented and their effect on repository performance is discussed. Seismic hazards and the potential effects of earthquakes on underground repositories are presented. The effect on structural stability and worker safety during construction from hydrocarbon and inorganic gases is described. Geohydrologic considerations including regional hydrology, repository scale hydrology and several hydrological failure modes are presented in detail as well as the hydrological considerations that effect repository design. Operational phase performance is discussed with respect to operations, ventilation system, shaft conveyances, waste handling and retrieval systems and receival rates of nuclear waste. Performance analysis of the post sealing period of a nuclear repository is discussed, and parameters to be used in such an analysis are presented along with regulatory constraints. Some judgements are made regarding hydrologic failure scenarios. Finally, the design and licensing process, consistent with the current licensing procedure is described in a format that can be easily understood.
Carpenter, D.W.; Martin, R.W.
Repository Reference Disposal Concepts and Thermal Load Management...
Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists...
EA-1404: Actinide Chemistry and Repository Science Laboratory...
4: Actinide Chemistry and Repository Science Laboratory, Carlsbad, New Mexico EA-1404: Actinide Chemistry and Repository Science Laboratory, Carlsbad, New Mexico SUMMARY This EA...
Salt Repository Project schedule integration
The Nuclear Waste Policy Act of 1982 defined the process and schedule leading to construction of a nuclear repository available to accept commercial nuclear waste by 1998. The significance of the efforts reported in this paper are that technical staff become equally convinced of the merit of scheduling when time permits, or magnitude requires, that they be intimately involved in the scheduling process. This particular project was also unique in the variety of technical disciplines forced to interact in order to determine schedule constraints between groups. This required a strong and experienced task force to bring the groups together, promulgate the technical principles of the scheduling methodology, and distill the proper logic. Finally, it was a necessity to be end-date constrained, and this required that management mandate realistic scopes of work as well as aggressive assumptions regarding durations of certain critical path activities.
Kopp, H.D.; LaFountain, L.J. (Battelle Memorial Institute, Amarillo, TX (USA))
Aerobic attached growth biofilter using tire chips and mixed broken glass as media for landfill leachate treatment.
??Ontario regulations can necessitate expensive leachate treatment plants in large landfills. Lower-cost technologies may suit rural landfills due to lower waste toxicity and less proximity� (more)
Smith, Daniel
Aerobic Attached Growth Biofilter Using Tire Chips And Mixed Broken Glass As Media For Landfill Leachate Treatment.
Nitrogen management in landfill leachate: Application of SHARON, ANAMMOX and combined SHARON-ANAMMOX process
Highlights: Black-Right-Pointing-Pointer Significant research on ammonia removal from leachate by SHARON and ANAMMOX process. Black-Right-Pointing-Pointer Operational parameters, microbiology, biochemistry and application of the process. Black-Right-Pointing-Pointer SHARON-ANAMMOX process for leachate a new research and this paper gives wide facts. Black-Right-Pointing-Pointer Cost-effective process, alternative to existing technologies for leachate treatment. Black-Right-Pointing-Pointer Address the issues and operational conditions for application in leachate treatment. - Abstract: In today's context of waste management, landfilling of Municipal Solid Waste (MSW) is considered to be one of the standard practices worldwide. Leachate generated from municipal landfills has become a great threat to the surroundings as it contains high concentration of organics, ammonia and other toxic pollutants. Emphasis has to be placed on the removal of ammonia nitrogen in particular, derived from the nitrogen content of the MSW and it is a long term pollution problem in landfills which determines when the landfill can be considered stable. Several biological processes are available for the removal of ammonia but novel processes such as the Single Reactor System for High Activity Ammonia Removal over Nitrite (SHARON) and Anaerobic Ammonium Oxidation (ANAMMOX) process have great potential and several advantages over conventional processes. The combined SHARON-ANAMMOX process for municipal landfill leachate treatment is a new, innovative and significant approach that requires more research to identify and solve critical issues. This review addresses the operational parameters, microbiology, biochemistry and application of both the processes to remove ammonia from leachate.
Sri Shalini, S., E-mail: firstname.lastname@example.com [Centre for Environmental Studies, Anna University, Chennai (India); Joseph, Kurian, E-mail: firstname.lastname@example.com [Centre for Environmental Studies, Anna University, Chennai (India)
. . · MONTICELLO NPL SITES FFA QUARTERLY REPORT: January 1- March 31, 2007 DOE Site Manager: Jalena Maestas 1.0 MMTS Activities/Status Repository and Pond 4 * Monthly and quarterly inspection of the repository identified no problems other than shrub damage by voles (inspection checklists attached). * Monthly inspection of Pond 4 identified no unacceptable conditions. * Pond 4 leachate detection and removal systems operated at normal levels (leachate pumping summary attached). * Repository leachate collection and removal system (LCRS) and leachate collection system (LDS) operated at normal levels (leachate pumping summary attached). * Equipment purchased to upgrade repository LCRS and LDS remote sensing and telemetry system. * Portions of repository cover were manually re-seeded with desirable shrubs to repair areas
Genre Taxonomy: A Knowledge Repository of Communicative Actions
Room in Mox Corporation [Orlikowski and Yates, 1998] collaborative repository (place holder, response
Addendum to Microalgae Culture Collection 1986-1987
The SERI Microalgae Culture Collection was established in support of the U.S. Department of Energy Biofuels and Municipal Waste Technology Program to provide a repository for strains identified or developed for mass culture biomass production.
Johansen, J. R.; Lemke, P.; Nagle, N. J.; Chelf, P.; Roessler, P. G.; Galloway, R.; Toon, S.
Current Status of Deep Geological Repository Development
This talk provided an overview of the current status of deep-geological-repository development worldwide. Its principal observation is that a broad consensus exists internationally that deep-geological disposal is the only long-term solution for disposition of highly radioactive nuclear waste. Also, it is now clear that the institutional and political aspects are as important as the technical aspects in achieving overall progress. Different nations have taken different approaches to overall management of their highly radioactive wastes. Some have begun active programs to develop a deep repository for permanent disposal: the most active such programs are in the United States, Sweden, and Finland. Other countries (including France and Russia) are still deciding on whether to proceed quickly to develop such a repository, while still others (including the UK, China, Japan) have affirmatively decided to delay repository development for a long time, typically for a generation of two. In recent years, a major conclusion has been reached around the world that there is very high confidence that deep repositories can be built, operated, and closed safely and can meet whatever safety requirements are imposed by the regulatory agencies. This confidence, which has emerged in the last few years, is based on extensive work around the world in understanding how repositories behave, including both the engineering aspects and the natural-setting aspects, and how they interact together. The construction of repositories is now understood to be technically feasible, and no major barriers have been identified that would stand in the way of a successful project. Another major conclusion around the world is that the overall cost of a deep repository is not as high as some had predicted or feared. While the actual cost will not be known in detail until the costs are incurred, the general consensus is that the total life-cycle cost will not exceed a few percent of the value of the electricity generated by the power reactors that have produced the waste. Of course, the current international situation is that no nation is currently willing to take any radioactive waste from another nation for deep disposal. This means that every nation will ultimately need to develop its own deep repository. This makes no sense, however--many nations have only a modest amount of waste, or do not have appropriate geological settings for a repository, or both. Ultimately, the need for one or more multi-national or international repositories will emerge, although so far this has not happened.
Budnitz, R J
Monitored Geologic Repository Test Evaluation Plan
The Monitored Geologic Repository test & evaluation program will specify tests, demonstrations, examinations, and analyses, and describe procedures to conduct and document testing necessary to verify meeting Monitored Geologic Repository requirements for a safe and effective geologic repository for radioactive waste. This test program will provide assurance that the repository is performing as designed, and that the barriers perform as expected; it will also develop supporting documentation to support the licensing process and to demonstrate compliance with codes, standards, and regulations. This comprehensive program addresses all aspects of verification from the development of test requirements to the performance of tests and reporting of the test results. The ''Monitored Geologic Repository Test & Evaluation Plan'' provides a detailed description of the test program approach necessary to achieve the above test program objectives. This test plan incorporates a set of test phases focused on ensuring repository safety and operational readiness and implements a project-wide integrated product management team approach to facilitate test program planning, analysis, and implementation. The following sections provide a description of the individual test phases, the methodology for test program planning and analyses, and the management approach for implementing these activities.
M.B. Skorska
Constructed wetlands for municipal solid waste landfill leachate treatment. Final report
In 1989, the US Geological Survey and Cornell University, in cooperation with the New York State Energy Research and Development Authority and the Tompkins County Solid Waste Department, began a three-year study at a municipal solid-waste landfill near Ithaca, New York, to test the effectiveness of leachate treatment with constructed wetlands and to examine the associated treatment processes. Specific objectives of the study were to examine: treatment efficiency as function of substrate composition and grain size, degree of plant growth, and seasonal changes in evapotranspiration rates and microbial activity; effects of leachate and plant growth on the hydraulic characteristics of the substrate; and chemical, biological, and physical processes by which nutrients, metals, and organic compounds are removed from leachate as it flows through the substrate. A parallel study at a municipal solid-waste landfill near Fenton, New York was conducted by researchers at Cornell University, Ithaca College, and Hawk Engineering (Trautmann and others, 1989). Results are described.
Peverly, J.; Sanford, W.E.; Steenhuis, T.S. [Cornell Univ., Ithaca, NY (United States)
Cost-Effective Cementitious Material Compatible with Yucca Mountain Repository Geochemistry
The current plans for the Yucca Mountain (YM) repository project (YMP) use steel structures to stabilize the disposal drifts and connecting tunnels that are collectively over 100 kilometers in length. The potential exist to reduce the underground construction cost by 100s of millions of dollars and improve the repository's performance. These economic and engineering goals can be achieved by using the appropriate cementitious materials to build out these tunnels. This report describes the required properties of YM compatible cements and reviews the literature that proves the efficacy of this approach. This report also describes a comprehensive program to develop and test materials for a suite of underground construction technologies.
Dole, LR
Interaction of Uranium Mill Tailings Leachate with Soils and Clay Liners
This study evaluates leachate-soil interactions that will take place at the Morton Ranch for certain disposal alternatives. Laboratory tests were conducted to evaluate the following: 1) physical and chemical characteristics of geologic materials from the Morton Ranch. 2) physical and chemical characteristics of acid leach tailings and tallings solution, 3) leaching tests with selected tailings materials and leach solutions to evaluate the leachability of contaminants with time under specific disposal alternatives, 4) adsorption studies measuring the sorption characteristics of heavy metals and radionuclides on the geologic materials at Morton Ranch, 5) clay liner stability tests to evaluate effects of acid leachate on clay mineralogy and clay permeability.
Gee, G. W.; Campbell, A. C.; Sherwood, D. R.; Strickert, R. G.; Phillips, S. J.
Preliminary Evaluation of a Newly Isolated Microalga Scenedesmus sp. CHX1 for Treating Landfill Leachate
This study aims to evaluate the feasibility of landfill leach ate treatment using micro algae. The growth and nutrients removal efficiency of a newly isolated micro alga Scenedesmus sp. CHX1 were monitored when the strain grew in landfill leach ate at ... Keywords: Scenedesmus sp. CHX1, Growth, Landfill leachate, Nutrients removal
Hai-Xiang Cheng, Guang-Ming Tian
EIDR :: Experimental Information and Data Repository
EIDR :: Experimental Information and Data Repository EIDR :: Experimental Information and Data Repository QUICK LINKS: About EIDR | EIDR FAQS | VIEW gene expression data | VIEW phenotype microarray data > Browse data by ... mouse over the below to display the menus experimental condition organism organism, experimental condition organism, type of laboratory analyses type of laboratory analyses Status of data import 2007-02-10 EIDR Overview EIDR is an information database for the ESPP project. It contains information about data generated by project participants, as well as links to data stored either in Biofiles or in the Experimental Data Repository. EIDR references data files that have been uploaded to LBNL using Biofiles, custom Web interfaces, or ftp. Information about the data includes design information about biomass production experiments, information about the lab analyses that generated the data, and links to more detailed information, displays, or analyses. You can browse for data using the menus in the Browse data by ... table to the left.
A study of tritium in municipal solid waste leachate and gas
It has become increasingly clear in the last few years that the vast majority of municipal solid waste landfills produce leachate that contains elevated levels of tritium. The authors recently conducted a study of landfills in New York and New Jersey and found that the mean concentration of tritium in the leachate from ten municipal solid waste (MSW) landfills was 33,800 pCi/L with a peak value of 192,000 pCi/L. A 2003 study in California reported a mean tritium concentration of 99,000 pCi/L with a peak value of 304,000 pCi/L. Studies in Pennsylvania and the UK produced similar results. The USEPA MCL for tritium is 20,000 pCi/L. Tritium is also manifesting itself as landfill gas and landfill gas condensate. Landfill gas condensate samples from landfills in the UK and California were found to have tritium concentrations as high as 54,400 and 513,000 pCi/L, respectively. The tritium found in MSW leachate is believed to derive principally from gaseous tritium lighting devices used in some emergency exit signs, compasses, watches, and even novelty items, such as 'glow stick' key chains. This study reports the findings of recent surveys of leachate from a number of municipal solid waste landfills, both open and closed, from throughout the United States and Europe. The study evaluates the human health and ecological risks posed by elevated tritium levels in municipal solid waste leachate and landfill gas and the implications to their safe management. We also assess the potential risks posed to solid waste management facility workers exposed to tritium-containing waste materials in transfer stations and other solid waste management facilities. (authors)
Mutch Jr, R. D. [HydroQual, Inc., 1200 MacArthur Blvd., Mahwah, NJ 07430 (United States); Manhattan College, Riverdale, NY (United States); Columbia Univ., New York, NY (United States); Mahony, J. D. [HydroQual, Inc., 1200 MacArthur Blvd., Mahwah, NJ 07430 (United States); Manhattan College, Riverdale, NY (United States)
Analytical Performance Models for Geologic Repositories
This report presents analytical solutions of the dissolution and hydrogeologic transport of radionuclides in geologic repositories. Numerical examples are presented to demonstrate the equations resulting from these analyses. The subjects treated in the present report are: (a) Solubility-limited transport with transverse dispersion (Chapter 2); (b) Transport of a radionuclide chain with nonequilibrium chemical reactions (Chapter 3); (c) Advective transport in a two-dimensional flow field (Chapter 4); (d) Radionuclide.transport in fractured media (Chapter 5); (e) A mathematical model for EPA's analysis of generic repositories (Chapter 6); and (f) Dissolution of radionuclides from solid waste (Chapter 7).
Chambre, P.L.; Pigford, T.H.; Fujita, A.; Kanki, T.; Kobayashi,A.; Lung, H.; Ting, D.; Sato, Y.; Savoshy, S.J.
New Yucca Mountain Repository Design to be Simpler, Safer and...
New Yucca Mountain Repository Design to be Simpler, Safer and More Cost-Effective New Yucca Mountain Repository Design to be Simpler, Safer and More Cost-Effective untitled More...
EIS-0250: Geologic Repository for the Disposal of Spent Nuclear...
EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada EIS-0250: Geologic Repository for the...
Distributed and collaborative learning objects repositories on grid networks
The paper deals with the design and a prototype implementation of a collaborative repository of scientific learning objects based on an efficient mechanism of filing and retrieving distributed knowledge on the Grid. The proposed repository can deal with ... Keywords: chemistry, grid, knowledge, learning objects, repository
Simonetta Pallottelli; Sergio Tasso; Nicola Pannacci; Alessandro Costantini; Noelia Faginas Lago
National Geoscience Data Repository System -- Phase III: Implementation and Operation of the Repository
The National Geoscience Data Repository System, Phase III was an operational project focused on coordinating and facilitating transfers of at-risk geoscience data from the private sector to the public domain.
Keane, Christopher M.
Web-based metadata schema repository
The metadata schema of a digital archive describes the structure and attributes of metadata. Analysis and definition of metadata schema for a new digital archive must be carefully carried out and determined at the first stage of development. To ease ... Keywords: digital archive, extensible markup language, hyperText markup language, metadata schema repository, native XML database, web-based
National Geoscience Data Repository System. Final report
The American Geological Institute (AGI) has completed the first phase of a study to assess the feasibility of establishing a National Geoscience Data Repository System to capture and preserve valuable geoscientific data. The study was initiated in response to the fact that billions of dollars worth of domestic geological and geophysical data are in jeopardy of being irrevocably lost or destroyed as a consequence of the ongoing downsizing of the US energy and minerals industry. This report focuses on two major issues. First, it documents the types and quantity of data available for contribution to a National Geoscience Data Repository System. Second, it documents the data needs and priorities of potential users of the system. A National Geoscience Data Repository System would serve as an important and valuable source of information for the entire geoscience community for a variety of applications, including environmental protection, water resource management, global change studies, and basic and applied research. The repository system would also contain critical data that would enable domestic energy and minerals companies to expand their exploration and production programs in the United States for improved recovery of domestic oil, gas, and mineral resources.
Schiffries, C.M.; Milling, M.E.
Repository synchronization in the OAI framework
The Open Archives Initiative Protocol for Metadata Harvesting (OAI-PMH) began as an alternative to distributed searching of scholarly eprint repositories. The model embraced by the OAI-PMH is that of metadata harvesting, where value-added services (by ...
Xiaoming Liu; Kurt Maly; Mohammad Zubair; Michael L. Nelson
Collection understanding
Collection understanding shifts the traditional focus of retrieval in large collections from locating specific artifacts to gaining a comprehensive view of the collection. Visualization tools are critical to the process of efficient collection understanding ... Keywords: ambient slideshow, collection understanding, digital libraries, image visualization, information visualization, streaming collage, variably gridded thumbnails
Michelle Chang; John J. Leggett; Richard Furuta; Andruid Kerne; J. Patrick Williams; Samuel A. Burns; Randolph G. Bias
Repository Applications: Potential Benefits of Using Depleted Uranium (DU)
Repository Applications Repository Applications Repository Applications: Potential Benefits of Using Depleted Uranium (DU) in a Geological Repository The United States is investigating the Yucca Mountain (YM) site in Nevada for the disposal of radioactive spent nuclear fuel (SNF)the primary waste from nuclear power plants. The SNF would be packaged and then emplaced 200 to 300 m underground in parallel disposal tunnels. The repository isolates the SNF from the biosphere until the radionuclides decay to safe levels. DU may improve the performance of geological repositories for disposal of SNF via three mechanisms: Radiation shielding for waste packages to protect workers Lowering the potential for long-term nuclear criticality in the repository Reducing the potential for releases of radionuclides from the SNF
Treatment of municipal landfill leachate using a combined anaerobic digester and activated sludge system
The main objective of this study was to assess the feasibility of treating sanitary landfill leachate using a combined anaerobic and activated sludge system. A high-strength leachate from Shiraz municipal landfill site was treated using this system. A two-stage laboratory-scale anaerobic digester under mesophilic conditions and an activated sludge unit were used. Landfill leachate composition and characteristics varied considerably during 8 months experiment (COD concentrations of 48,552-62,150 mg/L). It was found that the system could reduce the COD of the leachate by 94% at a loading rate of 2.25 g COD/L/d and 93% at loading rate of 3.37 g COD/L/d. The anaerobic digester treatment was quite effective in removing Fe, Cu, Mn, and Ni. However, in the case of Zn, removal efficiency was about 50%. For the rest of the HMs the removal efficiencies were in the range 88.8-99.9%. Ammonia reduction did not occur in anaerobic digesters. Anaerobic reactors increased alkalinity about 3.2-4.8% in the 1st digester and 1.8-7.9% in the 2nd digester. In activated sludge unit, alkalinity and ammonia removal efficiency were 49-60% and 48.6-64.7%, respectively. Methane production rate was in the range of 0.02-0.04, 0.04-0.07, and 0.02-0.04 L/g COD{sub rem} for the 1st digester, the 2nd digester, and combination of both digesters, respectively; the methane content of the biogas varied between 60% and 63%.
Kheradmand, S. [Department of Civil and Environmental Engineering, University of Shiraz, Shiraz 7134851156 (Iran, Islamic Republic of); Karimi-Jashni, A., E-mail: firstname.lastname@example.com [Department of Civil and Environmental Engineering, University of Shiraz, Shiraz 7134851156 (Iran, Islamic Republic of); Sartaj, M. [Department of Civil Engineering, Isfahan University of Technology, Isfahan 841568311 (Iran, Islamic Republic of)
Hydraulic Conductivity of Geosynthetic Clay Liners to Coal Combustion Product Leachates: Interim Report
Hydraulic conductivity tests are being conducted on geosynthetic clay liners (GCLs) using solutions representing leachates observed in disposal facilities for coal combustion products (CCPs). Five different GCL products that are commercially available within the United States are being tested: two containing conventional sodium bentonite (NaB), two containing polymer-modified bentonite (PMB), and one with a bentonite polymer composite (BPC). Testing to date has been conducted by direct permeation ...
Groundwater Quality Signatures for Assessing Potential Impacts from Coal Combustion Product Leachate
Boron and sulfate are recognized as potential indicators of the influence of leachate from coal-combustion products (CCPs) on groundwater quality. However, there are cases in which these two constituents do not provide sufficient data to characterize groundwater for potential impacts from CCPs. In these cases, the concentrations of other indicator constituents in solution and/or advanced analytical techniques may be used to support other information. A three-tiered analysis approach can provide a ...
Organic and nitrogen removal from landfill leachate in aerobic granular sludge sequencing batch reactors
Highlights: Black-Right-Pointing-Pointer Aerobic granular sludge SBR was used to treat real landfill leachate. Black-Right-Pointing-Pointer COD removal was analyzed kinetically using a modified model. Black-Right-Pointing-Pointer Characteristics of nitrogen removal at different ammonium inputs were explored. Black-Right-Pointing-Pointer DO variations were consistent with the GSBR performances at low ammonium inputs. - Abstract: Granule sequencing batch reactors (GSBR) were established for landfill leachate treatment, and the COD removal was analyzed kinetically using a modified model. Results showed that COD removal rate decreased as influent ammonium concentration increasing. Characteristics of nitrogen removal at different influent ammonium levels were also studied. When the ammonium concentration in the landfill leachate was 366 mg L{sup -1}, the dominant nitrogen removal process in the GSBR was simultaneous nitrification and denitrification (SND). Under the ammonium concentration of 788 mg L{sup -1}, nitrite accumulation occurred and the accumulated nitrite was reduced to nitrogen gas by the shortcut denitrification process. When the influent ammonium increased to a higher level of 1105 mg L{sup -1}, accumulation of nitrite and nitrate lasted in the whole cycle, and the removal efficiencies of total nitrogen and ammonium decreased to only 35.0% and 39.3%, respectively. Results also showed that DO was a useful process controlling parameter for the organics and nitrogen removal at low ammonium input.
Wei Yanjie [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Key Laboratory of Environmental Protection in Water Transport Engineering Ministry of Communications, Tianjin Research Institute of Water Transport Engineering, Tianjin 300456 (China); Ji Min, E-mail: email@example.com [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Li Ruying [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Qin Feifei [Tianjin Tanggu Sino French Water Supply Co. Ltd., Tianjin 300450 (China)
This report summarizes work completed by the repository subsurface design group during the 1993 fiscal year (FY93), and represents a portion of the ongoing, repository Advanced Conceptual Design (ACD) effort. The ACD work is being performed in accordance with guidance and controls established for the United States Department of Energy's (DOE) Yucca Mountain Project (YMP). This document draws information from other ACD reports prepared and submitted during the year, and from other program studies, including the Exploratory Studies Facility (ESF) Title II design. Site specific data gathered by the Surface Based Testing (SBT) program has been included to the extent that it became available early enough for use in the designs presented herein.
Dana J. Rogers
aDORe: a modular and standards-based digital object repository at the los alamos national laboratory
This paper describes the aDORe repository architecture, designed and implemented for ingesting, storing, and accessing a vast collection of Digital Objects at the Research Library of the Los Alamos National Laboratory. Keywords: MPEG-21, OAI-PMH, OAIS, OpenURL, digital object
Jeroen Bekaert; Xiaoming Liu; Herbert Van de Sompel
EPRI Distribution Reliability Practices Repository V2
A key objective of EPRI's research into distribution reliability practices is to identify, document and provide practice summary descriptions to research participants in a format that facilitates comparison and aids decision-makers in identifying those practices in place at other utilities which can be applied to their utility to improve performance.�This research report presents distribution reliability practice results from six different companies in a repository which places ...
Salt repository project closeout status report
This report provides an overview of the scope and status of the US Department of Energy (DOE`s) Salt Repository Project (SRP) at the time when the project was terminated by the Nuclear Waste Policy Amendments Act of 1987. The report reviews the 10-year program of siting a geologic repository for high-level nuclear waste in rock salt formations. Its purpose is to aid persons interested in the information developed during the course of this effort. Each area is briefly described and the major items of information are noted. This report, the three salt Environmental Assessments, and the Site Characterization Plan are the suggested starting points for any search of the literature and information developed by the program participants. Prior to termination, DOE was preparing to characterize three candidate sites for the first mined geologic repository for the permanent disposal of high-level nuclear waste. The sites were in Nevada, a site in volcanic tuff; Texas, a site in bedded salt (halite); and Washington, a site in basalt. These sites, identified by the screening process described in Chapter 3, were selected from the nine potentially acceptable sites shown on Figure I-1. These sites were identified in accordance with provisions of the Nuclear Waste Policy Act of 1982. 196 refs., 21 figs., 11 tabs.
Polybrominated diphenyl ethers (PBDEs) in leachates from selected landfill sites in South Africa
The last few decades have seen dramatic growth in the scale of production and the use of polybrominated diphenyl ethers (PBDEs) as flame retardants. Consequently, PBDEs such as BDE -28, -47, -66, -71, -75, -77, -85, -99, -100, -119, -138, -153, -154, and -183 have been detected in various environmental matrices. Generally, in South Africa, once the products containing these chemicals have outlived their usefulness, they are discarded into landfill sites. Consequently, the levels of PBDEs in leachates from landfill sites may give an indication of the general exposure and use of these compounds. The present study was aimed at determining the occurrence and concentrations of most common PBDEs in leachates from selected landfill sites. The extraction capacities of the solvents were also tested. Spiked landfill leachate samples were used for the recovery tests. Separation and determination of the PBDE congeners were carried out with a gas chromatograph equipped with Ni{sup 63} electron capture detector. The mean percentage recoveries ranged from 63% to 108% (n = 3) for landfill leachate samples with petroleum ether giving the highest percentage extraction. The mean concentrations of PBDEs obtained ranged from ND to 2670 pg l{sup -1}, ND to 6638 pg l{sup -1}, ND to 7230 pg l{sup -1}, 41 to 4009 pg l{sup -1}, 90 to 9793 pg l{sup -1} for the Garankuwa, Hatherly, Kwaggarsrand, Soshanguve and Temba landfill sites, respectively. Also BDE -28, -47, -71 and BDE-77 were detected in the leachate samples from all the landfill sites; and all the congeners were detected in two of the oldest landfill sites. The peak concentrations were recorded for BDE-47 at three sites and BDE-71 and BDE-75 at two sites. The highest concentration, 9793 {+-} 1.5 pg l{sup -1}, was obtained for the Temba landfill site with the highest BOD value. This may suggest some influence of organics on the level of PBDEs. Considering the leaching characteristics of brominated flame retardants, there is a high possibility that with time these compounds may infiltrate into the groundwater around the sites since most of the sites are not adequately lined.
Odusanya, David O. [Department of Environmental, Water and Earth Sciences, Faculty of Science, Tshwane University of Technology, Private Bag X680, 175 Nelson Mandela Drive, Arcadia, Pretoria 0001 (South Africa); Okonkwo, Jonathan O. [Department of Environmental, Water and Earth Sciences, Faculty of Science, Tshwane University of Technology, Private Bag X680, 175 Nelson Mandela Drive, Arcadia, Pretoria 0001 (South Africa)], E-mail: firstname.lastname@example.com; Botha, Ben [Department of Environmental, Water and Earth Sciences, Faculty of Science, Tshwane University of Technology, Private Bag X680, 175 Nelson Mandela Drive, Arcadia, Pretoria 0001 (South Africa)
The purpose of this document is to develop preliminary high-level functional and physical control system architectures for the proposed subsurface repository at Yucca Mountain. This document outlines overall control system concepts that encompass and integrate the many diverse systems being considered for use within the subsurface repository. This document presents integrated design concepts for monitoring and controlling the diverse set of subsurface operations. The subsurface repository design will be composed of a series of diverse systems that will be integrated to accomplish a set of overall functions and objectives. The subsurface repository contains several Instrumentation and Control (I&C) related systems including: waste emplacement systems, ventilation systems, communication systems, radiation monitoring systems, rail transportation systems, ground control monitoring systems, utility monitoring systems (electrical, lighting, water, compressed air, etc.), fire detection and protection systems, retrieval systems, and performance confirmation systems. Each of these systems involve some level of I&C and will typically be integrated over a data communication network. The subsurface I&C systems will also integrate with multiple surface-based site-wide systems such as emergency response, health physics, security and safeguards, communications, utilities and others. The scope and primary objectives of this analysis are to: (1) Identify preliminary system level functions and interface needs (Presented in the functional diagrams in Section 7.2). (2) Examine the overall system complexity and determine how and on what levels these control systems will be controlled and integrated (Presented in Section 7.2). (3) Develop a preliminary subsurface facility-wide design for an overall control system architecture, and depict this design by a series of control system functional block diagrams (Presented in Section 7.2). (4) Develop a series of physical architectures that present preliminary concepts for integrating the diverse set of control systems to be used within the subsurface repository facility (Presented in Section 7.3). (5) Develop initial concepts for an overall subsurface data communication system that can be used to integrate critical and data-intensive control systems (Presented in Section 7.4). (6) Discuss technology trends and control system design issues (Presented in Section 7.5).
C.J. Fernado
Impact of Drill and Blast Excavation on Repository Performance Confirmation
There has been considerable work accomplished internationally examining the effects of drill and blast excavation on rock masses surrounding emplacement openings of proposed nuclear waste repositories. However, there has been limited discussion tying the previous work to performance confirmation models such as those proposed for Yucca Mountain, Nevada. This paper addresses a possible approach to joining the available information on drill and blast excavation and performance confirmation. The method for coupling rock damage data from drill and blast models to performance assessment models for fracture flow requires a correlation representing the functional relationship between the peak particle velocity (PPV) vibration levels and the potential properties that govern water flow rates in the host rock. Fracture aperture and frequency are the rock properties which may be most influenced by drill and blast induced vibration. If it can be shown (using an appropriate blasting model simulation) that the effect of blasting is far removed from the waste package in an emplacement drift, then disturbance to the host rock induced in the process of drill and blast excavation may be reasonably ignored in performance assessment calculations. This paper proposes that the CANMET (Canada Center for Mineral and Energy Technology) Criterion, based on properties that determine rock strength, may be used to define a minimum PPV. This PPV can be used to delineate the extent of blast induced damage. Initial applications have demonstrated that blasting models can successfully be coupled with this criterion to predict blast damage surrounding underground openings. The Exploratory Studies Facility at Yucca Mountain has used a blasting model to generate meaningful estimates of near-field vibration levels and damage envelopes correlating to data collected from pre-existing studies conducted. Further work is underway to expand this application over a statistical distribution of geologic parameters, encompassing all the rock types that will be encountered for the proposed repository site at Yucca Mountain. This paper suggests that, based on predicted and verified vibration levels from blasting a distance equal to four standard deviations is unlikely to affect properties that govern water flow in the host rock. The authors propose this predicted distance and verification of vibration levels may be applied to the excavation of repository subsurface openings that may be most efficiently excavated by drill and blast methods with a reasonable assurance of safety.
R. Keller; N. Francis; J. Houseworth; N. Kramer
Viability Assessment of a Repository at Yucca Mountain | Department of
Viability Assessment of a Repository at Yucca Mountain Viability Assessment of a Repository at Yucca Mountain Viability Assessment of a Repository at Yucca Mountain Summary The Viability Assessment of a Repository at Yucca Mountain describes the nuclear waste problem and explains why the United States and other nations are considering deep geologic disposal as the solution. The overview describes why the Unites States is considering Yucca Mountain and how a monitored geologic repository would work in the mountain. It presents a repository design, an assessment of its expected performance, and an evaluation of the possible effects on people living near Yucca Mountain. Also presented is the work remaining to be completed prior to a license application, along with the estimated cost of building and operating a
Status of Proposed Repository for Latin-American Spent Fuel
This report compiles preliminary information that supports the premise that a repository is needed in Latin America and analyzes the nuclear situation (mainly in Argentina and Brazil) in terms of nuclear capabilities, inventories, and regional spent-fuel repositories. The report is based on several sources and summarizes (1) the nuclear capabilities in Latin America and establishes the framework for the need of a permanent repository, (2) the International Atomic Energy Agency (IAEA) approach for a regional spent-fuel repository and describes the support that international institutions are lending to this issue, (3) the current situation in Argentina in order to analyze the Argentinean willingness to find a location for a deep geological repository, and (4) the issues involved in selecting a location for the repository and identifies a potential location. This report then draws conclusions based on an analysis of this information. The focus of this report is mainly on spent fuel and does not elaborate on other radiological waste sources.
Ferrada, J.J.
Calphad Data and File Repositories for the Development of Design ...
Increasing knowledge about these alloys requires updates and extension of existing databases with Calphad file and data repositories enabling more efficient�...
File and Data Repositories for CALPHAD and Beyond
Such a repository needs to include files with functional descriptions, data files used for refinement of the functional descriptions and auxiliary files. The files are �...
Business Case Slide 6: High-Volume: Repository - Description
Volume: Repository - Description Description of potential uses Structural component of cask (basket, wall) as a cermet Cermet: DUO2 particles embedded in steel matrix Fill material...
Business Case Slide 9: High-Volume: Repository - Potential Benefits
Repository - Potential Benefits Potential benefits EM Any of the four applications could use most or all of the DU inventory which could avoid transportation and disposal cost No...
Drift Natural Convection and Seepage at the Yucca Mountain Repository
Flow path of radionuclides from repository and intofor sequestration of radionuclides, from the small quantityadvective transport of radionuclides in this region. 4)
Halecky, Nicholaus Eugene
DOE Hydrogen and Fuel Cells Program: Analysis Repository Home...
Electricity production, central and distributed Energy resource estimation and forecasting. The U.S. Department of Energy created this repository to help analysts, policy...
Collecting apparatus
DOE Patents (OSTI)
An improved collecting apparatus for small aquatic or airborne organisms such as plankton, larval fish, insects, etc. The improvement constitutes an apertured removal container within which is retained a collecting bag, and which is secured at the apex of a conical collecting net. Such collectors are towed behind a vessel or vehicle with the open end of the conical net facing forward for trapping the aquatic or airborne organisms within the collecting bag, while allowing the water or air to pass through the apertures in the container. The container is readily removable from the collecting net whereby the collecting bag can be quickly removed and replaced for further sample collection. The collecting bag is provided with means for preventing the bag from being pulled into the container by the water or air flowing therethrough.
Duncan, Charles P. (Walnut Creek, CA)
Climate Collections
Regional/Global > Climate Collections Regional/Global > Climate Collections Climate Collections Overview Climate encompasses the statistics of temperature, humidity, atmospheric pressure, wind, rainfall, atmospheric particle count, and numerous other meteorological elements in a given region over long periods of time. Climate can be contrasted to weather, which is the present condition of these same elements over periods up to two weeks. The climate collections project includes data sets containing measured and modeled values for variables such as temperature, precipitation, humidity, radiation, wind velocity, and cloud cover and include station measurements as well as gridded mean values. The ORNL DAAC Climate Collections Data archive includes 10 data products from the following categories:
Range of Neutronic Parameters for Repository Criticality Analyses
The ''Range of Neutronic Parameters for Repository Criticality Analyses'' technical report contains a summary of the benchmark criticality analyses (including the laboratory critical experiment [LCEs] and the commercial reactor criticals [CRCs]) used to support the validation of the criticality evaluation methods. This report also documents the development of the Critical Limits (CLs) for the repository criticality analyses.
W.J. Anderson
Reusable learning objects: a survey of LOM-based repositories
In this paper, we survey the field of learning object repositories. Learning objects are typically relatively small content components that are meant to be reusable in different contexts. Associated to these learning objects are metadata, so that they ... Keywords: Learning Object Metadata (LOM), digital libraries, learning object repositories, metadata, reusable learning objects
Filip Neven; Erik Duval
A Weighted Freshness Metric for Maintaining Search Engine Local Repository
Current search engines maintain a local repository to improve the search efficiency. A crawler is used to periodically poll the remote web pages to update the contents of the local repository. Due to the resource limitations, some local pages may be ...
Jianchao Han; Nick Cercone; Xiaohua Hu
Hydroclimatology Collections
North America. What about the two CD's are we going to archive them? See THIS LINK. The ORNL DAAC Hydroclimatology Collections Data archive includes the following data products:...
The National Repository at Yucca Mountain, Russ Dyer
Repository at Repository at Yucca Mountain Presented to: EM High Level Waste Corporate Board Presented by: Russ Dyer Chief Scientist Office of Civilian Radioactive Waste Management July 24, 2008 Idaho National Laboratory 2 SBBB-GeneralBriefing_070808Rev1.ppt Solving a national problem now * On June 3, 2008, the U.S. Department of Energy submitted an application to the U.S. Nuclear Regulatory Commission for a license to construct a repository at Yucca Mountain 3 SBBB-GeneralBriefing_070808Rev1.ppt Repository license application * The LA seeks authorization to construct the nation's first geologic repository * It is a culmination of more than 25 years of scientific research and engineering * The LA describes DOE's plan to safely isolate spent nuclear fuel and high-level radioactive
Transport and reaction kinetics at the glass:solution interface region: Results of repository-oriented leaching experiments
Repository-oriented leaching experiments involving Savannah River Laboratory (SRL) 165 type glass under a {gamma}-radiation field (1 = 0.2 x 10{sup 4} R/h) have been performed by the Nevada Nuclear Waste Storage Investigations (NNWSI) project. In this communication, we discuss glass surface analyses obtained by SEM, nuclear resonance profiling, and SIMS together with leachate solution data in relation to a mechanism that couples diffusion, hydrolysis (etching and gelation), and precipitation to qualitatively describe the release of different glass components to the leachant solutions. The release of mobile (e.g., Li) and partly mobile (e.g., B) species is controlled primarily by interdiffusion with water species across the interdiffusion zone. Glass components that are immobile in the interdiffusion zone are released to the solution by etching. For prediction of long-term steady-state concentrations of glass components with low solubility, the relative rates of release from the glass and secondary mineral precipitation must be taken into account.
Abrajano, T.A. Jr.; Bates, J.K.
Repository Subsurface Preliminary Fire Hazard Analysis
This fire hazard analysis identifies preliminary design and operations features, fire, and explosion hazards, and provides a reasonable basis to establish the design requirements of fire protection systems during development and emplacement phases of the subsurface repository. This document follows the Technical Work Plan (TWP) (CRWMS M&O 2001c) which was prepared in accordance with AP-2.21Q, ''Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities''; Attachment 4 of AP-ESH-008, ''Hazards Analysis System''; and AP-3.11Q, ''Technical Reports''. The objective of this report is to establish the requirements that provide for facility nuclear safety and a proper level of personnel safety and property protection from the effects of fire and the adverse effects of fire-extinguishing agents.
Richard C. Logan
Repository surface design site layout analysis
The purpose of this analysis is to establish the arrangement of the Yucca Mountain Repository surface facilities and features near the North Portal. The analysis updates and expands the North Portal area site layout concept presented in the ACD, including changes to reflect the resizing of the Waste Handling Building (WHB), Waste Treatment Building (WTB), Carrier Preparation Building (CPB), and site parking areas; the addition of the Carrier Washdown Buildings (CWBs); the elimination of the Cask Maintenance Facility (CMF); and the development of a concept for site grading and flood control. The analysis also establishes the layout of the surface features (e.g., roads and utilities) that connect all the repository surface areas (North Portal Operations Area, South Portal Development Operations Area, Emplacement Shaft Surface Operations Area, and Development Shaft Surface Operations Area) and locates an area for a potential lag storage facility. Details of South Portal and shaft layouts will be covered in separate design analyses. The objective of this analysis is to provide a suitable level of design for the Viability Assessment (VA). The analysis was revised to incorporate additional material developed since the issuance of Revision 01. This material includes safeguards and security input, utility system input (size and location of fire water tanks and pump houses, potable water and sanitary sewage rates, size of wastewater evaporation pond, size and location of the utility building, size of the bulk fuel storage tank, and size and location of other exterior process equipment), main electrical substation information, redundancy of water supply and storage for the fire support system, and additional information on the storm water retention pond.
Montalvo, H.R.
Monitored Geologic Repository Project Description Document
The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the Yucca Mountain Site Characterization Project Requirements Document (YMP RD) (YMP 2001a) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) technical requirements in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The technical requirements documented in the PDD are to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the technical requirements from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the technical requirements captured in the SDDs and the design requirements captured in US Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M&O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 1-1, the MGR Architecture (Section 4.1), the Technical Requirements (Section 5), and the Controlled Project Assumptions (Section 6).
P. Curry
In the past six months the NGDRS program has seen a new spike in activity, particularly in October 2000. This new spike in activity is the result of increased activities in the petroleum sector, including new funding to examine infrastructure issues facing many of the companies over the long-term. With industry conditions continuing to rapidly change and evolve, the primary core and cuttings preservation strategy has evolved as well. With the severe lack of available public data repository space and the establishment of a major national geoscience data repository facility unlikely in the near future, the focus is on increasing public awareness and access to nonproprietary company data holdings that remain in the public and private sector. Efforts still continue to identify and facilitate the entry of new repository space into the public sector. Additionally, AGI has been working with the National Academy of Sciences Board on Earth Sciences and Resources staff to initiate a study and workshop to develop a policy recommendation on geoscience data preservation and prioritization of efforts. Additional data transfer efforts were undertaken during the second half of FY00. Altura's Permian Basin core was contributed to the Texas BEG's facility in Midland. Transcription and evaluation of selected seismic data from the Santa Barbara Channel previously owned by Phillips was completed. Additionally, Chevron has released over 180,000 boxes of cores to the public through the NGDRS metadata catalog.
Marcus Milling
USA NRC/RSR Data Bank System and Reactor Safety Research Data Repository (RSRDR)
The United States Nuclear Regulatory Commission (NRC), through its Division of Reactor Safety Research (RSR) of the Office of Nuclear Regulatory Research, has established the NRC/RSR Data Bank Program to collect, process, and make available data from the many domestic and foreign water reactor safety research programs. An increasing number of requests for data and/or calculations generated by NRC Contractors led to the initiation of the program which allows timely and direct access to water reactor safety data in a manner most useful to the user. The program consists of three main elements: data sources, service organizations, and a data repository.
Maskewitz, B.F.; Bankert, S.F.
Naturally occurring mobile colloids are ubiquitous and are involved in many important processes in the subsurface zone. For example, colloid generation and subsequent mobilization represent a possible mechanism for the transport of contaminants including radionuclides in the subsurface environments. For colloid-facilitated transport to be significant, three criteria must be met: (1) colloids must be generated; (2) contaminants must associate with the colloids preferentially to the immobile solid phase (aquifer); and (3) colloids must be transported through the groundwater or in subsurface environments - once these colloids start moving they become 'mobile colloids'. Although some experimental investigations of particle release in natural porous media have been conducted, the detailed mechanisms of release and re-deposition of colloidal particles within natural porous media are poorly understood. Even though this vector of transport is known, the extent of its importance is not known yet. Colloid-facilitated transport of trace radionuclides has been observed in the field, thus demonstrating a possible radiological risk associated with the colloids. The objective of this study was to determine if cementitious leachate would promote the in situ mobilization of natural colloidal particles from a SRS sandy sediment. The intent was to determine whether cementitious surface or subsurface structure would create plumes that could produce conditions conducive to sediment dispersion and mobile colloid generation. Column studies were conducted and the cation chemistries of influents and effluents were analyzed by ICP-OES, while the mobilized colloids were characterized using XRD, SEM, EDX, PSD and Zeta potential. The mobilization mechanisms of colloids in a SRS sandy sediment by cement leachates were studied.
Li, D.; Roberts, K.; Kaplan, D.; Seaman, J.
Thermohydrologic behavior and repository design at Yucca Mountain
Radioactive decay of nuclear waste emplaced at Yucca Mountain will produce an initial heat flux many times larger than the heat flux in some natural geothermal systems. This heat flux will change the thermal and hydrologic environment at Yucca Mountain significantly, affecting both the host rock and conditions within the emplacement tunnels (drifts). Understanding the thermohydrologic behavior in this coupled natural and engineered system is critical to the assessment of the viability of Yucca Mountain as a nuclear-waste repository site and for repository design decision-making. We report results from a study that uses our multi-scale modeling approach to explore the relationship between repository design, thermohydrologic behavior, and key repository performance measures.
Buscheck, T; Rosenberg, N D; Gansemer, J D; Sun, Y
2 A Simulation Code for Yucca Mountain Transport Processes:List of Figures Yucca Mountain location, southwest1 Introduction 1.1 Yucca Mountain Repository . . . . 1.1.1
Business Case Slide 11: High-Volume: Repository - Program Focus
Program Focus Previous Slide Next Slide Table of Contents High-Volume: Repository - Program Focus Program focus (ORNL) Fill and cermets are being pursued Both put DUO2 close to...
Business Case Slide 10: High-Volume: Repository - Issues
Issues Previous Slide Next Slide Table of Contents High-Volume: Repository - Issues Issues Technical basis for using DUO2 as a geochemical barrier Technical issues DUO2 alteration...
Method for storing spent nuclear fuel in repositories
A method for storing radioactive spent fuel in repositories containing sulfur as the storage medium is disclosed. Sulfur is non-corrosive and not subject to radiation damage. Thus, storage periods of up to 100 years are possible.
Schweitzer, Donald G. (Bayport, NY); Sastre, Cesar (Shoreham, NY); Winsche, Warren (Bellport, NY)
ROARS: a scalable repository for data intensive scientific computing
As scientific research becomes more data intensive, there is an increasing need for scalable, reliable, and high performance storage systems. Such data repositories must provide both data archival services and rich metadata, and cleanly integrate with ...
Hoang Bui; Peter Bui; Patrick Flynn; Douglas Thain
Repository Synchronization in the OAI Framework Xiaoming Liu
Repository Synchronization in the OAI Framework Xiaoming Liu Research Library Los Alamos Research Laboratory Los Alamos, NM, 87544 liu firstname.lastname@example.com Kurt Maly Mohammad Zubair Michael L. Nelson Computer Science
Nelson, Michael L.
collections of its (currently over 100) member institutions. It has been funded by DARPA and the National Science Foundations, with most of the technical work recently being...
GSA Data Repository item 0000 Supplemental data for
GSA Data Repository item 0000 Supplemental data for Exhumation History of the Alam Kuh Area Data Repository item 0000 Item PDF file name U-Pb data table for Akapol zircon samples (97AK101, 97AK102, and 19-12-1) Akapol_zircon_data.PDF U-Pb data table for Alam Kuh zircon samples (19-29-1) Alam_Kuh_zircon_data
Harrison, Mark
In the past six months the NGDRS program has continued to engaged new contacts, identify additional data transfer targets, and improve the metadata catalog for both easier use and long-term maintainability. With industry conditions continuing to rapidly change and evolve, the primary core and cuttings preservation strategy has evolved as well. With the severe lack of available public data repository space and the establishment of a major national geoscience data repository facility unlikely in the near future, the focus is on increasing public awareness and access to nonproprietary company data holdings that remain in the public and private sector. Efforts still continue to identify and facilitate the entry of new repository space into the public sector. Additionally, AGI has been working with the National Academy of Sciences Board on Earth Sciences and Resources staff to initiate a study and workshop to develop a policy recommendation on geoscience data preservation and prioritization of efforts. Additional data transfer efforts were undertaken during the first half of FY00. AGI is working with the Texas Bureau of Economic Geology to assist in the transfer of Altura's midland core holdings to the University of Texas. Phillips has made selected seismic data from the Santa Barbara Channel available for transfer. A pilot test has been initiated to determine the cost and potential success rate at transcription of the original tapes. Additionally, redesign of the GeoTrek metadata catalog was initiated, including both a redesign of the user interface as well as making GeoTrek fully a broker, accessing multiple databases at remote locations in real time.
National Geoscience Data Repository System, Phase III: Implementation and operation of the repository
The American Geological Institute's (AGI) National Geoscience Data Repository System (NGDRS) was initiated in response to the fact that billions of dollars worth of domestic geoscience data are in jeopardy of being irrevocably lost or destroyed as a consequence of the ongoing downsizing of the U.S. energy and minerals industry. Preservation and access to domestic geological and geophysical data are critical to the energy security and economic prosperity of the nation. There is a narrow window of opportunity to act before valuable data are destroyed. The data truly represent a national treasure and immediate steps must be taken to assure their preservation.
American Geological Institute
Improving Repository Performance by Using a Fill
a Fill a Fill Improving Repository Performance by Using a Fill The use of fills, semi-independent of the specific fill material, can improve package performance. The first barrier to prevent releases from the spent nuclear fuel is the waste package itself. The longer the waste package remains intact, the lower the ultimate releases from the spent nuclear fuel. In a typical waste package over half of the interior space is empty space. There are coolant channels in the spent fuel and square fuel assemblies can not fully fill a round waste package. After the package is buried, it will begin to corrode and the walls will thin. Rock falls may cause early failure of the waste package. However, if the package is full, it is more difficult to crush a full package and fail the exterior wall. The behavior of a waste package over time is similar to a soda can. Empty cans are easy to crush. Full, sealed cans are difficult to crush because the fluid inside supports the can.
LIFE Materials: Fuel Cycle and Repository Volume 11
The fusion-fission LIFE engine concept provides a path to a sustainable energy future based on safe, carbon-free nuclear power with minimal nuclear waste. The LIFE design ultimately offers many advantages over current and proposed nuclear energy technologies, and could well lead to a true worldwide nuclear energy renaissance. When compared with existing and other proposed future nuclear reactor designs, the LIFE engine exceeds alternatives in the most important measures of proliferation resistance and waste minimization. The engine needs no refueling during its lifetime. It requires no removal of fuel or fissile material generated in the LIFE engine. It leaves no weapons-attractive material at the end of life. Although there is certainly a need for additional work, all indications are that the 'back end' of the fuel cycle does not to raise any 'showstopper' issues for LIFE. Indeed, the LIFE concept has numerous benefits: (1) Per unit of electricity generated, LIFE engines would generate 20-30 times less waste (in terms of mass of heavy metal) requiring disposal in a HLW repository than does the current once-through fuel cycle. (2) Although there may be advanced fuel cycles that can compete with LIFE's low mass flow of heavy metal, all such systems require reprocessing, with attendant proliferation concerns; LIFE engines can do this without enrichment or reprocessing. Moreover, none of the advanced fuel cycles can match the low transuranic content of LIFE waste. (3) The specific thermal power of LIFE waste is initially higher than that of spent LWR fuel. Nevertheless, this higher thermal load can be managed using appropriate engineering features during an interim storage period, and could be accommodated in a Yucca-Mountain-like repository by appropriate 'staging' of the emplacement of waste packages during the operational period of the repository. The planned ventilation rates for Yucca Mountain would be sufficient for LIFE waste to meet the thermal constraints of the repository design. (4) A simple, but arguably conservative, estimate for the dose from a repository containing 63,000 MT of spent LIFE fuel would have similar performance to the currently planned Yucca Mountain Repository. This indicates that a properly designed 'LIFE Repository' would almost certainly meet the proposed Nuclear Regulatory Commission standards for dose to individuals, even though the waste in such a repository would have produced 20-30 times more generated electricity than the reference case for Yucca Mountain. The societal risk/benefit ratio for a LIFE repository would therefore be significantly better than for currently planned repositories for LWR fuel.
Shaw, H; Blink, J A
The NGDRS has facilitated 85% of cores, cuttings, and other data identified available for transfer to the public sector. Over 12 million linear feet of cores and cuttings, in addition to large numbers of paleontological samples and are now available for public use. To date, with industry contributions for program operations and data transfers, the NGDRS project has realized a 6.5 to 1 return on investment to Department of Energy funds. Large-scale transfers of seismic data have been evaluated, but based on the recommendation of the NGDRS steering committee, cores have been given priority because of the vast scale of the seismic data problem relative to the available funding. The rapidly changing industry conditions have required that the primary core and cuttings preservation strategy evolve as well. Additionally, the NGDRS clearinghouse is evaluating the viability of transferring seismic data covering the western shelf of the Florida Gulf Coast. AGI remains actively involved in working to realize the vision of the National Research Council's report of geoscience data preservation. GeoTrek has been ported to Linux and MySQL, ensuring a purely open-source version of the software. This effort is key in ensuring long-term viability of the software so that is can continue basic operation regardless of specific funding levels. Work has been on a major revision of GeoTrek, using the open-source MapServer project and its related MapScript language. This effort will address a number of key technology issues that appear to be rising for 2003, including the discontinuation of the use of Java in future Microsoft operating systems. The recent donation of BPAmoco's Houston core facility to the Texas Bureau of Economic Geology has provided substantial short-term relief of the space constraints for public repository space.
Monte Carlo simulations for generic granite repository studies
In a collaborative study between Los Alamos National Laboratory (LANL) and Sandia National Laboratories (SNL) for the DOE-NE Office of Fuel Cycle Technologies Used Fuel Disposition (UFD) Campaign project, we have conducted preliminary system-level analyses to support the development of a long-term strategy for geologic disposal of high-level radioactive waste. A general modeling framework consisting of a near- and a far-field submodel for a granite GDSE was developed. A representative far-field transport model for a generic granite repository was merged with an integrated systems (GoldSim) near-field model. Integrated Monte Carlo model runs with the combined near- and farfield transport models were performed, and the parameter sensitivities were evaluated for the combined system. In addition, a sub-set of radionuclides that are potentially important to repository performance were identified and evaluated for a series of model runs. The analyses were conducted with different waste inventory scenarios. Analyses were also conducted for different repository radionuelide release scenarios. While the results to date are for a generic granite repository, the work establishes the method to be used in the future to provide guidance on the development of strategy for long-term disposal of high-level radioactive waste in a granite repository.
Chu, Shaoping [Los Alamos National Laboratory; Lee, Joon H [SNL; Wang, Yifeng [SNL
Criticality issues with highly enriched fuels in a repository environment
This paper presents preliminary analysis of a volcanic tuff repository containing a combination of low enrichment commercial spent nuclear fuels (SNF) and DOE-owned SNF packages. These SNFs were analyzed with respect to their criticality risks. Disposal of SNF packages containing significant fissile mass within a geologic repository must comply with current regulations relative to criticality safety during transportation and handling within operational facilities. However, once the repository is closed, the double contingency credits for criticality safety are subject to unremediable degradation, (e.g., water intrusion, continued presence of neutron absorbers in proximity to fissile material, and fissile material reconfiguration). The work presented in this paper focused on two attributes of criticality in a volcanic tuff repository for near-field and far-field scenarios: (1) scenario conditions necessary to have a criticality, and (2) consequences of a nuclear excursion that are components of risk. All criticality consequences are dependent upon eventual water intrusion into the repository and subsequent breach of the disposal package. Key criticality parameters necessary for a critical assembly are: (1) adequate thermal fissile mass, (2) adequate concentration of fissile material, (3) separation of neutron poison from fissile materials, and (4) sufficient neutron moderation (expressed in units of moderator to fissile atom ratios). Key results from this study indicated that the total energies released during a single excursion are minimal (comparable to those released in previous solution accidents), and the maximum frequency of occurrence is bounded by the saturation and temperature recycle times, thus resulting in small criticality risks.
Taylor, L.L. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States); Sanchez, L.C.; Rath, J.S. [Sandia National Labs., Albuquerque, NM (United States)
Proceedings of the scientific visit on crystalline rock repository development.
A scientific visit on Crystalline Rock Repository Development was held in the Czech Republic on September 24-27, 2012. The visit was hosted by the Czech Radioactive Waste Repository Authority (RAWRA), co-hosted by Sandia National Laboratories (SNL), and supported by the International Atomic Energy Agency (IAEA). The purpose of the visit was to promote technical information exchange between participants from countries engaged in the investigation and exploration of crystalline rock for the eventual construction of nuclear waste repositories. The visit was designed especially for participants of countries that have recently commenced (or recommenced) national repository programmes in crystalline host rock formations. Discussion topics included repository programme development, site screening and selection, site characterization, disposal concepts in crystalline host rock, regulatory frameworks, and safety assessment methodology. Interest was surveyed in establishing a %E2%80%9Cclub,%E2%80%9D the mission of which would be to identify and address the various technical challenges that confront the disposal of radioactive waste in crystalline rock environments. The idea of a second scientific visit to be held one year later in another host country received popular support. The visit concluded with a trip to the countryside south of Prague where participants were treated to a tour of the laboratory and underground facilities of the Josef Regional Underground Research Centre.
Mariner, Paul E.; Hardin, Ernest L.; Miksova, Jitka [RAWRA, Czech Republic
Salt Repository Project shaft design guide: Revision 0
The Salt Repository Project (SRP) Shaft Design Guide (SDG) and the accompanying SRP Input to Seismic Design define the basic approach for developing appropriate shaft designs for a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. The SDG is based on current mining industry standards and practices enhanced to meet the special needs of an underground nuclear waste repository. It provides a common approach for design of both the exploratory and repository shafts. The SDG defines shaft lining and material concepts and presents methods for calculating the loads and displacements that will be imposed on lining structures. It also presents the methodology and formulae for sizing lining components. The SDG directs the shaft designer to sources of geoscience and seismic design data for the Deaf Smith County, Texas repository site. In addition, the SDG describes methods for confirming shaft lining design by means of computer analysis, and it discusses performance monitoring needs that must be considered in the design. 113 refs., 18 figs., 14 tabs.
Not Available
Transportation analysis for the concept of regional repositories
Over the past several years, planning associated with the National Waste Terminal Storage (NWTS) program assumed the use of one or two large, centrally located repository facilities. Recently, an alternative approach has been proposed which consists of the use of multiple, smaller regional repositories. In this report, several regional concepts were studied and the transportation requirements for the shipment of spent fuel to the regional repositories were estimated. In general, the transportation requirements decrease as the number of repositories increase. However, as far as transportation is concerned, the point of diminishing returns is reached at approximately one repository in each of three to four regions. Additional savings beyond this point are small. A series of sensitivity studies is also included to demonstrate the impact on the total transportation requirements of varying cask capacity, rail speed, or truck speed. Since most of the projected fuel shipments are to be made by rail, varying the capacity of the rail cask or varying average rail transport speed will have a major effect on overall transportation requirements.
Joy, D.S.; Hudson, B.J.
Reactive transport modelling of the interaction of fission product ground contamination with alkaline and cementitious leachates
The fission products Cs-137 and Sr-90 are amongst the most common radionuclides occurring in ground contamination at the UK civil nuclear sites. Such contamination is often associated with alkaline liquids and the mobility of these fission products may be affected by these chemical conditions. Similar geochemical effects may also result from cementitious leachate associated with building foundations and the use of grouts to remediate ground contamination. The behaviour of fission products in these scenarios is a complex interaction of hydrogeological and geochemical processes. A suite of modelling tools have been developed to investigate the behaviour of a radioactive plume containing Cs and Sr. Firstly the effects of sorption due to cementitious groundwater is modelled using PHREEQC. This chemical model is then incorporated into PHAST for the 3-D reactive solute transport modeling. Results are presented for a generic scenario including features and processes that are likely to be relevant to a number of civil UK nuclear sites. Initial results show that modelling can be a very cost-effective means to study the complex hydrogeological and geochemical processes involved. Modelling can help predict the mobility of contaminants in a range of site end point scenarios, and in assessing the consequences of decommissioning activities. (authors)
Kwong, S.; Small, J. [Nexia Solutions Ltd, The British Technology Centre, Sellafield, Seascale, CA20 1PG (United Kingdom)
Anaerobic treatment of sludge from a nitrification-denitrification landfill leachate plant
The viability of anaerobic digestion of sludge from a MSW landfill leachate treatment plant, with COD values ranging between 15,000 and 19,400 mg O{sub 2} dm{sup -3}, in an upflow anaerobic sludge blanket reactor was studied. The reactor employed had a useful capacity of 9 l, operating at mesophilic temperature. Start-up of the reactor was carried out in different steps, beginning with diluted sludge and progressively increasing the amount of sludge fed into the reactor. The study was carried out over a period of 7 months. Different amounts of methanol were added to the feed, ranging between 6.75 and 1 cm{sup 3} dm{sup -3} of feed in order to favour the growth of methanogenic flora. The achieved biodegradation of the sludge using an upflow anaerobic sludge blanket Reactor was very high for an HRT of 9 days, obtaining decreases in COD of 84-87% by the end of the process. Purging of the digested sludge represented {approx}16% of the volume of the treated sludge.
Maranon, E. [Chemical and Environmental Engineering Department, Higher Polytechnic School of Engineering, University of Oviedo, Campus of Viesques, 33204 Gijon (Spain)]. E-mail: firstname.lastname@example.com; Castrillon, L. [Chemical and Environmental Engineering Department, Higher Polytechnic School of Engineering, University of Oviedo, Campus of Viesques, 33204 Gijon (Spain); Fernandez, Y. [Chemical and Environmental Engineering Department, Higher Polytechnic School of Engineering, University of Oviedo, Campus of Viesques, 33204 Gijon (Spain); Fernandez, E. [COGERSA, 33697 Serin, Gijon (Spain)
Stochastic modelling of landfill leachate and biogas production incorporating waste heterogeneity. Model formulation and uncertainty analysis
A mathematical model simulating the hydrological and biochemical processes occurring in landfilled waste is presented and demonstrated. The model combines biochemical and hydrological models into an integrated representation of the landfill environment. Waste decomposition is modelled using traditional biochemical waste decomposition pathways combined with a simplified methodology for representing the rate of decomposition. Water flow through the waste is represented using a statistical velocity model capable of representing the effects of waste heterogeneity on leachate flow through the waste. Given the limitations in data capture from landfill sites, significant emphasis is placed on improving parameter identification and reducing parameter requirements. A sensitivity analysis is performed, highlighting the model's response to changes in input variables. A model test run is also presented, demonstrating the model capabilities. A parameter perturbation model sensitivity analysis was also performed. This has been able to show that although the model is sensitive to certain key parameters, its overall intuitive response provides a good basis for making reasonable predictions of the future state of the landfill system. Finally, due to the high uncertainty associated with landfill data, a tool for handling input data uncertainty is incorporated in the model's structure. It is concluded that the model can be used as a reasonable tool for modelling landfill processes and that further work should be undertaken to assess the model's performance.
Zacharof, A.I.; Butler, A.P
Environmental Assessment for Actinide Chemistry and Repository Science
questions on the Environmental Assessment for Actinide Chemistry and Repository Science Laboratory, email firstname.lastname@example.com or call (505) 234-7349. questions on the Environmental Assessment for Actinide Chemistry and Repository Science Laboratory, email firstname.lastname@example.com or call (505) 234-7349. Environmental Assessment for Actinide Chemistry and Repository Science Laboratory Final - January, 2006 This document has been provided to you in PDF format. Please install Adobe Acrobat Reader before accessing these documents. Some of the Chapters containing complex graphics have been split into multiple parts to allow for more detail in the graphics and ease in downloading. Cover Sheet, Table of Contents, List of Tables, List of Figures, and Acronyms and Abbreviations Chapter 1 - Introduction and Statement of Purpose and Need Chapter 2 - Proposed Action and Alternatives Chapter 3 - Existing Environment
Repository Reference Disposal Concepts and Thermal Load Management Analysis
Repository Reference Disposal Concepts and Thermal Load Management Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clay/shale, salt, crystalline, other sedimentary), and the engineering concept of operations (range of generic operational concepts examined). Two major categories for waste package emplacement modes are identified: 1) "open" where extended ventilation can remove heat for many years following waste emplacement underground; and 2) "enclosed" modes for clay/shale and salt media where waste packages are emplaced in direct or close contact with natural or engineered materials which may have temperature limits that constrain thermal
Long-term Repository Benefits of Using Cermet Waste Packages
Long-Term Benefits Long-Term Benefits Long-term Repository Benefits of Using Cermet Waste Packages A cermet waste package may improve the long-term performance of the YM repository by two mechanisms: reducing (1) the potential for nuclear criticality in the repository and (2) the long-term release rate of radionuclides from the waste package. In the natural environment, the centers of uranium ore deposits have remained intact for very long time periods while the outer edges of the ore deposit have degraded. A cermet waste package may operate in the same way. The sacrificial, slow degradation of the waste package and the DU oxide protects the SNF uranium dioxide in the interior of the package long after the package has failed. Page 2 of 4 Follow the link below to learn more about Cermets:
Final Supplemental Environmental Impact Statement for a Geologic Repository
Supplemental Environmental Impact Statement for a Geologic Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada - Nevada Rail Transportation CorridorDOE/EIS-0250F-S2andFinal Envir Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada - Nevada Rail Transportation CorridorDOE/EIS-0250F-S2andFinal Envir This part of the Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada -- Nevada Rail Transportation Corridor (DOE/EIS-0250F-S2) (Nevada Rail Corridor SEIS)
- Nevada Rail - Nevada Rail Transportation Corridor DOE/EIS-0250F-S2 and Final Env Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada -- Nevada Rail Transportation Corridor DOE/EIS-0250F-S2 and Final Env The Summary of the Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada -- Nevada Rail Transportation Corridor DOE/EIS-0250F-S2 and Final Environmental Impact Statement for a Rail Alignment for the Construction and Operation of a Railroad in Nevada to a Geologic Repository at Yucca Mountain, Nye County,
Improving Repository Performance by Using DU Dioxide Fill
DU Dioxide Fill DU Dioxide Fill Improving Repository Performance by Using DU Dioxide Fill Fills may improve repository performance by acting as sacrificial materials, which delay the degradation of SNF uranium dioxide. Because fill and SNF have the same chemical form of uranium (uranium dioxide), the DU dioxide in a repository is the only fill which has the same behavior as that of the SNF. In the natural environment, some uranium ore deposits have remained intact for very long periods of time. The outer parts of the ore deposit degrade while the inner parts of the deposit are protected. The same approach is proposed herein for protecting SNF. The application could use half or more of the DU inventory in the United States. Behavior of Uranium and Potential Behavior of a Waste Package with SNF and Fill
Performance Assessment Strategy Plan for the Geologic Repository Program
Performance assessment is a major constituent of the program being conducted by the US Department of Energy (DOE) to develop a geologic repository. Performance assessment is the set of activities needed for quantitative evaluations to assess compliance with the performance requirements in the regulations for a geologic repository and to support the development of the repository. The strategy for these evaluations has been documented in the Performance Assessment Strategy Plan (DOE, 1989). The implementation of the performance assessment strategy is defined in this document. This paper discusses the scope and objectives of the implementation plan, the relationship of the plan to other program plans, summarizes the performance assessment areas and the integrated strategy of the performance assessment program. 1 fig., 3 tabs.
Waterproofing and Strengthening Volcanic Tuff in Waste Repositories
Waste repositories from surface trenches and shafts at Los Alamos to drilled tunnels at Yucca Mountain are being built in volcanic Tuff, a soft compacted material that is permeable to water and air. US Department of Energy documents on repository design identify the primary design goal of 'preventing water from reaching the waste canisters, dissolving the canisters and carrying the radioactive waste particles away from the repository'. Designers expect to achieve this by use of multiple barriers along with careful placement of the repository both well above the water table and well above the ground level in a mountain. Though repositories are located in areas that have a historically dry climate to minimize the impact of rainfall infiltration, global warming phenomena may have the potential to alter regional climate patterns - potentially leading to higher infiltration rates. Conventional methods of sealing fractures within volcanic tuff may not be sufficiently robust or long lived to isolate a repository shaft from water for the required duration. A new grouting technology based on molten wax shows significant promise for producing the kind of long term sealing performance required. Molten wax is capable of permeating a significant distance through volcanic tuff, as well as sealing fractures by permeation that is thermally dependent instead of chemically or time dependent. The wax wicks into and saturates tuff even if no fractures are present, but penetrates and fills only the heated area. Heated portions of the rock fill like a vessel. The taffy-like wax has been shown to waterproof the tuff, and significantly increase its resistance to fracture. This wax was used in 2004 for grouting of buried radioactive beryllium waste at the Idaho National Laboratory, chiefly to stop the water based corrosion reactions of the waste. The thermoplastic material contains no water and does not dry out or change with age. Recent studies indicate that this kind of wax material may be inherently resistant to bio-degradation. (authors)
Carter, E.E.; Carter, P.E. [Technologies Co, Texas (United States); Cooper, D.C. [Ph.D. Idaho National Laboratory, Idaho Falls, ID (United States)
Traffic data repository at the WIDE project
It becomes increasingly important for both network researchers and operators to know the trend of network traffic and to find anomaly in their network traffic. This paper describes an on-going effort within the WIDE project to collect a set of free tools ...
Kenjiro Cho; Koushirou Mitsuya; Akira Kato
Double Diffusive Natural Convection in a Nuclear Waste Repository
In this study, we conduct a two-dimensional numerical analysis of double diffusive natural convection in an emplacement drift for a nuclear waste repository. In-drift heat and moisture transport is driven by combined thermal- and compositional-induced buoyancy forces. Numerical results demonstrate buoyancy-driven convective flow patterns and configurations during both repository heat-up and cool-down phases. It is also shown that boundary conditions, particularly on the drip-shield surface, have strong impacts on the in-drift convective flow and transport.
Y. Hao; J. Nitao; T.A. Buscheck; Y. Sun
Data collection
0.054; wR factor = 0.127; data-to-parameter ratio = 16.9. The title compound, C22H17NO, is a novel Schiff base synthesized via a condensation reaction between 9-anthracenecarboxaldehyde and 2-amino-p-cresol. The asymmetric unit contains two independent molecules that are joined by an O� H OH hydrogen bond. An intramolecular O�H N hydrogen bond occurs in each molecule.-stacking about inversion centers was observed between adjacent phenol rings [centroid�centroid distance = 3.850 (2) A ? ] and adjacent anthracene rings [centroid�centroid distance = 3.834 (2) A ?]. The C�N C�C torsion angles between the phenol and anthracene rings are close to 180 with values of 174.06 (15) and 179.85 (14). Related literature For related structures, see: De et al. (2008); �nver et al. (2009). For bond-length data, see: Allen et al. (1987). For background to the use of luminescent metal complexes formed by Schiff bases in light emitting diode construction and solar energy collection, see: Liao et al. (2009); Mak et al. (2009).
Andr�s Villalp; A Frank R. Fronczek B; Isovitsch A; Triclinic P; Mo K Radiation
Nuclear waste repository transparency technology test bed demonstrations at WIPP
Secretary of Energy, Bill Richardson, has stated that one of the nuclear waste legacy issues is ``The challenge of managing the fuel cycle's back end and assuring the safe use of nuclear power.'' Waste management (i.e., the back end) is a domestic and international issue that must be addressed. A key tool in gaining acceptance of nuclear waste repository technologies is transparency. Transparency provides information to outside parties for independent assessment of safety, security, and legitimate use of materials. Transparency is a combination of technologies and processes that apply to all elements of the development, operation, and closure of a repository system. A test bed for nuclear repository transparency technologies has been proposed to develop a broad-based set of concepts and strategies for transparency monitoring of nuclear materials at the back end of the fuel/weapons cycle. WIPP is the world's first complete geologic repository system for nuclear materials at the back end of the cycle. While it is understood that WIPP does not currently require this type of transparency, this repository has been proposed as realistic demonstration site to generate and test ideas, methods, and technologies about what transparency may entail at the back end of the nuclear materials cycle, and which could be applicable to other international repository developments. An integrated set of transparency demonstrations was developed and deployed during the summer, and fall of 1999 as a proof-of-concept of the repository transparency technology concept. These demonstrations also provided valuable experience and insight into the implementation of future transparency technology development and application. These demonstrations included: Container Monitoring Rocky Flats to WIPP; Underground Container Monitoring; Real-Time Radiation and Environmental Monitoring; Integrated level of confidence in the system and information provided. As the world's only operating deep geologic repository, the Waste Isolation Pilot Plant (WIPP) offers a unique opportunity to serve as an international cooperative test bed for developing and demonstrating technologies and processes in a fully operational repository system setting. To address the substantial national security implications for the US resulting from the lack of integrated, transparent management and disposition of nuclear materials at the back-end of the nuclear fuel and weapons cycles, it is proposed that WIPP be used as a test bed to develop and demonstrate technologies that will enable the transparent and proliferation-resistant geologic isolation of nuclear materials. The objectives of this initiative are to: (1) enhance public confidence in safe, secure geologic isolation of nuclear materials; (2) develop, test, and demonstrate transparency measures and technologies for the back-end of nuclear fuel cycle; and (3) foster international collaborations leading to workable, effective, globally-accepted standards for the transparent monitoring of geological repositories for nuclear materials. Test-bed activities include: development and testing of monitoring measures and technologies; international demonstration experiments; transparency workshops; visiting scientist exchanges; and educational outreach. These activities are proposed to be managed by the Department of Energy/Carlsbad Area Office (DOE/CAO) as part of The Center for Applied Repository and Underground Studies (CARUS).
Using semantic templates to study vulnerabilities recorded in large software repositories
Software repositories are rich sources of information about vulnerabilities that occur during a product's lifecycle. Although available, such information is scattered across numerous databases. Furthermore, in large software repositories, a single vulnerability ... Keywords: CVE, CWE, buffer overflow, fix patterns, ontology, semantic template, software repository, vulnerability
Yan Wu; Robin A. Gandhi; Harvey Siy
The Choquet integral analytic hierarchy process for radwaste repository site selection in Taiwan
The Radwaste Repository Site Selection In Taiwan have received considerable continuous improvement by the fuzzy Choquet integral aggregation operator. It allows expressing scenario that are either hosted externally by the repository safety assessment ... Keywords: AHP method, choquet integral, radioactive waste repository
Chen Lin
Environmental effects on corrosion in the Tuff repository
Cortest Columbus is investigating the long-term performance of container materials used for high-level waste packages as part of the information needed by the Nuclear Regulatory Commission to assess the Department of Energy`s application to construct a geologic repository for high-level radioactive waste. The scope of work consists of employing short-term techniques, to examine a wide range of possible failure modes. Long-term tests are being used to verify and further examine specific failure modes identified as important by the short-term studies. The original focus of the program was on the salt repository but the emphasis was shifted to the Tuff repository. This report summarizes the results of a literature survey performed under Task 1 of the program. The survey focuses on the influence of environmental variables on the corrosion behavior of candidate container materials for the Tuff repository. Environmental variables considered include: radiation, thermal and microbial effects. 80 refs., 44 figs., 44 tabs.
Beavers, J.A.; Thompson, N.G. [Cortest Columbus, Inc., OH (USA)
(Re)Use in public scientific workflow repositories
Scientific workflows help in designing, managing, monitoring, and executing in-silico experiments. Since scientific workflows often are complex, sharing them by means of public workflow repositories has become an important issue for the community. However, ... Keywords: scientific workflows, similarity measures, workflow reuse
Johannes Starlinger; Sarah Cohen-Boulakia; Ulf Leser
Graphical user interface (GUI) testing: Systematic mapping and repository
Context: GUI testing is system testing of a software that has a graphical-user interface (GUI) front-end. Because system testing entails that the entire software system, including the user interface, be tested as a whole, during GUI testing, test cases-modeled ... Keywords: Bibliometrics, GUI application, Paper repository, Systematic mapping, Testing
Ishan Banerjee, Bao Nguyen, Vahid Garousi, Atif Memon
Pathways core: a data model for cross-repository services
As part of the NSF-funded Pathways project, we have created an interoperable data model to facilitate object re-use and a broad spectrum of cross-repository services. The resulting Pathways Core data model is designed to be lightweight to implement, ... Keywords: data model, interoperability, scholarly communication
Jeroen Bekaert; Xiaoming Liu; Herbert Van de Sompel; Carl Lagoze; Sandy Payette; Simeon Warner
Characterization of Actinides in Simulated Alkaline Tank Waste Sludges and Leachates
Removal of waste-limiting components of sludge (Al, Cr, S, P) in underground tanks at Hanford by treatment with concentrated alkali has proven less efficacious for Al and Cr removal than had been hoped. More aggressive treatments of sludges, for example, contact with oxidants targeting Cr(III), have been tested in a limited number of samples and found to improve leaching efficiency for Cr. Oxidative alkaline leaching can be expected to have at best a secondary influence on the mobilization of Al. Our earlier explorations of Al leaching from sludge simulants indicated acidic and complexometric leaching can improve Al dissolution. Unfortunately, treatments of sludge samples with oxidative alkaline, acidic or complexing leachates produce conditions under which normally insoluble actinide ions (e.g., Am3+, Pu4+, Np4+) can be mobilized to the solution phase. Few experimental or meaningful theoretical studies of actinide chemistry in strongly alkaline, strongly oxidizing solutions have been completed. Unfortunately, extrapolation of the more abundant acid phase thermodynamic data to these radically different conditions provides limited reliable guidance for predicting actinide speciation in highly salted alkaline solutions. In this project, we are investigating the fundamental chemistry of actinides and important sludge components in sludge simulants and supernatants under representative oxidative leaching conditions. We are examining the potential impact of acidic or complexometric leaching with concurrent secondary separations on Al removal from sludges. Finally, a portion of our research is directed at the control of polyvalent anions (SO4=, CrO4=, PO43-) in waste streams destined for vitrification. Our primary objective is to provide adequate insight into actinide behavior under these conditions to enable prudent decision making as tank waste treatment protocols develop. We expect to identify those components of sludges that are likely to be problematic in the application of oxidative, acidic, and complexometric leaching protocols.
Nash, Kenneth L.
Anaerobic digestion of pressed off leachate from the organic fraction of municipal solid waste
A highly polluted liquid ('press water') was obtained from the pressing facility for the organic fraction of municipal solid waste in a composting plant. Methane productivity of the squeezed-off leachate was investigated in batch assays. To assess the technical feasibility of 'press water' as a substrate for anaerobic digestion, a laboratory-scale glass column reactor was operated semi-continuously at 37 {sup o}C. A high methane productivity of 270 m{sup -3} CH{sub 4} ton{sup -1} COD{sub added} or 490 m{sup -3} CH{sub 4} ton{sup -1} VS{sub added} was achieved in the batch experiment. The semi-continuously run laboratory-scale reactor was initially operated at an organic loading rate of 10.7 kg COD m{sup -3} d{sup -1}. The loading was increased to finally 27.7 kg COD m{sup -3} d{sup -1}, corresponding to a reduction of the hydraulic retention time from initially 20 to finally 7.7 days. During the digestion, a stable elimination of organic material (measured as COD elimination) of approximately 60% was achieved. Linearly with the increment of the OLR, the volumetric methane production of the reactor increased from 2.6 m{sup 3} m{sub reactor}{sup -3} d{sup -1} to 7.1 m{sup 3} m{sub reactor}{sup -3} d{sup -1}. The results indicated that 'press water' from the organic fraction of municipal solid waste was a suitable substrate for anaerobic digestion which gave a high biogas yield even at very high loading rates.
Nayono, Satoto E. [Department of Civil Engineering, Yogyakarta State University, Campus UNY Karangmalang Yogyakarta 55281 (Indonesia); Institute of Biology for Engineers and Biotechnology of Wastewater, University of Karlsruhe, Am Fasanengarten, 76131 Karlsruhe (Germany); Winter, Josef, E-mail: firstname.lastname@example.com [Institute of Biology for Engineers and Biotechnology of Wastewater, University of Karlsruhe, Am Fasanengarten, 76131 Karlsruhe (Germany); Gallert, Claudia [Institute of Biology for Engineers and Biotechnology of Wastewater, University of Karlsruhe, Am Fasanengarten, 76131 Karlsruhe (Germany)
Nevada potential repository preliminary transportation strategy Study 2. Volume 1
The objectives of this study were to build on the findings of the Nevada Potential Repository Preliminary Transportation Strategy Study 1 (CRWMS M&O 1995b), and to provide additional information for input to the repository environmental impact statement (EIS) process. In addition, this study supported the future selection of a preferred rail corridor and/or heavy haul route based on defensible data, methods, and analyses. Study research did not consider proposed legislation. Planning was conducted according to the Civilian Radioactive Waste Management Program Plan (DOE 1994a). The specific objectives of Study 2 were to: eliminate or reduce data gaps, inconsistencies, and uncertainties, and strengthen the analysis performed in Study 1; develop a preliminary list of rail route evaluation criteria that could be used to solicit input from stakeholders during scoping meetings. The evaluation criteria will be revised based on comments received during scoping; restrict and refine the width of the four rail corridors identified in Study 1 to five miles or less, based on land use constraints and engineering criteria identified and established in Study 2; evaluate national-level effects of routing spent nuclear fuel and high-level waste to the four identified branch lines, including the effects of routing through or avoiding Las Vegas; continue to gather published land use information and environmental data to support the repository EIS; continue to evaluate heavy haul truck transport over three existing routes as an alternative to rail and provide sufficient information to support the repository EIS process; and evaluate secondary uses for rail (passenger use, repository construction, shared use).
A Summary of Properties Used to Evaluate INEEL Calcine Disposal in the Yucca Mountain Repository
To support evaluations of the direct disposal of Idaho National Engineering and Environmental Laboratory calcines to the repository at Yucca Mountain, an evaluation of the performance of the calcine in the repository environment must be performed. This type of evaluation demonstrates, through computer modeling and analysis, the impact the calcine would have on the ability of the repository to perform its function of containment of materials during the repository lifetime. This report discusses parameters that were used in the scoping evaluation conducted in FY 2003. It provides nominal values for the parameters, with explanation of the source of the values, and how the values were modified for use in repository analysis activities.
Dahl, C.A.
DOE Hydrogen Analysis Repository: Biogas Resources Characterization
Biogas Resources Characterization Biogas Resources Characterization Project Summary Full Title: Biogas Resources Characterization Project ID: 259 Principal Investigator: Ali Jalalzadeh-Azar Brief Description: This project intends to develop a cost-analysis tool based on the H2A Production model, collect global information system (GIS) / cost data, and perform techno-economic analyses of upgrading biogas and utilizing the resulting bio-methane. Keywords: Biogas; Bio-methane; Landfill; Dairy farm; Sewage treatment plant; Fuel cell Purpose Fuel cells operating on bio-methane or on hydrogen derived from bio-methane can mitigate energy and environmental issues and provide an opportunity for their commercialization. This project can provide valuable insights and information to the stakeholders-utilities, municipalities, and policy
Sorption of 237Np by UO2 under Repository Conditions
237 Np by UO 2 under Repository Conditions M. Jonathan Haire E. V. Zakharova T. V. Kazakovskaya Oak Ridge National Laboratory Institute of Physical Chemistry Institute of Experimental Physics Oak Ridge, Tennessee 37831-6166 Moscow, Russia, 117915 Sarov, Russia, 607190 Phone: (865) 574-7141 Phone: 7 095 335 1742 Phone: 7 42796 73369 e-mail: email@example.com e-mail: email@example.com e-mail: email@example.com Abstract - The primary radioisotope contributor to the calculated long-term radiation dose to the public at the Yucca Mountain spent nuclear fuel (SNF) repository site boundary is neptunium-237 ( 237 Np). Russian experiments have shown that Np(V) and Np(IV) are sorbed onto UO 2 . If Np were sorbed by UO 2 in spent fuel rather than being transported to the site
Nevada Rail Nevada Rail Transportation Corridor DOE/EIS-0250F-S2 and Final En Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada - Nevada Rail Transportation Corridor DOE/EIS-0250F-S2 and Final En Proposed Action: To determine a rail alignment within a rail corridor in which to construct and operate a railroad to transport spent nuclear fuel, high-level radioactive waste, and other materials from an existing railroad in Nevada to a repository at Yucca Mountain, Nye County, Nevada. The Proposed Action includes the construction of railroad construction and operations support facilities. This Rail Alignment EIS analyzes two alternatives that would implement the Proposed Action: the Caliente rail
and could possibly serve as a repository for
and could possibly serve as a repository for and could possibly serve as a repository for captured CO 2 emissions. The formation is covered by layers of low permeability rock and possesses several properties that are conducive to CO 2 storage, such as the appropriate depth, thickness, porosity, and permeability. Prior to drilling the test well, MRCSP conducted a seismic survey at the site and obtained necessary permits for the injection test from the U.S. Environmental Protection Agency (EPA) and the Kentucky Division of Oil and Gas. Following the permitting process, the researchers injected clean brine in order to determine formation properties like the maximum injection rate and then injected approximately 1,000 metric tons of CO 2 in two, 500-meter-ton steps. The injection rate, pressure, temperature,
Expected brine movement at potential nuclear waste repository salt sites
The BRINEMIG brine migration code predicts rates and quantities of brine migration to a waste package emplaced in a high-level nuclear waste repository in salt. The BRINEMIG code is an explicit time-marching finite-difference code that solves a mass balance equation and uses the Jenks equation to predict velocities of brine migration. Predictions were made for the seven potentially acceptable salt sites under consideration as locations for the first US high-level nuclear waste repository. Predicted total quantities of accumulated brine were on the order of 1 m/sup 3/ brine per waste package or less. Less brine accumulation is expected at domal salt sites because of the lower initial moisture contents relative to bedded salt sites. Less total accumulation of brine is predicted for spent fuel than for commercial high-level waste because of the lower temperatures generated by spent fuel. 11 refs., 36 figs., 29 tabs.
McCauley, V.S.; Raines, G.E.
Transuranic Burning Issues Related to a Second Geologic Repository
This report defines issues that need to be addressed by a development program recently initiated to establish the viability of a transuranic burning concept application that would achieve a substantial delay to the need date for a second geologic repository. The visualized transuranic burning concept application is one in which spent fuel created after a date in the 2010 time frame or later would be processed and the separated plutonium used to start up liquid metal reactors (LMRs).
National Geoscience Data Repository System: Phase 2 final report
The American Geological Institute (AGI) has completed Phase 2 of a project to establish a National Geoscience Data Repository System (NGDRS). The project`s primary objectives are to preserve geoscience data in jeopardy of being destroyed and to make that data available to those who have a need to use it in future investigations. These data are available for donation to the public as a result of the downsizing that has occurred in the major petroleum and mining companies in the US for the past decade. In recent years, these companies have consolidated domestic operations, sold many of their domestic properties and relinquished many of their leases. The scientific data associated with those properties are no longer considered to be useful assets and are consequently in danger of being lost forever. The national repository project will make many of these data available to the geoscience community for the first time. Phase 2 encompasses the establishment of standards for indexing and cataloging of geoscience data and determination of the costs of transferring data from the private sector to public-sector data repositories. Pilot projects evaluated the feasibility of the project for transfer of different data types and creation of a Web-based metadata supercatalog and browser. Also as part of the project, a national directory of geoscience data repositories was compiled to assess what data are currently available in existing facilities. The next step, Phase 3, will focus on the initiation of transfer of geoscience data from the private sector to the public domain and development of the web-based Geotrek metadata supercatalog.
Current Status of The Romanian National Deep Geological Repository Program
Construction of a deep geological repository is a very demanding and costly task. By now, countries that have Candu reactors, have not processed the spent fuel passing to the interim storage as a preliminary step of final disposal within the nuclear fuel cycle back-end. Romania, in comparison to other nations, represents a rather small territory, with high population density, wherein the geological formation areas with radioactive waste storage potential are limited and restricted not only from the point of view of the selection criteria due to the rocks natural characteristics, but also from the point of view of their involvement in social and economical activities. In the framework of the national R and D Programs, series of 'Map investigations' have been made regarding the selection and preliminary characterization of the host geological formation for the nation's spent fuel deep geological repository. The fact that Romania has many deposits of natural gas, oil, ore and geothermal water, and intensively utilizes soil and also is very forested, cause some of the apparent acceptable sites to be rejected in the subsequent analysis. Currently, according to the Law on the spent fuel and radioactive waste management, including disposal, The National Agency of Radioactive Waste is responsible and coordinates the national strategy in the field and, subsequently, further actions will be decided. The Romanian National Strategy, approved in 2004, projects the operation of a deep geological repository to begin in 2055. (authors)
Radu, M.; Nicolae, R.; Nicolae, D. [Center of Technology and Engineering for Nuclear Objectives (CITON), ILFOV County (Romania)
Microalgae Culture Collection, 1985-1986
The SERI Microalgae Culture Collection was established in support of the US Department of Energy's Biofuels Program to provide a repository for strains identified or developed for mass culture biomass production and to make these strains readily available to the research community. The strains in the collection have been selected for their potential in biomass fuel applications, and many produce significant quantities of cellular storage lipids. The Culture Collection Catalog lists 20 strains of ten species. Many have been tested in outdoor mass culture systems, and several have demonstrated excellent performance as biomass producers, with yields of up to 40 grams of organic matter per square meter per day. The majority of strains added to the collection this year have been isolated from inland saline waters, although marine species are included as well. We believe that the strains in this collection can provide a source of extremely useful organisms, both for laboratory experimentation and for mass culture research. 98 refs., 31 figs., 52 tabs.
Proceedings of 3rd US/German Workshop on Salt Repository Research, Design,
Proceedings of 3rd US/German Workshop on Salt Repository Research, Proceedings of 3rd US/German Workshop on Salt Repository Research, Design, and Operation Proceedings of 3rd US/German Workshop on Salt Repository Research, Design, and Operation The 3rd U.S./German Workshop on Salt Repository Research, Design and Operation was held in Albuquerque and Carlsbad, New Mexico on October 8-11, 2012. Approximately 60 salt research scientists from Germany and the United States met to discuss repository science state of the art. Workshop topics included: 1) Safety case for heat-generating waste disposal in salt; 2) Benchmark modeling in preparation for thermomechanical field-scale tests; and 3) Reconsolidation of granular salt. Collaboration being pursued by U.S. and German salt repository researchers is presented in the report.
EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and
EIS-0250: Geologic Repository for the Disposal of Spent Nuclear EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada Summary This EIS analyzes DOE's proposed action to construct, operate, monitor, and eventually close a geologic repository at Yucca Mountain for the disposal of spent nuclear fuel and high-level radioactive waste. The EIS evaluates not only impacts from constructing, operating, monitoring, and closing a repository, but also from transporting the materials from 72 commercial and 4 DOE sites to the Yucca Mountain repository site in Nye County, Nevada. Public Comment Opportunities
Preliminary analyses of scenarios for potential human interference for repositories in three salt formations
Preliminary analyses of scenarios for human interference with the performance of a radioactive waste repository in a deep salt formation are presented. The following scenarios are analyzed: (1) the U-Tube Connection Scenario involving multiple connections between the repository and the overlying aquifer system; (2) the Single Borehole Intrusion Scenario involving penetration of the repository by an exploratory borehole that simultaneously connects the repository with overlying and underlying aquifers; and (3) the Pressure Release Scenario involving inflow of water to saturate any void space in the repository prior to creep closure with subsequent release under near lithostatic pressures following creep closure. The methodology to evaluate repository performance in these scenarios is described and this methodology is applied to reference systems in three candidate formations: bedded salt in the Palo Duro Basin, Texas; bedded salt in the Paradox Basin, Utah; and the Richton Salt Dome, Mississippi, of the Gulf Coast Salt Dome Basin.
Business Case Slide 8: High-Volume: Repository - Basis for Use
Volume: Repository - Basis for Use Basis for use DUO2 in or near cask should be a geochemical barrier Establish reducing conditions Inhibit spent fuel dissolution Keep...
EA-1404: Actinide Chemistry and Repository Science Laboratory, Carlsbad, New Mexico
Energy.gov (U.S. Department of Energy (DOE))
This EA evaluates the environmental impacts for the proposal to construct and operate an Actinide Chemistry and Repository Science Laboratory to support chemical research activities related to the...
Generic Repository Concepts and Thermal Analysis for Advanced Fuel Cycles
The current posture of the used nuclear fuel management program in the U.S. following termination of the Yucca Mountain Project, is to pursue research and development (R&D) of generic (i.e., non-site specific) technologies for storage, transportation and disposal. Disposal R&D is directed toward understanding and demonstrating the performance of reference geologic disposal concepts selected to represent the current state-of-the-art in geologic disposal. One of the principal constraints on waste packaging and emplacement in a geologic repository is management of the waste-generated heat. This paper describes the selection of reference disposal concepts, and thermal management strategies for waste from advanced fuel cycles. A geologic disposal concept for spent nuclear fuel (SNF) or high-level waste (HLW) consists of three components: waste inventory, geologic setting, and concept of operations. A set of reference geologic disposal concepts has been developed by the U.S. Department of Energy (DOE) Used Fuel Disposition Campaign, for crystalline rock, clay/shale, bedded salt, and deep borehole (crystalline basement) geologic settings. We performed thermal analysis of these concepts using waste inventory cases representing a range of advanced fuel cycles. Concepts of operation consisting of emplacement mode, repository layout, and engineered barrier descriptions, were selected based on international progress and previous experience in the U.S. repository program. All of the disposal concepts selected for this study use enclosed emplacement modes, whereby waste packages are in direct contact with encapsulating engineered or natural materials. The encapsulating materials (typically clay-based or rock salt) have low intrinsic permeability and plastic rheology that closes voids so that low permeability is maintained. Uniformly low permeability also contributes to chemically reducing conditions common in soft clay, shale, and salt formations. Enclosed modes are associated with temperature constraints that limit changes to the encapsulating materials, and they generally have less capacity to dissipate heat from the waste package and its immediate surroundings than open modes such as that proposed for a repository at Yucca Mountain, Nevada. Open emplacement modes can be ventilated for many years prior to permanent closure of the repository, limiting peak temperatures both before and after closure, and combining storage and disposal functions in the same facility. Open emplacement modes may be practically limited to unsaturated host formations, unless emplacement tunnels are effectively sealed everywhere prior to repository closure. Thermal analysis of disposal concepts and waste inventory cases has identified important relationships between waste package size and capacity, and the duration of surface decay storage needed to meet temperature constraints. For example, the choice of salt as the host medium expedites the schedule for geologic disposal by approximately 50 yr (other factors held constant) thereby reducing future reliance on surface decay storage. Rock salt has greater thermal conductivity and stability at higher temperatures than other media considered. Alternatively, the choice of salt permits the use of significantly larger waste packages for SNF. The following sections describe the selection of reference waste inventories, geologic settings, and concepts of operation, and summarize the results from the thermal analysis.
Hardin, Ernest [Sandia National Laboratories (SNL); Blink, James [Lawrence Livermore National Laboratory (LLNL); Carter, Joe [Savannah River National Laboratory (SRNL); Massimiliano, Fratoni [Lawrence Livermore National Laboratory (LLNL); Greenberg, Harris [Lawrence Livermore National Laboratory (LLNL); Howard, Rob L [ORNL
Progressive dissolution of the Murchison carbonaceous chondrite with acids of increasing strengths reveals large internal W isotope variations that reflect a heterogeneous distribution of s- and r-process W isotopes among the components of primitive chondrites. At least two distinct carriers of nucleosynthetic W isotope anomalies must be present, which were produced in different nucleosynthetic environments. The co-variation of {sup 182}W/{sup 184}W and {sup 183}W/{sup 184}W in the leachates follows a linear trend that is consistent with a mixing line between terrestrial W and a presumed s-process-enriched component. The composition of the s-enriched component agrees reasonably well with that predicted by the stellar model of s-process nucleosynthesis. The co-variation of {sup 182}W/{sup 184}W and {sup 183}W/{sup 184}W in the leachates provides a means for correcting the measured {sup 182}W/{sup 184}W and {sup 182}W/{sup 183}W of Ca-Al-rich inclusions (CAI) for nucleosynthetic anomalies using the isotopic variations in {sup 183}W/{sup 184}W. This new correction procedure is different from that used previously, and results in a downward shift of the initial {epsilon}{sup 182}W of CAI to -3.51 {+-} 0.10 (where {epsilon}{sup 182}W is the variation in 0.01% of the {sup 182}W/{sup 183}W ratio relative to Earth's mantle). This revision leads to Hf-W model ages of core formation in iron meteorite parent bodies that are {approx}2 Myr younger than previously calculated. The revised Hf-W model ages are consistent with CAI being the oldest solids formed in the solar system, and indicate that core formation in some planetesimals occurred within {approx}2 Myr of the beginning of the solar system.
Burkhardt, Christoph; Wieler, Rainer [Institute of Geochemistry and Petrology, Clausiusstrasse 25, ETH Zurich, CH-8092 Zurich (Switzerland); Kleine, Thorsten [Institut fuer Planetologie, Westfaelische Wilhelms-Universitaet Muenster, Wilhelm-Klemm-Strasse 10, D-48149 Muenster (Germany); Dauphas, Nicolas, E-mail: email@example.com [Origins Laboratory, Department of the Geophysical Sciences and Enrico Fermi Institute, University of Chicago, 5734 South Ellis Avenue, Chicago, IL 60637 (United States)
Evaluation of a Spent Fuel Repository at Yucca Mountain, Nevada
In June 2008, the U.S. Department of Energy (DOE) submitted a license application to the U.S. Nuclear Regulatory Commission (NRC) for the construction of a geologic repository at Yucca Mountain, Nevada, for the disposal of spent nuclear fuel and high-level radioactive waste. The license application was accepted for formal NRC review in September 2008. Throughout the more than 20-year history of the Yucca Mountain project, EPRI has performed independent assessments of key technical and scientific issues t...
Contact zones and hydrothermal systems as analogues to repository conditions
Radioactive waste isolation efforts in the US are currently focused on examining basalt, tuff, salt, and crystalline rock as candidate rock types to encompass waste repositories. As analogues to near-field conditions, the distributions of radio- and trace-elements have been examined across contacts between these rocks and dikes and stocks that have intruded them. The intensive study of the Stripa quartz monzonite has also offered the opportunity to observe the distribution of uranium and its daughters in groundwater and its relationship to U associated with fracture-filling and alteration minerals. Investigations of intrusive contact zones to date have included (1) a tertiary stock into Precambrian gneiss, (2) a stock into ash flow tuff, (3) a rhyodacite dike into Columbia River basalt, and (4) a kimberlite dike into salt. With respect to temperature and pressure, these contact zones may be considered "worst-case scenario" analogues. Results indicate that there has been no appreciable migration of radioelements from the more radioactive intrusives into the less radioactive country rocks, either in response to the intrusions or in the fracture-controlled hydrological systems that developed following emplacement. In many cases, the radioelements are locked up in accessory minerals, suggesting that artificial analogues to these would make ideal waste forms. Emphasis should now shift to examination of active hydrothermal systems, studying the distribution of key elements in water, fractures, and alteration minerals under pressure and temperature conditions most similar to those expected in the near-field environment of a repository. 14 refs.
Wollenberg, H.A.; Flexser, S.
Dessicant materials screening for backfill in a salt repository
Maintaining an anhydrous environment around nuclear waste stored in a salt repository is a concern which can be alleviated by using a desiccant material for backfilling. Such a desiccant should desiccate a brine yet be non deliquescent, the hydrated product should have moderate thermal stability, and the desiccant should have a high capacity and be readily available. From a literature search MgO and CaO were identified for detailed study. These oxides, and an intimate mixture of the two obtained by calcining dolomite, were used in experiments to further determine their suitability. They proved to be excellent desiccants with a high water capacity. The hydrates of both have moderate thermal stability and a high water content. Both MgO and CaO react in an alkaline chloride brine forming oxychloride compounds with different waters of crystallization. Some of these compounds are the Sorel Cements. CaO hydrates to Ca(OH)/sub 2/ which carbonates with CO/sub 2/ in air to form CaCO/sub 3/ and release the hydrated water. Thus the intimate mixture of CaO and MgO from calcined dolomite may serve as a desiccant and remove CO/sub 2/ from the repository atmosphere.
Simpson, D.R.
Repository disposal requirements for commercial transuranic wastes (generated without reprocessing)
This report forms a preliminary planning basis for disposal of commercial transuranic (TRU) wastes in a geologic repository. Because of the unlikely prospects for commercial spent nuclear fuel reprocessing in the near-term, this report focuses on TRU wastes generated in a once-through nuclear fuel cycle. The four main objectives of this study were to: develop estimates of the current inventories, projected generation rates, and characteristics of commercial TRU wastes; develop proposed acceptance requirements for TRU wastes forms and waste canisters that ensure a safe and effective disposal system; develop certification procedures and processing requirements that ensure that TRU wastes delivered to a repository for disposal meet all applicable waste acceptance requirements; and identify alternative conceptual strategies for treatment and certification of commercial TRU first objective was accomplished through a survey of commercial producers of TRU wastes. The TRU waste acceptance and certification requirements that were developed were based on regulatory requirements, information in the literature, and from similar requirements already established for disposal of defense TRU wastes in the Waste Isolation Pilot Plant (WIPP) which were adapted, where necessary, to disposal of commercial TRU wastes. The results of the TRU waste-producer survey indicated that there were a relatively large number of producers of small quantities of TRU wastes.
Daling, P.M.; Ludwick, J.D.; Mellinger, G.B.; McKee, R.W.
Common Metadata for Climate Modelling Digital Repositories CIM-enabled OASIS
Common Metadata for Climate Modelling Digital Repositories CIM-enabled OASIS CERFACS Technical-1.2.1 Scientific Digital Repositories DOCUMENT Deliverable D5.7 Month 36 Deliverable Title CIM-enabled OASIS to manipulate the CIM Authors S. Valcke, J.M. Epitalon, M.P. Moine, CERFACS Document Status Final Document Link
Benchmarking DAML+OIL Repositories Yuanbo Guo, Jeff Heflin, and Zhengxiang Pan
Benchmarking DAML+OIL Repositories Yuanbo Guo, Jeff Heflin, and Zhengxiang Pan Department, heflin, firstname.lastname@example.com Abstract. We present a benchmark that facilitates the evaluation of DAML+OIL repositories in a standard and systematic way. This benchmark is intended to evaluate the performance of DAML+OIL
Heflin, Jeff
EM Gains Insight from Germany on Salt-Based Repositories | Department of
Gains Insight from Germany on Salt-Based Repositories Gains Insight from Germany on Salt-Based Repositories EM Gains Insight from Germany on Salt-Based Repositories December 14, 2011 - 12:00pm Addthis Participants in the workshops in Germany toured Asse II, one of Germanyâs two salt-based repositories, to gain insights into that facilityâs technical challenges and proposed solutions. Pictured, left to right, are an Asse II employee, Bernhard Kienzler of the Karlsruhe Institute of Technology, CBFO Chief Scientist Roger Nelson, CBFO International Programs Manager Dr. Abraham Van Luik, and Andrew Wolfsberg, Acting Deputy Division Leader for Earth and Environmental Sciences at Los Alamos National Laboratory. Participants in the workshops in Germany toured Asse II, one of Germany's two salt-based repositories, to gain insights into that facility's
An evaluation of near-field host rock temperatures for a spent fuel repository
A repository heat transfer analysis has been performed by the Pacific Northwest Laboratory (PNL) for the US Department of Energy's Performance Assessment Scientific Support Program. The objective of this study was to evaluate the near-field thermal environmental conditions for a spent fuel repository system. A spent fuel logistics analysis was performed using a waste management system simulation model, WASTES-II, to evaluate the thermal characteristics of spent fuel received at the repository. A repository-scale thermal analysis was performed using a finite difference heat transfer code, TEMPEST, to evaluate the near-field host rock temperature. The calculated temporal and spatial distributions of near-field host rock temperatures provide input to the repository source term model in evaluations of engineered barrier system performance. 9 refs., 10 figs., 2 tabs.
Altenhofen, M.K.; Lowery, P.S.
Phase III: Implementation and Operation of the Repository
The metadata catalog was brought online for public access May 14, 1998. Since then dozens of users have registered and began to access the system. The system was demonstrated at the AAPG annual meeting in Salt Lake City and the EAGE (European Association of Geoscientists and Engineers) annual meeting in Leipzig, Germany. Hart Publications and PTTC ?NetworkNews? have published articles about the metadata catalog, and articles for the AAPG Explorer and GSA Today are being developed. A back-up system at AGI headquarters was established. In support of the metadata catalog system, a leased-line Internet connection and two servers were installed. Porting of the GeoTrek server software to the new systems has begun. The back-up system will be operational during the 3 rd quarter of 1998 and will serve the NGDRS needs during periods when access to the site in Houston is down. Additionally, experimentation with new data types and deployment schemes will be tested on the system at AGI. The NGDRS has picked-up additional endorsements from the American Association of State Geologists, the MMS Outer Continental Shelf Policy Committee, and a new endorsement is being formulated by the AAPG Core Preservation Committee for consideration by the AAPG Executive Committee. The Texas Bureau of Economic Geology (BEG) is currently geocoding the well locations for the metadata catalog. Also, they have solicited proposals for the development of a core inventory control system that will work hand-in-hand with GeoTrek. A contract for that system will probably be given during the 3 rd quarter of 1998. The Texas Railroad Commission proposes to test the application of GeoTrek for accessing data in a joint project with the BEG. Several data transfer projects are underway. Vastar has committed to the transfer of 2D Appalachian seismic lines to the NDGRS clearinghouse. Receiving repositories have been identified and the final preparations are being made for transfer to these public repositories. Discussions have been initiated with the State of Oregon concerning listing their 400 oil and gas well and 50 geothermal well cores and logs on the metadata catalog. Additionally, discussions continue with the Stapleton Development Corporation concerning the transfer of facilities in Denver for use as a central core repository. A letter of intent for the facility?s transfer is being reviewed.
Generic repository design concepts and thermal analysis (FY11).
Reference concepts for geologic disposal of used nuclear fuel and high-level radioactive waste in the U.S. are developed, including geologic settings and engineered barriers. Repository thermal analysis is demonstrated for a range of waste types from projected future, advanced nuclear fuel cycles. The results show significant differences among geologic media considered (clay/shale, crystalline rock, salt), and also that waste package size and waste loading must be limited to meet targeted maximum temperature values. In this study, the UFD R&D Campaign has developed a set of reference geologic disposal concepts for a range of waste types that could potentially be generated in advanced nuclear FCs. A disposal concept consists of three components: waste inventory, geologic setting, and concept of operations. Mature repository concepts have been developed in other countries for disposal of spent LWR fuel and HLW from reprocessing UNF, and these serve as starting points for developing this set. Additional design details and EBS concepts will be considered as the reference disposal concepts evolve. The waste inventory considered in this study includes: (1) direct disposal of SNF from the LWR fleet, including Gen III+ advanced LWRs being developed through the Nuclear Power 2010 Program, operating in a once-through cycle; (2) waste generated from reprocessing of LWR UOX UNF to recover U and Pu, and subsequent direct disposal of used Pu-MOX fuel (also used in LWRs) in a modified-open cycle; and (3) waste generated by continuous recycling of metal fuel from fast reactors operating in a TRU burner configuration, with additional TRU material input supplied from reprocessing of LWR UOX fuel. The geologic setting provides the natural barriers, and establishes the boundary conditions for performance of engineered barriers. The composition and physical properties of the host medium dictate design and construction approaches, and determine hydrologic and thermal responses of the disposal system. Clay/shale, salt, and crystalline rock media are selected as the basis for reference mined geologic disposal concepts in this study, consistent with advanced international repository programs, and previous investigations in the U.S. The U.S. pursued deep geologic disposal programs in crystalline rock, shale, salt, and volcanic rock in the years leading up to the Nuclear Waste Policy Act, or NWPA (Rechard et al. 2011). The 1987 NWPA amendment act focused the U.S. program on unsaturated, volcanic rock at the Yucca Mountain site, culminating in the 2008 license application. Additional work on unsaturated, crystalline rock settings (e.g., volcanic tuff) is not required to support this generic study. Reference disposal concepts are selected for the media listed above and for deep borehole disposal, drawing from recent work in the U.S. and internationally. The main features of the repository concepts are discussed in Section 4.5 and summarized in Table ES-1. Temperature histories at the waste package surface and a specified distance into the host rock are calculated for combinations of waste types and reference disposal concepts, specifying waste package emplacement modes. Target maximum waste package surface temperatures are identified, enabling a sensitivity study to inform the tradeoff between the quantity of waste per disposal package, and decay storage duration, with respect to peak temperature at the waste package surface. For surface storage duration on the order of 100 years or less, waste package sizes for direct disposal of SNF are effectively limited to 4-PWR configurations (or equivalent size and output). Thermal results are summarized, along with recommendations for follow-on work including adding additional reference concepts, verification and uncertainty analysis for thermal calculations, developing descriptions of surface facilities and other system details, and cost estimation to support system-level evaluations.
Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); Dupont, Mark (Savannah River Nuclear Solutions, Aiken, SC); Blink, James A. (Lawrence Livermore National Laboratory, Livermore, CA); Fratoni, Massimiliano (Lawrence Livermore National Laboratory, Livermore, CA); Greenberg, Harris (Lawrence Livermore National Laboratory, Livermore, CA); Carter, Joe (Savannah River Nuclear Solutions, Aiken, SC); Hardin, Ernest L.; Sutton, Mark A. (Lawrence Livermore National Laboratory, Livermore, CA)
Chemistry of transuranium elements in salt-base repository
The mobility and potential release of actinides into the accessible environment continues to be the key performance assessment concern of nuclear repositories. Actinide, in particular plutonium speciation under the wide range of conditions that can exist in the subsurface is complex and depends strongly on the coupled effects of redox conditions, inorganic/organic complexation, and the extent/nature of aggregation. Understanding the key factors that define the potential for actinide migration is, in this context, an essential and critical part of making and sustaining a licensing case for a nuclear repository. Herein we report on recent progress in a concurrent modeling and experimental study to determine the speciation of plutonium, uranium and americium in high ionic strength Na-CI-Mg brines. This is being done as part of the ongomg recertification effort m the Waste Isolation Pilot Plant (WIPP). The oxidation-state specific solubility of actinides were established in brine as function of pC{sub H+}, brine composition and the presence and absence of organic chelating agents and carbonate. An oxidation-state invariant analog approach using Nd{sup 3+} and Th{sup 4+} was used for An{sup 3+} and An{sup 4+} respectively. These results show that organic ligands and hydrolysis are key factors for An(III) solubility, hydrolysis at pC{sub H+} above 8 is predominate for An(IV) and carbonates are the key factor for U(VI) solubility. The effect of high ionic strength and brine components measured in absence of carbonates leads to measurable increased in overall solubility over analogous low ionic strength groundwater. Less is known about the bioreduction of actinides by halo-tolerant microorganisms, but there is now evidence that bioreduction does occur and is analogous, in many ways, to what occurs with soil bacteria. Results of solubility studies that focus on Pitzer parameter corrections, new species (e.g. borate complexation), and the thermodynamic parameters for modeling are discussed.
Borkowski, Marian [Los Alamos National Laboratory; Reed, Donald T [Los Alamos National Laboratory; Lucchini, Jean - Francois [Los Alamos National Laboratory; Richmann, Michael K [Los Alamos National Laboratory; Khaing, H [Los Alamos National Laboratory; Swanson, J [Los Alamos National Laboratory; Ams, D [Los Alamos National Laboratory
Final Systems Development Report for the Clark County Socioeconomic Impact Assessment of the Proposed High-Level Nuclear Waste Repository at Yucca Mountain, NV
The Systems Development Report represents the third major step in the Clark County Socioeconomic Impact Assessment of the Proposed High-Level Nuclear Waste Repository at Yucca Mound Nevada. The first of these steps was to forge a Research Design that would serve as a guide for the overall research process. The second step was the construction of the Base Case, the purpose of which was to describe existing conditions in Clark County in the specified analytic areas of Economic-Demographic/Fiscal, Emergency Planning and Management, Transportation and Sociocultural analysis. The base case description will serve as a basis for assessing changes in these topic areas that might result from the Yucca Mountain project. These changes will be assessed by analyzing conditions with and without repository development in the county. Prior to performing such assessments, however, the snapshot type of data found in the base case must be operationalized or systematized to allow for more dynamic data utilization. In other words, a data system that can be used to analyze the consequences of the introduction of different variables (or variable values) in the Clark County context must be constructed. Such a system must be capable of being updated through subsequent data collection and monitoring efforts to both provide a rolling base case and supply information necessary to construct trend analyses. For example, during the Impact Assessment phase of the study process, the without repository analysis is accomplished by analyzing growth for the county given existing conditions and likely trends. These data are then compared to the with Yucca Mountain project conditions anticipated for the county. Similarly, once the emergency planning management and response needs associated with the repository are described, these needs will be juxtaposed against existing (and various future) capacity(ies) in order to determine the nature and magnitude of impacts in this analytic area. Analogous tasks will be performed for the other analytic areas detailed in the Base Case and outlined below.
Improved collecting apparatus
An improved collecting apparatus for small aquatic or airborne organisms such as plankton, larval fish, insects, etc. The improvement constitutes an apertured removal container within which is retained a collecting bag, and which is secured at the apex of a conical collecting net. Such collectors are towed behind a vessel or vehicle with the open end of the conical net facing forward for trapping the aquatic or airborne organisms within the collecting bag, while allowing the water or air to pass through the apertures in the container. The container is readily removable from the collecting net whereby the collecting bag can be quickly removed and replaced for further sample collection. The collecting bag is provided with means for preventing the bag from being pulled into the container by the water or air following therethrough.
Duncan, C.P.
A Summary of INEEL Calcine Properties Used to Evaluate Direct Calcine Disposal in the Yucca Mountain Repository
C. A. Dahl
Toxicity characteristic leaching procedure fails to extract oxoanion-forming elements that are extracted by municipal solid waste leachates
US EPA and state regulatory agencies rely on standard extraction tests to identify wastes that have the potential to contaminate surface water or groundwater. To evaluate the predictive abilities of these extraction tests, the Toxicity Characteristic Leaching Procedure (TCLP), the Waste Extraction Test (WET), and the Synthetic Precipitation Leaching Procedure (SPLP) were compared with actual municipal solid waste leachates (MSWLs) for their ability to extract regulated elements from a variety of industrial solid wastes in short- and long-term extractions. Short-term extractions used MSWLs from a variety of California landfills. Long-term sequential extractions simulated longer term leaching, as might occur in MSW landfills. For most regulated elements, the TCLP roughly predicted the maximum concentrations extracted by the MSWLs. For regulated elements that form oxoanions (e.g., Sb, As, Mo, Se, V), however the TCLP underpredicted the levels extracted by the MSWL. None of the standard tests adequately predicted these levels. The results emphasize the need for better standardized techniques to identify wastes that have the potential to contaminate groundwater with oxoanion-forming elements, particularly arsenic.
Hooper, K.; Iskander, M.; Sivia, G. [California Dept. of Toxic Substances Control, Berkeley, CA (United States). Hazardous Materials Lab.] [and others
Vegetation Collections Project Page
Vegetation Collections Vegetation Collections Vegetation Collections Overview Vegetation regulates the flow of numerous biogeochemical cycles, most critically those of water, carbon, and nitrogen; it is also of great importance in local and global energy balances. Vegetation collections data include: Biomass Biome Characteristics Litter Chemistry and Decomposition Geoecology Nutrient Concentration, Profiles, and Turnover Global Fire Emissions, Vegetation, and Leaf Area Index (LAI) Ecosystem Structure and Function Phenoregions Carbon Flux Vegetation Resources The following resources related to Vegetation Collections are maintained by the ORNL DAAC: Global Leaf Area Index Data Net Primary Production Project Get Vegetation Data Find and order data sets: See list of data sets and download data
Collective error detection for MPI collective operations
An MPI profiling library is a standard mechanism for intercepting MPI calls by applications. Profiling libraries are so named because they are commonly used to gather performance data on MPI programs. Here we present a profiling library whose purpose ... Keywords: MPI, collective, datatype, errors, hashing
Chris Falzone; Anthony Chan; Ewing Lusk; William Gropp
U.S. Department of Energy Awards a Contract to USA Repository Services for
a Contract to USA Repository a Contract to USA Repository Services for Management and Operating Contractor Support for the Yucca Mountain Project U.S. Department of Energy Awards a Contract to USA Repository Services for Management and Operating Contractor Support for the Yucca Mountain Project October 30, 2008 - 4:14pm Addthis Washington, D.C. -- The U.S. Department of Energy (DOE) today awarded a $2.5 billion management and operating (M&O) contract to USA Repository Services (USA-RS), a wholly-owned subsidiary of the URS Corporation. USA-RS will be supported by principal subcontractors: Shaw Environmental and Infrastructure, Inc., and AREVA Federal Services, Inc. "If we are to meet growing energy demand and slow the growth of greenhouse gas emissions, nuclear power must be a larger part of our energy mix; it is
U.S. Department of Energy Awards a Contract to USA Repository U.S. Department of Energy Awards a Contract to USA Repository Services for Management and Operating Contractor Support for the Yucca Mountain Project U.S. Department of Energy Awards a Contract to USA Repository Services for Management and Operating Contractor Support for the Yucca Mountain Project October 30, 2008 - 4:14pm Addthis Washington, D.C. -- The U.S. Department of Energy (DOE) today awarded a $2.5 billion management and operating (M&O) contract to USA Repository Services (USA-RS), a wholly-owned subsidiary of the URS Corporation. USA-RS will be supported by principal subcontractors: Shaw Environmental and Infrastructure, Inc., and AREVA Federal Services, Inc. "If we are to meet growing energy demand and slow the growth of greenhouse gas emissions, nuclear power must be a larger part of our energy mix; it is
This fact sheet describes the repository design activities the U.S. Department o
repository design activities the U.S. Department of Energy is conducting at the Monticello repository design activities the U.S. Department of Energy is conducting at the Monticello Mill Tailings Site in Monticello, Utah. These activities are being performed in accordance with Federal and State environ- mental laws. Background The purpose of the Monticello cleanup projects is to minimize the risks to the public and the environment from exposure to mill tailings and the radon gas they produce. The Monticello Mill Tailings Site cleanup remedy was se- lected in the Record of Decision in August 1990 and recon- firmed in December 1994. It includes permanent disposal of mill tailings and contaminated materials in a repository to be constructed on U.S. Department of Energy (DOE)- owned land south of the millsite in Monticello, Utah. The repository will hold approximately 2.6 to 3.0 million cubic
Proceedings of 3rd US/German Workshop on Salt Repository Research...
New Mexico on October 8-11, 2012. Approximately 60 salt research scientists from Germany and the United States met to discuss repository science state of the art. Workshop...
Risk-informing decisions about high-level nuclear waste repositories
Performance assessments (PAs) are important sources of information for societal decisions in high-level radioactive waste (HLW) management, particularly in evaluating safety cases for proposed HLW repository development. ...
Ghosh, Suchandra Tina, 1973-
University of Wisconsin: NSpace: Exploring Architectural Design Principles for a Next-Generation Institutional Repository
plugin to generate Eclipse project configuration files for each of the NSpace subprojects: $ cd nspace $ maven -Dgoal=eclipse multiproject:goal This will also download and cache all of the JAR dependencies for NSpace in your local Maven repository...
Simpson, Mike; Downing, Jim
Structure for a Living Requirements Repository for Long Term Operation of Nuclear Power Plants
This report describes the structure and specifications for a relational repository that will capture long-term requirements (LTRs) and their dependencies on underlying technologies. In addition, it presents principles and prototypical examples for graphical models that supplement the relational repository and support the development, capture, and re-use of long-term instrumentation and control architectural elements to support plant modifications that enable long-term ...
Program on Technology Innovation: EPRI Yucca Mountain Spent Fuel Repository Evaluation
The Department of Energy (DOE) is moving to prepare and submit a license application to the Nuclear Regulatory Commission (NRC) to initiate construction of a geologic repository at Yucca Mountain, Nevada, for the storage of spent nuclear fuel and high level radioactive waste. Throughout the nearly 20-year history of the project, EPRI has performed independent assessments of technical and scientific issues considered important to eventual repository licensing. This report presents background on the overal...
Facilitating the Deposit of Experimental Chemistry Data in Institutional Repositories: Project SPECTRa
restrictions. One conspicuous component of the OA movement has been the development of repositories as a means of managing the deposit, dissemination and preservation of research outputs in digital form. The Directory of Open Access Repositories, Open... the needs of the chemistry research community The project selected three distinct areas of chemistry research � synthetic organic chemistry, crystallography and computational chemistry - for investigation. Each of these proved to have specific...
Morgan, Peter
A performance goal-based seismic design philosophy for waste repository facilities
A performance goal-based seismic design philosophy, compatible with DOE`s present natural phenomena hazards mitigation and ``graded approach`` philosophy, has been proposed for high level nuclear waste repository facilities. The rationale, evolution, and the desirable features of this method have been described. Why and how the method should and can be applied to the design of a repository facility are also discussed.
Hossain, Q.A.
The Department of Energy (DOE) is moving to prepare and submit a license application to the Nuclear Regulatory Commission (NRC) to initiate construction of a geologic repository at Yucca Mountain, Nevada, for the storage of spent nuclear fuel and high level radioactive waste. Throughout the more than 20-year history of the project, EPRI has performed independent assessments of technical and scientific issues considered important to eventual repository licensing. This report presents background on the ove...
Program on Technology Innovation: Evaluation of a Spent Fuel Repository at Yucca Mountain, Nevada
The U.S. Department of Energy (DOE) is moving to prepare and submit a license application to initiate construction of a geologic repository at Yucca Mountain, Nevada, for the storage of spent nuclear fuel and high level radioactive waste. Throughout the more than 20-year history of the project, EPRI has performed independent assessments of technical and scientific issues that are considered important to the eventual licensing of the repository. This report provides background on the overall project and d...
Potential Igneous Processes Relevant to the Yucca Mountain Repository: Extrusive-Release Scenario: Analysis and Implications
The Department of Energy (DOE) is moving to prepare and submit a license application to initiate construction of the geologic repository at Yucca Mountain. As part of the application, the DOE must provide estimates of the dose risk to a local population caused by low probability igneous eruptions that may occur through the repository after closure. To date, published estimates of such dose risks have included a large number of conservative assumptions such that it appears as if igneous eruptions provide ...
Repository site data report for unsaturated tuff, Yucca Mountain, Nevada
The US Department of Energy is currently considering the thick sequences of unsaturated, fractured tuff at Yucca Mountain, on the southwestern boundary of the Nevada Test Site, as a possible candidate host rock for a nuclear-waste repository. Yucca Mountain is in one of the most arid areas in the United States. The site is within the south-central part of the Great Basin section of the Basin and Range physiographic province and is located near a number of silicic calderas of Tertiary age. Although localized zones of seismic activity are common throughout the province, and faults are present at Yucca Mountain, the site itself is basically aseismic. No data are available on the composition of ground water in the unsaturated zone at Yucca Mountain. It has been suggested that the composition is bounded by the compositions of water from wells USW-H3, UE25p-1, J-13, and snow or rain. There are relatively few data available from Yucca Mountain on the moisture content and saturation, hydraulic conductivity, and characteristic curves of the unsaturated zone. The available literature on thermomechanical properties of tuff does not always distinguish between data from the saturated zone and data from the unsaturated zone. Geochemical, hydrologic, and thermomechanical data available on the unsaturated tuffs of Yucca Mountain are tabulated in this report. Where the data are very sparse, they have been supplemented by data from the saturated zone or from areas other than Yucca Mountain. 316 refs., 58 figs., 37 tabs.
Tien, P.L.; Updegraff, C.D.; Siegel, M.D.; Wahi, K.K.; Guzowski, R.V.
Identification of tire leachate toxicants and a risk assessment of water quality effects using tire reefs in canals
Cover is important to aquatic habitat and fisheries often try to improve habitats by addition of natural and artificial material to improve cover diversity and complexity. Habitat-improvement programs range from submerging used Christmas trees to more complex programs. Used automobile tires have been employed in the large scale construction of reefs and fish attractors in marine environments and to a lesser extent in freshwater and have been recognized as a durable, inexpensive and long-lasting material benefiting fishery communities. Recent studies by the U.S. Bureau of Reclamation have quantified the importance of tire reefs to enhancing freshwater canal fisheries in the southwestern United States. These studies have demonstrated that fishes and aquatic macroinvertebrates are attracted to these structures, increasing species diversity, densities and biomass where reefs are placed in canals. However, the use of tire reefs in aquatic environments which have relatively small volumes compared to marine or reservoir environments has raised water quality concerns. Effects of tires on water quality have not typically been studied in the past because of the obvious presence of fishes and other aquatic organisms that make use of tire reefs; the implication being that tires are inert and non-toxic. Little information on effects of tires on water quality is in the literature. Stone demonstrated that tire exposure had no detrimental effects on two species of marine fish while results of Kellough's freshwater tests were inconclusive, but suggested that some factor in tire leachate was toxic to rainbow trout (Oncorhynchus mykiss). Nozaka et al. found no harmful substances leached from tire material soaked in fresh water. Because there are few data on toxicity associated with tires, this became the focus of our study. Toxicity Identification Evaluation (TIE) procedures developed by the EPA were used to evaluate water quality impacted by tires. 17 refs., 4 figs.
Nelson, S.M.; Mueller, G. (Bureau of Reclamation, Denver, CO (United States)); Hemphill, D.C. (Lower Colorado Regional Office, Boulder City, NV (United States))
using chemical solvents is one promising solution, especially when applied to coal-frred power plants. IEA (IEA, 2009) considers that it could handle up to 19% of COz emissions. Post-combustion capture
Recanati, Catherine
SAND REPORT SAND2004-2871 Unlimited Release August 19, 2004 A Mathematical Framework for Multiscale://www.ntis.gov/ordering.htm #12;SAND2004-2871 Unlimited Release Printed August 19, 2004 A Mathematical Framework for Multiscale] for coupling finite elements (FE), classical molecular dynamics (MD), and tight binding (TB) quantum
the nanoprobes commonly con- sidered for medical imaging are organic dyes such as DAPI or green fluorescence emission bandwidths, high photochemical stability and long fluorescence lifetime (up to sev- eral. 2. Evolution of (a) FTIR spectra vs. dialysis time for Eu-free apatite colloid and (b) FTIR
, the function of power plants, and water resources management. Many efforts have contributed to the development was motivated by the implementation of a Kalman Filter algorithm on top of a diffusive flood wave propagation
Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech
this version : Annie-Claude BAYEUL-LAINE, Sophie SIMONET, Gérard BOIS - Unsteady flow field in a mini VAWT Author manuscript, published in "6th ICPF conference China (2013)" #12;Unsteady flow field in a mini firstname.lastname@example.com Abstract. The present wind turbine is a small one which can be used on roofs or in gardens. This turbine
Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and
separation Recirculation zone Forward facing step Wind turbine siting a b s t r a c t An experimental. Wind turbines are commonly sited in the vicinity of topological features such as coastal cliffs facing step geometry will aid the optimal placement of wind turbines sited within complex terrain. 2
industry for applications requiring an excellent mechanical resistance at high temperatures. However speed steel, carbide, ceramic, CBN, dia- mond), the carbides are economically recommended
, Toulouse, France The spatial distribution, the velocity statistics and the dispersion of the gas phase have , even at the lowest gas volume fraction. These oscillations however play no role in the dispersion which the evolution of the dispersion coefficients, Dx and Dy, with the gas volume fraction. Both evolve almost
for generating largely clean CO2-free electricity and zirconium is a fission product that is expected to be present in irradiated fuels. The present investigation addresses the electrochemical reduction of Zr4 nuclear fuel. The renewed interest owes its origin to several attractive features
and trends concerning cellulosic materials processed in scCO2 such as cellulose drying to obtain aerogels for cellulose esters and ether synthesis, and fibres and film fabrication. These materials are used in coatings
of these structures, see e.g. [7]). Definition 3.1 A sequential data structure (sds) [1] is a triple S = (C, V, P
, a natural gas component, hence a non-renewable energy. Ethanol and particularly bioethanol from sugar cane, sugar beet or corn is preferable to methanol due to its superior dissolving power for vegetable oils of the conversion of the sunflower oil (1 h), the reaction medium was neutralized by HCl addition
of fiberboards, or for their heat insulation properties in building industry. Moreover, thermo to evaluate the influence of thermo-pressing conditions on mechanical and heat insulation properties promising heat insulation properties. Indeed, thermal conductivity of fiberboards at 25 C was low (from 103
Paris-Sud XI, Université de
, Madeleine and Brousse, Valérie. Modular simulation and optimization of an 12MW industrial gasifier. (2010 Simulation and Optimization of an 12MW Industrial Gasifier X. Joulia(1) , P. Floquet(1) , R. Sardeing(2) , O located in Morcenx (France). This gasifier is able to treat more than 46,875 ton/year of RDF (Refused
Multiprocessing compactifying garbage collection
Algorithms for a multiprocessing compactifying garbage collector are presented and discussed. The simple case of two processors, one performing LISP-like list operations and the other performing garbage collection continuously, is thoroughly examined. ... Keywords: LISP, compactification, data structures, free storage, garbage collection, gc processor, list processing, multiprocessing, parallel processing, pointers, reclaimer, relocation, semaphores, storage allocation, storage reclamation, synchronization
Guy L. Steele, Jr.
The purpose of this letter is to transmit the U.S. Department of Energy's (DOE) first update to the Yucca Mountain Repository LA, which meets the requirements of 10 CFR � 63.22(c) to update the application on notification of the appointment of an Atomic Safety and Licensing Board. DOE initially transmitted its LA for construction authorization to the U.S. Nuclear Regulatory Commission (NRC) on June 3, 2008. In accordance with 10 CFR � 63.22(e), DOE certifies that this revision reflects the updated LA as of October 16, 2008. Changes made to this revision were determined not to be significant and did not impact the conclusions of the LA. The update was initiated soon after the docketing of the LA by the NRC in anticipation of notification of the appointment of an Atomic Safety and Licensing Board. Due to the lengthy process required to maintain configuration control between the paper version and the electronic version, and the time required to print the paper version, DOE is submitting the update prepared as of that time. Enclosed are optical storage media which contain: 1) the first update of the LA, with revised sections clearly identified as Revision 1, and text and figure changes noted with marginal change bars; and 2) updates to the primary reference documents to the LA, affecting 36 of the original 196 references. In addition, enclosed in paper format are: 1) a detailed listing of the contents of the optical storage media submitted with this letter; 2) a summary of the specific LA changes that have been made, including the sections revised and a description of each change; and 3) copies of the individual LA pages affected by changes since the June 3, 2008, submittal. The updates to the primary reference
Michael F. Weber
Evaluation of the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Using Total System Performance Assessment: Phase 6
A successful license application for the candidate spent-fuel and high-level waste repository at Yucca Mountain depends on a robust demonstration of long-term safety. This report presents EPRI's evaluation of, and makes a case for, the suitability of the Yucca Mountain repository using a Total System Performance Assessment (TSPA). The report discusses factors that make the Yucca Mountain repository system suitable for continued development and initiation of the licensing process. Information in this Phas...
Expected near-field thermal environments in a sequentially loaded spent-fuel or high-level waste repository in salt
This report describes the effect of realistic waste emplacement schedules on repository thermal environments. Virtually all estimates to date have been based on instantaneous loading of wastes having uniform properties throughout the repository. However, more realistic scenarios involving sequential emplacement of wastes reflect the gradual filling of the repository over its lifetime. These cases provide temperatures that can be less extreme than with the simple approximation. At isolated locations in the repository, the temperatures approach the instantaneous-loading limit. However, for most of the repository, temperature rises in the near-field are 10 to 40 years behind the conservative estimates depending on the waste type and the location in the repository. Results are presented for both spent-fuel and high-level reprocessing waste repositories in salt, for a regional repository concept, and for a single national repository concept. The national repository is filled sooner and therefore more closely approximates the instantaneously loaded repository. However, temperatures in the near-field are still 20/sup 0/C or more below the values in the simple model for 40 years after startup of repository emplacement operations. The results suggest that current repository design concepts based on the instantaneous-loading predictions are very conservative. Therefore, experiments to monitor temperatures in a test and evaluation facility, for example, will need to take into account the reduced temperatures in order to provide data used in predicting repository performance.
Rickertsen, L.D.; Arbital, J.G.; Claiborne, H.C.
UESC Data Collection Update
UESC Data UESC Data Collection Evan Fuka Energetics, Incorporated 2 | Federal Energy Management Program eere.energy.gov * Overview of Data Collection * What is Needed * How to Submit Data * Why it is Important to You Presentation Overview 3 | Federal Energy Management Program eere.energy.gov * Data on UESC projects has been collected since 1995 * Over $2.3 billion has been invested in federal facilities upgrades and retrofits through the UESC funding mechanism * Information on almost 2,000 UESC projects has been voluntarily submitted and tracked on a continuous basis UESC Data Collection Facts 4 | Federal Energy Management Program eere.energy.gov * Average annual project investment: $123 Million * Utilities engaging in UESC: approximately 40 * UESC Utilities active in FUPWG: approximately 20
Soils Collections Project Page
Soil Collections Soil Collections Soil Collections Overview Soil covers a major portion of the Earth's surface, and is an important natural resource that either directly or indirectly supports most of the planet's life. Soil is a mixture of mineral and organic materials plus air and water. The contents of soil vary by location and are constantly changing. The ORNL DAAC Soil Collections archive contains data on the physical and chemical properties of soils, including: soil carbon and nitrogen soil water-holding capacity soil respiration soil texture Most data sets are globally gridded, while a few are of a regional nature. Get Soils Data Find and order data sets: See list of data sets and download data Browse Soils Data Holdings by selected attributes Retrieve Soils data by FTP browse
A comparative simulation study of coupled THM processes and their effect on fractured rock permeability around nuclear waste repositories
emplacement drift at Yucca Mountain. Journal of Contaminantniches in tuff units at Yucca Mountain. Proceedings of thetunnels, similar to the Yucca Mountain repository concept in
Rutqvist, Jonny
Modeling thermal-hydrological response of the unsaturated zone at Yucca Mountain, Nevada, to thermal load at a potential repository
Repository at Yucca Mountain. In Materials Research Societystudies using the Yucca Mountain unsaturated zone model.Unsaturated Zone, Yucca Mountain, Nevada. Water Resources
Haukwa, C.B.; Wu, Yu-Shu; Bodvarsson, G.S.
NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft
This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.
Status of LANL investigations of temperature constraints on clay in repository environments
The Used Fuel Disposition (UFD) Campaign is presently evaluating various generic options for disposal of used fuel. The focus of this experimental work is to characterize and bound Engineered Barrier Systems (EBS) conditions in high heat load repositories. The UFD now has the ability to evaluate multiple EBS materials, waste containers, and rock types at higher heat loads and pressures (including deep boreholes). The geologic conditions now available to the U.S.A. and the international community for repositories include saturated and reduced water conditions, along with higher pressure and temperature (P, T) regimes. Chemical and structural changes to the clays, in either backfill/buffer or clay-rich host rock, may have significant effects on repository evolution. Reduction of smectite expansion capacity and rehydration potential due to heating could affect the isolation provided by EBS. Processes such as cementation by silica precipitation and authigenic illite could change the hydraulic and mechanical properties of clay-rich materials. Experimental studies of these repository conditions at high P,T have not been performed in the U.S. for decades and little has been done by the international community at high P,T. The experiments to be performed by LANL will focus on the importance of repository chemical and mineralogical conditions at elevated P,T conditions. This will provide input to the assessment of scientific basis for elevating the temperature limits in clay barriers.
Caporuscio, Florie A [Los Alamos National Laboratory; Cheshire, Michael C [Los Alamos National Laboratory; Newell, Dennis L [Los Alamos National Laboratory; McCarney, Mary Kate [Los Alamos National Laboratory
Evaluation of Five Sedimentary Rocks Other Than Salt for Geologic Repository Siting Purposes
The US Department of Energy (DOE), in order to increase the diversity of rock types under consideration by the geologic disposal program, initiated the Sedimary ROck Program (SERP), whose immediate objectiv eis to evaluate five types of secimdnary rock - sandstone, chalk, carbonate rocks (limestone and dolostone), anhydrock, and shale - to determine the potential for siting a geologic repository. The evaluation of these five rock types, together with the ongoing salt studies, effectively results in the consideration of all types of relatively impermeable sedimentary rock for repository purposes. The results of this evaluation are expressed in terms of a ranking of the five rock types with respect to their potential to serve as a geologic repository host rock. This comparative evaluation was conducted on a non-site-specific basis, by use of generic information together with rock evaluation criteria (RECs) derived from the DOE siting guidelines for geologic repositories (CFR 1984). An information base relevant to rock evaluation using these RECs was developed in hydrology, geochemistry, rock characteristics (rock occurrences, thermal response, rock mechanics), natural resources, and rock dissolution. Evaluation against postclosure and preclosure RECs yielded a ranking of the five subject rocks with respect to their potential as repository host rocks. Shale was determined to be the most preferred of the five rock types, with sandstone a distant second, the carbonate rocks and anhydrock a more distant third, and chalk a relatively close fourth.
Croff, A.G.; Lomenick, T.F.; Lowrie, R.S.; Stow, S.H.
Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum
This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive.
Walton, W.C.; Voorhees, M.L.; Prickett, T.A.
Background - Revenue Collection
Revenue Collection Revenue Collection The Internal Revenue Service (IRS) collects Federal fuel taxes from large oil companies or large oil distribution firms with storage facilities prior to distribution of the fuels to customers. The Federal fuel taxes are imposed when the fuel is first removed from bulk storage and sold. Although these taxes are "passed on" to the individual purchaser, data at the individual purchaser level are simply not available. Additional Federal heavy vehicle non-fuel-based fees include (1) the retail sales excise tax on tractors and trailers, (2) the tax on heavy vehicle tire sales, and (3) the heavy vehicle-use tax. Truck registration was once used as a proxy for truck taxes, but was rejected because it did not accurately reflect on-highway usage in a particular State. In fact, the State where the heavy vehicle and/or tires are purchased is not necessarily the State in which these purchases will be used.
Utility Data Collection Service
Data Collection Service Data Collection Service Federal-Utility Partnership Working Group 4 May 2006 Paul Kelley, Chief of Operations, 78 th CES, Robins AFB David Dykes, Industrial Segment Mgr, Federal, GPC Topics Background Commodities Metered Data Collection Cost Results Background Robins AFB (RAFB) needed to: Control electricity usage and considered Demand Control Track and bill base tenants for energy usage Metering Project Originated in 1993 $$ requirements limited interest Developed criteria for available $$ Energy Policy Act 2005: All facilities sub-metered by 2012 $$ no longer restricts metering project Metering Criteria prior to EPACT 2005 All New Construction - (per Air Force Instructions)
Report on Modeling Coupled Processes in the Near Field of a Clay Repository
on Modeling Coupled Processes in the Near Field of a Clay on Modeling Coupled Processes in the Near Field of a Clay Repository Report on Modeling Coupled Processes in the Near Field of a Clay Repository Clay/shale has been considered as potential host rock for geological disposal of high-level radioactive waste throughout the world. Coupled thermal, hydrological, mechanical, and chemical (THMC) processes have a significant impact on the long-term safety of a clay repository. This report documents results from three R&D activities: (1) implementation and validation of constitutive relationships, (2) development of a discrete fracture network (DFN) model for investigating coupled processes in the excavation damaged zone, and (3) development of a THM model for the Full-Scale Emplacement Experiment tests at Mont Terri, Switzerland, for the
Coupled Model for Heat and Water Transport in a High Level Waste Repository
Coupled Model for Heat and Water Transport in a High Level Waste Coupled Model for Heat and Water Transport in a High Level Waste Repository in Salt Coupled Model for Heat and Water Transport in a High Level Waste Repository in Salt This report summarizes efforts to simulate coupled thermal-hydrological-chemical (THC) processes occurring within a generic hypothetical high-level waste (HLW) repository in bedded salt; chemical processes of the system allow precipitation and dissolution of salt with elevated temperatures that drive water and water vapor flow around hot waste packages. Characterizing salt backfill processes is an important objective of the exercise. An evidence-based algorithm for mineral dehydration is also applied in the modeling. The Finite Element Heat and Mass transfer code (FEHM) is used to simulate coupled thermal,
MemBeR: A Micro-benchmark Repository for XQuery
Abstract. XQuery is a feature-rich language with complex semantics. This makes it hard to come up with a benchmark suite which covers all performance-critical features of the language, and at the same time allows one to individually validate XQuery evaluation techniques. This paper presents MemBeR, a micro-benchmark repository, allowing the evaluation of an XQuery implementation with respect to precise evaluation techniques. We take the view that a fixed set of queries is probably insufficient to allow testing for various performance aspects, thus, the users of the repository must be able to add new data sets and/or queries for specific performance assessment tasks. We present our methodology for constructing the micro-benchmark repository, and illustrate with some sample micro-benchmarks. 1
Loredana Afanasiev; Ioana Manolescu
Source terms for analysis of accidents at a high level waste repository
This paper describes an approach to identifying source terms from possible accidents during the preclosure phase of a high-level nuclear waste repository. A review of the literature on repository safety analyses indicated that source term estimation is in a preliminary stage, largely based on judgement-based scoping analyses. The approach developed here was to partition the accident space into domains defined by certain threshold values of temperature and impact energy density which may arise in potential accidents and specify release fractions of various radionuclides, present in the waste form, in each domain. Along with a more quantitative understanding of accident phenomenology, this approach should help in achieving a clearer perspective on scenarios important to preclosure safety assessments of geologic repositories. 18 refs., 3 tabs.
Mubayi, V.; Davis, R.E.; Youngblood, R.
Conceptual model for regional radionuclide transport from a salt dome repository: a technical memorandum
Disposal of high-level radioactive wastes is a major environmental problem influencing further development of nuclear energy in this country. Salt domes in the Gulf Coast Basin are being investigated as repository sites. A major concern is geologic and hydrologic stability of candidate domes and potential transport of radionuclides by groundwater to the biosphere prior to their degradation to harmless levels of activity. This report conceptualizes a regional geohydrologic model for transport of radionuclides from a salt dome repository. The model considers transport pathways and the physical and chemical changes that would occur through time prior to the radionuclides reaching the biosphere. Necessary, but unknown inputs to the regional model involve entry and movement of fluids through the repository dome and across the dome-country rock interface and the effect on the dome and surrounding strata of heat generated by the radioactive wastes.
Kier, R.S.; Showalter, P.A.; Dettinger, M.D.
Portable data collection device
The present invention provides a portable data collection device that has a variety of sensors that are interchangeable with a variety of input ports in the device. The various sensors include a data identification feature that provides information to the device regarding the type of physical data produced by each sensor and therefore the type of sensor itself. The data identification feature enables the device to locate the input port where the sensor is connected and self adjust when a sensor is removed or replaced. The device is able to collect physical data, whether or not a function of a time.
French, Patrick D. (Aurora, CO)
Collectivity, chaos, and computers
Two important pieces of nuclear structure are many-body collective deformations and single-particle spin-orbit splitting. The former can be well-described microscopically by simple SU(3) irreps, but the latter mixes SU(3) irreps, which presents a challenge for large-scale, ab initio calculations on fast modern computers. Nonetheless, SU(3)-like phenomenology remains even in the face of strong mixing. The robustness of band structure is reminiscent of robust, pairing collectivity that arises from random two-body interactions.
Calvin W. Johnson
Methods of calculating the post-closure performance of high-level waste repositories
This report is intended as an overview of post-closure performance assessment methods for high-level radioactive waste repositories and is designed to give the reader a broad sense of the state of the art of this technology. As described here, ''the state of the art'' includes only what has been reported in report, journal, and conference proceedings literature through August 1987. There is a very large literature on the performance of high-level waste repositories. In order to make a review of this breadth manageable, its scope must be carefully defined. The essential principle followed is that only methods of calculating the long-term performance of waste repositories are described. The report is organized to reflect, in a generalized way, the logical order to steps that would be taken in a typical performance assessment. Chapter 2 describes ways of identifying scenarios and estimating their probabilities. Chapter 3 presents models used to determine the physical and chemical environment of a repository, including models of heat transfer, radiation, geochemistry, rock mechanics, brine migration, radiation effects on chemistry, and coupled processes. The next two chapters address the performance of specific barriers to release of radioactivity. Chapter 4 treats engineered barriers, including containers, waste forms, backfills around waste packages, shaft and borehole seals, and repository design features. Chapter 5 discusses natural barriers, including ground water systems and stability of salt formations. The final chapters address optics of general applicability to performance assessment models. Methods of sensitivity and uncertainty analysis are described in Chapter 6, and natural analogues of repositories are treated in Chapter 7. 473 refs., 19 figs., 2 tabs.
Ross, B. (ed.)
Potential Igneous Processes Relevant to the Yucca Mountain Repository: Intrusive-Release Scenario
The Department of Energy (DOE) is moving to prepare and submit a license application to initiate construction of the geologic repository at Yucca Mountain. As part of the application, the DOE must provide estimates of the dose risk to a local population caused by low-probability intrusions of volcanic magma that may occur into the repository after closure. To date, published estimates of such dose risks have included a large number of conservative assumptions such that it appears as if the igneous intrus...
Oil Shale Development from the Perspective of NETL's Unconventional Oil Resource Repository
The history of oil shale development was examined by gathering relevant research literature for an Unconventional Oil Resource Repository. This repository contains over 17,000 entries from over 1,000 different sources. The development of oil shale has been hindered by a number of factors. These technical, political, and economic factors have brought about R&D boom-bust cycles. It is not surprising that these cycles are strongly correlated to market crude oil prices. However, it may be possible to influence some of the other factors through a sustained, yet measured, approach to R&D in both the public and private sectors.
Smith, M.W. (REM Engineering Services, Morgantown, WV); Shadle, L.J.; Hill, D. (REM Engineering Services, Morgantown, WV)
Designing a secure storage repository for sharing scientific datasets using public clouds
As Cloud platforms gain increasing traction among scientific and business communities for outsourcing storage, computing and content delivery, there is also growing concern about the associated loss of control over private data hosted in the Cloud. In ... Keywords: access control, data repository, eEngineering, public clouds, secure cloud storage
Alok Gautam Kumbhare; Yogesh Simmhan; Viktor Prasanna
Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository
This paper reviews the state-of-the-art understanding of the degradation processes by the Yucca Mountain Project (YMP) with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the first 10,000-years after repository closure. This paper provides an overview of the degradation of the waste packages and drip shields in the repository after permanent closure of the facility. The degradation modes discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking, and hydrogen induced cracking of Alloy 22 and titanium alloys. The effects of microbial activity and radiation on the degradation of Alloy 22 and titanium alloys are also discussed. Further, for titanium alloys, the effects of fluorides, bromides, and galvanic coupling to less noble metals are considered. It is concluded that the materials and design adopted will provide sufficient safety margins for at least 10,000-years after repository closure.
K.G. Mon; F. Hua
Adopting softer approaches in the study of repository data: a comparative analysis
Context: Given the acknowledged need to understand the people processes enacted during software development, software repositories and mailing lists have become a focus for many studies. However, researchers have tended to use mostly mathematical ... Keywords: Jazz, communication, content analysis, psycholinguistics, software teams
Sherlock A. Licorish; Stephen G. MacDonell
Limits on the thermal energy release from radioactive wastes in a mined geologic repository
The theraml energy release of nuclear wastes is a major factor in the design of geologic repositories. Thermal limits need to be placed on various aspets of the geologic waste disposal system to avoid or retard the degradation of repository performance because of increased temperatures. The thermal limits in current use today are summarized in this report. These limits are placed in a hierarchial structure of thermal criteria consistent with the failure mechanism they are trying to prevent. The thermal criteria hierarchy is used to evaluate the thermal performance of a sample repository design. The design consists of disassembled BWR spent fuel, aged 10 years, close packed in a carbon steel canister with 15 cm of crushed salt backfill. The medium is bedded salt. The most-restrictive temperature for this design is the spent-fuel centerline temperature limit of 300/sup 0/C. A sensitivity study on the effects of additional cooling prior to disposal on repository thermal limits and design is performed.
Scott, J.A.
The Analytical Repository Source-Term (AREST) model: Description and documentation
The geologic repository system consists of several components, one of which is the engineered barrier system. The engineered barrier system interfaces with natural barriers that constitute the setting of the repository. A model that simulates the releases from the engineered barrier system into the natural barriers of the geosphere, called a source-term model, is an important component of any model for assessing the overall performance of the geologic repository system. The Analytical Repository Source-Term (AREST) model being developed is one such model. This report describes the current state of development of the AREST model and the code in which the model is implemented. The AREST model consists of three component models and five process models that describe the post-emplacement environment of a waste package. All of these components are combined within a probabilistic framework. The component models are a waste package containment (WPC) model that simulates the corrosion and degradation processes which eventually result in waste package containment failure; a waste package release (WPR) model that calculates the rates of radionuclide release from the failed waste package; and an engineered system release (ESR) model that controls the flow of information among all AREST components and process models and combines release output from the WPR model with failure times from the WPC model to produce estimates of total release. 167 refs., 40 figs., 12 tabs.
Liebetrau, A.M.; Apted, M.J.; Engel, D.W.; Altenhofen, M.K.; Strachan, D.M.; Reid, C.R.; Windisch, C.F.; Erikson, R.L.; Johnson, K.I.
Towards a knowledge repository for collaborative design process: focus on conflict management
The increasing competition and complexity of products and processes require new organizational concepts for product development. Collaborative design deals with the sharing of various interests and resources among various actors with the aim of reaching ... Keywords: Collaborative design, Conflict management, Knowledge repository
L. Gzara Yesilbas; M. Lombard
Geochemical modeling of the nuclear-waste repository system. A status report
The primary objective of the geochemical modeling task is to develop an understanding of the waste-repository geochemical system and provide a valuable tool for estimating future states of that system. There currently exists a variety of computer codes which can be used in geochemical modeling studies. Some available codes contain the framework for simulating a natural chemical system and estimating, within limits, the response of that system to environmental changes. By data-base enhancement and code development, this modeling technique can be even more usefully applied to a nuclear-waste repository. In particular, thermodynamic data on elements not presently in the data base but identified as being of particular hazard in the waste-repository system, need to be incorporated into the code to estimate the near-field as well as the far-field reactions during a hypothetical breach. A reaction-path-simulation code, which estimates the products of specific rock/water reactions, has been tested using basalt and ground water. Results show that the mass-transfer capabilities of the code will be useful in chemical-evolution studies and scenario analyses. The purpose of this report is to explain the status of geochemical modeling as it currently applies to the chemical system of a hypothetical nuclear-waste repository in basalt and to present the plan proposed for further developmet and application.
Deutsch, W.J.
Leveraging usage similarity for effective retrieval of examples in code repositories
Developers often learn to use APIs (Application Programming Interfaces) by looking at existing examples of API usage. Code repositories contain many instances of such usage of APIs. However, conventional information retrieval techniques fail to perform ... Keywords: api usage, code search, software information retrieval, ssi, structural semantic indexing
Sushil K. Bajracharya; Joel Ossher; Cristina V. Lopes
Role of groundwater oxidation potential and radiolysis on waste glass performance in crystalline repository environments
Laboratory experiments have shown that groundwater conditions in a Stripa granite repository will be as reducing as those in a basalt repository. The final oxidation potential (Eh) at 70/sup 0/C for Stripa groundwater deaerated and equilibrated with crystalline granite was -0.45V. In contrast, the oxidation potential at 60/sup 0/C for Grande Ronde groundwater equilibrated with basalt was -0.40V. The reducing groundwater conditions were found to slightly decrease the time-dependent release of soluble components from the waste glass. Spectrophotometric analysis of the equilibrated groundwaters indicated the presence of Fe/sup 2 +/ confirming that the Fe/sup 2 +//Fe/sup 3 +/ couple is controlling the oxidation potential. It was also shown that in the alkaline pH regime of these groundwaters the iron species are primarily associated with x-ray amorphous precipitates in the groundwater. Gamma radiolysis in the absence of waste glass and in the absence of oxygen further reduces the oxidation potential of both granitic and basaltic groundwaters. The effect is more pronounced in the basaltic groundwater. The mechanism for this decrease is under investigation but appears related to the reactive amorphous precipitate. The results of these tests suggest that H/sub 2/ may not escape from the repository system as postulated and that radiolysis may not cause the groundwaters to become oxidizing in a crystalline repository when abundant Fe/sup 2 +/ species are present. 23 refs., 3 figs., 3 tabs.
Jantzen, C M; Bibler, N E
Interacting with local and remote data repositories using the stashR package
The stashR package (a Set of Tools for Administering Shared Repositories) for R implements a basic versioned key-value style database where character string keys are associated with data values. Using the S4 classes �localDB� and ... Keywords: Data distribution, Database, Version control
Sandrah P. Eckel; Roger D. Peng
Determination of Importance Evaluation for the ESF Enhanced Charcterization of the Repository Block Cross Drift
The objective of this DIE is to determine whether the ECRB-Cross-Drift-related activities, as identified in Section 6.0, could potentially impact (1) Yucca Mountain Site Characterization Project (YMP) testing or (2) the waste isolation capabilities of a potential repository at the Yucca Mountain site. Any controls necessary to limit such potential impacts are also identified herein.
S. Goodin
Efficacy of backfilling and other engineered barriers in a radioactive waste repository in salt
In the United States, investigation of potential host geologic formations was expanded in 1975 to include hard rocks. Potential groundwater intrusion is leading to very conservative and expensive waste package designs. Recent studies have concluded that incentives for engineered barriers and 1000-year canisters probably do not exist for reasonable breach scenarios. The assumption that multibarriers will significantly increase the safety margin is also questioned. Use of a bentonite backfill for surrounding a canister of exotic materials was developed in Sweden and is being considered in the US. The expectation that bentonite will remain essentially unchanged for hundreds of years for US repository designs may be unrealistic. In addition, thick bentonite backfills will increase the canister surface temperature and add much more water around the canister. The use of desiccant materials, such as CaO or MgO, for backfilling seems to be a better method of protecting the canister. An argument can also be made for not using backfill material in salt repositories since the 30-cm-thick space will provide for hole closure for many years and will promote heat transfer via natural convection. It is concluded that expensive safety systems are being considered for repository designs that do not necessarily increase the safety margin. It is recommended that the safety systems for waste repositories in different geologic media be addressed individually and that cost-benefit analyses be performed.
Claiborne, H.C.
The multi-faceted use of the OAI-PMH in the LANL repository
This paper focuses on the multifaceted use of the OAI-PMH in a repository architecture designed to store digital assets at the Research Library of the Los Alamos National Laboratory (LANL), and to make the stored assets available in a uniform way to various downstream applications. In the architecture, the MPEG-21 Digital Item Declaration Language is used as the XML-based format to represent complex digital objects. Upon ingestion, these objects are stored in a multitude of autonomous OAI-PMH repositories. An OAI-PMH compliant Repository Index keeps track of the creation and location of all those repositories, whereas an Identifier Resolver keeps track of the location of individual objects. An OAI-PMH Federator is introduced as a single-point-of-access to downstream harvesters. It hides the complexity of the environment to those harvesters, and allows them to obtain transformations of stored objects. While the proposed architecture is described in the context of the LANL library, the paper will also touch on its more general applicability.
Henry N. Jerez; Xiaoming Liu; Patrick Hochstenbach
The multi-faceted use of the OAI-PMH in the lanl repository
This paper focuses on the multifaceted use of the OAI-PMH in a repository architecture designed to store digital assets at the Research Library of the Los Alamos National Laboratory (LANL), and to make the stored assets available in a uniform way to ... Keywords: OAI-PMH, digital libraries, federation, interoperability
Henry N. Jerez; Xiaoming Liu; Patrick Hochstenbach; Herbert Van de Sompel
For immediate release National Library Board and The Institution of Engineers Singapore Build Partnership for Engineering Repository, Education and Knowledge
Singapore (IES) to bring a wealth of engineering information and knowledge to professional engineers, students and the general public. This is NLB�s first partnership with a professional body in Singapore. �The partnership brings together the strengths of both NLB and IES in a synergistic manner to benefit all parties. The engineering community will benefit from the use of the reference collections in the Lee Kong Chian Reference Library at the National Library. IES � knowledge domain in engineering science will help us in building a network of knowledge assets, � said Dr N. Varaprasad, Chief Executive, NLB. (to be confirmed) Under this Memorandum of Understanding (MOU), NLB and IES will be collaborating on three key areas: 1. Engineering Repository @ Lee Kong Chian Reference Library � Jointly providing information services in print, audiovisual and electronic formats, codes of practice and reference materials on the engineering sciences, relevant to practising engineers, students and the general public. 2. Engineering Education and Knowledge @ NLB Public Libraries � Jointly conduct regular talks, seminars, conferences and training courses on engineering topics that are of interest to practising engineers, engineering students and the general public.
Effects of resource activities upon repository siting and waste containment with reference to bedded salt
The primary consideration for the suitability of a nuclear waste repository site is the overall ability of the repository to safely contain radioactive waste. This report is a discussion of the past, present, and future effects of resource activities on waste containment. Past and present resource activities which provide release pathways (i.e., leaky boreholes, adjacent mines) will receive initial evaluation during the early stages of any repository site study. However, other resource activities which may have subtle effects on containment (e.g., long-term pumping causing increased groundwater gradients, invasion of saline water causing lower retardation) and all potential future resource activities must also be considered during the site evaluation process. Resource activities will affect both the siting and the designing of repositories. Ideally, sites should be located in areas of low resource activity and low potential for future activity, and repository design should seek to eliminate or minimize the adverse effects of any resource activity. Buffer zones should be created to provide areas in which resource activities that might adversely affect containment can be restricted or curtailed. This could mean removing large areas of land from resource development. The impact of these frozen assets should be assessed in terms of their economic value and of their effect upon resource reserves. This step could require a major effort in data acquisition and analysis followed by extensive numerical modeling of regional fluid flow and mass transport. Numerical models should be used to assess the effects of resource activity upon containment and should include the cumulative effects of different resource activities. Analysis by other methods is probably not possible except for relatively simple cases.
Ashby, J.; Rowe, J.
Garbage Collecting the World
Distributed symbolic computations involve the existence of remote references allowing an object, local to a processor, to designate another object located on another processor. To reclaim inaccessible objects is the non trivial task of a distributed Garbage Collector (GC). We present in this paper a new distributed GC algorithm which (i) is faulttolerant, (ii ) is largely independent of how a processor garbage collects its own data space, (iii ) does not need centralized control nor global stop-the-world synchronization, (iv) allows for multiple concurrent active GCs, (v) does not require to migrate objects from processor to processor and (vi) eventually reclaims all inaccessible objects including distributed cycles. These results are mainly obtained through the concept of a group of processors (or processes). Processors of a same group cooperate together to a GC inside this group; this GC is conservative with respect to the outside of the group. A processor contributes to the glob...
Bernard Lang; Christian Queinnec; Jos� Piquer
A network-accessible repository for petroleum reservoir information
Researchers from Montana Tech, the University of Montana, and Montana State University are currently collaborating with commercial partners to collect and analyze data from the Rabbit Hills oil field near Chinook, Montana. The data accumulated from this project are in various familiar forms, such as 3-D seismic datasets, 35 mm slides of outcroppings and core samples, imagery of rock/core thin sections, well logs, production history datasets, and computer generated maps derived from seismic and well log analysis. Also included is computer generated imagery representing the visualization of various datasets, in the form of animations (with accompanying audio) that depict fly-throughs of geologic structures, cumulative oil production over time from wells in the field, and fanning through seismic time slices. It is critical to the project`s success to establish a way for participants that are widely distributed geographically to contribute information and access information contributed by others. Modern Internet/World Wide Web technology makes this sort of data contribution and dissemination feasible for all the types of information listed above. The presentation will focus on the key technical decisions made in structuring and maintaining a Web site with these diverse types of data.
Ford, R.; Thompson, D.; Braun, J. [Univ. of Montana, Missoula, MT (United States)
Mobility-supporting data management for location-based mobile systems: the special case of single category location repositories
Location-based mobile applications require timely generation of user-centric proximities from application-relevant repositories of business locations. The proximity generation requirement is poorly served by conventional query resolution methods which ...
James E. Wyse
DOE Hydrogen Analysis Repository: HyDRA: Hydrogen Demand and Resource
HyDRA: Hydrogen Demand and Resource Analysis Tool HyDRA: Hydrogen Demand and Resource Analysis Tool Project Summary Full Title: HyDRA: Hydrogen Demand and Resource Analysis Tool Project ID: 220 Principal Investigator: Johanna Levene Brief Description: HyDRA has evolved from a basic display of spatial data to a repository of over 100 datasets with dynamic data, querying, and interoperability with other models and spatial data repositories and over 350 registered users. Keywords: Hydrogen infrastructure; wind; solar; biomass; coal; natural gas Purpose Facilitate regional and geographical analyses of resources, demand, and infrastructure relevant to the implementation of hydrogen production, delivery, and dispensing. Performer Principal Investigator: Johanna Levene Organization: National Renewable Energy Laboratory (NREL)
A Review Corrosion of TI Grade 7 and Other TI Alloys in Nuclear Waste Repository Environments
Titanium alloy degradation modes are reviewed in relation to their performance in repository environments. General corrosion, localized corrosion, stress corrosion cracking, hydrogen induced cracking, microbially influenced corrosion, and radiation-assisted corrosion of Ti alloys are considered. With respect to the Ti Grade 7 drip shields selected for emplacement in the repository at Yucca Mountain, general corrosion, hydrogen induced cracking, and radiation-assisted corrosion will not lead to failure within the 10,000 year regulatory period; stress corrosion cracking (in the absence of disruptive events) is of no consequence to barrier performance; and localized corrosion and microbially influenced corrosion are not expected to occur. To facilitate the discussion, Ti Grades 2, 5, 7, 9, 11, 12, 16, 17, 18, and 24 are included in this review.
F. Hua; K. Mon; P. Pasupathi; G. Gordon
RECON: a computer program for analyzing repository economics. Documentation and user's manual. Revision 1
From 1981 through 1984 the Pacific Northwest Laboratory has been developing a computer model named RECON to calculate repository costs from parametric data input. The objective of the program has been to develop the capability to evaluate the effect on costs of changes in repository design parameters and operating scenario assumptions. This report documents the development of the model through September of 1984. Included in the report are: (1) descriptions of model development and the underlying equations, assumptions and definitions; (2) descriptions of data input using either card images or an interactive data input program; and (3) detailed listings of the program and definitions of program variables. Cost estimates generated using the model have been verified against independent estimates and good agreement has been obtained. 2 refs.
Clark, L.L.; Schutz, M.E.; Luksic, A.T.
Selection and durability of seal materials for a bedded salt repository: preliminary studies
This report details preliminary results of both experimental and theoretical studies of cementitious seal materials for use in a proposed nuclear waste repository in bedded salt. Effects of changes in bulk composition and environment upon phase stability and physical/mechanical properties have been evaluated for more than 25 formulations. Bonding and interfacial characteristics of the region between host rock and seal material or concrete aggregate and cementitious matrix for selected formulations have been studied. Compatibilities of clays and zeolites in brines typical of the SE New Mexico region have been investigated, and their stabilities reviewed. Results of these studies have led to the conclusion that cementitious materials can be formulated which are compatible with the major rock types in a bedded salt repository environment. Strengths are more than adequate, permeabilities are consistently very low, and elastic moduli generally increase only very slightly with time. Seal formulation guidelines and recommendations for present and future work are presented. 73 references, 25 figures, 61 tables.
Roy, D.M.; Grutzeck, M.W.; Wakeley, L.D.
MRS system study for the repository: Yucca Mountain Site Characterization Project; Volume 2
The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), has initiated a waste management system study to identify the impacts of the presence or absence of a monitored retrievable storage facility (hereinafter referred to as ``MRS``) on system costs and program schedules. To support this study, life-cycle cost estimates and construction schedules have been prepared for the surface and underground facilities and operations geologic nuclear waste repository at Yucca Mountain, Nye County, Nevada. Nine different operating scenarios (cases) have been identified by OCRWM for inclusion in this study. For each case, the following items are determined: the repository design and construction costs, operating costs, closure and decommissioning costs, required staffing, construction schedules, uncertainties associated with the costs and schedules, and shipping cask and disposal container throughputs. This document contains A-D.
Sinagra, T.A. [Bechtel National, Inc., San Francisco, CA (USA); Harig, R. [Parsons, Brinckerhoff, Quade and Douglas, Inc., San Francisco, CA (USA)
Building Component Library: An Online Repository to Facilitate Building Energy Model Creation; Preprint
This paper describes the Building Component Library (BCL), the U.S. Department of Energy's (DOE) online repository of building components that can be directly used to create energy models. This comprehensive, searchable library consists of components and measures as well as the metadata which describes them. The library is also designed to allow contributors to easily add new components, providing a continuously growing, standardized list of components for users to draw upon.
Fleming, K.; Long, N.; Swindler, A.
Engineered barrier development for a nuclear waste repository in basalt: an integration of current knowledge
This document represents a compilation of data and interpretive studies conducted as part of the engineered barriers program of the Basalt Waste Isolation Project. The overall objective of these studies is to provide information on barrier system designs, emplacement and isolation techniques, and chemical reactions expected in a nuclear waste repository located in the basalts underlying the Hanford Site within the state of Washington. Backfills, waste-basalt interactions, sorption, borehole plugging, etc., are among the topics discussed.
Smith, M.J.
Expected environments in high-level nuclear waste and spent fuel repositories in salt
The purpose of this report is to describe the expected environments associated with high-level waste (HLW) and spent fuel (SF) repositories in salt formations. These environments include the thermal, fluid, pressure, brine chemistry, and radiation fields predicted for the repository conceptual designs. In this study, it is assumed that the repository will be a room and pillar mine in a rock-salt formation, with the disposal horizon located approx. 2000 ft (610 m) below the surface of the earth. Canistered waste packages containing HLW in a solid matrix or SF elements are emplaced in vertical holes in the floor of the rooms. The emplacement holes are backfilled with crushed salt or other material and sealed at some later time. Sensitivity studies are presented to show the effect of changing the areal heat load, the canister heat load, the barrier material and thickness, ventilation of the storage room, and adding a second row to the emplacement configuration. The calculated thermal environment is used as input for brine migration calculations. The vapor and gas pressure will gradually attain the lithostatic pressure in a sealed repository. In the unlikely event that an emplacement hole will become sealed in relatively early years, the vapor space pressure was calculated for three scenarios (i.e., no hole closure - no backfill, no hole closure - backfill, and hole closure - no backfill). It was assumed that the gas in the system consisted of air and water vapor in equilibrium with brine. A computer code (REPRESS) was developed assuming that these changes occur slowly (equilibrium conditions). The brine chemical environment is outlined in terms of brine chemistry, corrosion, and compositions. The nuclear radiation environment emphasized in this report is the stored energy that can be released as a result of radiation damage or crystal dislocations within crystal lattices.
Claiborne, H.C.; Rickertsen, L.D., Graham, R.F.
Evaluation of a Spent Fuel Repository at Yucca Mountain, Nevada: 2004 Progress Report
Following completion of the site characterization and site recommendation phases, the Department of Energy (DOE) is moving to prepare and submit a license application to initiate construction of the geologic repository at Yucca Mountain. This report provides background on how the project arrived at this juncture in its history and detailed information on EPRI's Yucca Mountain-related activities during calendar year 2004. The report summarizes EPRI work completed and in progress on evaluation of igneous c...
Performance Confirmation for the Candidate Yucca Mountain High-Level Nuclear Waste Repository: Final Report -- December 2001
The U.S. Department of Energy (DOE) secretary, the President, and Congress may soon consider whether to allow the DOE to proceed into the formal licensing process with the Yucca Mountain high-level nuclear waste repository site. A long-term research and development (R&D) and performance confirmation program can provide substantially more confidence that the correct decisions are being made at each stage of repository development. It is necessary, however, to make sure that the confirmation program will, ...
MRS/IS facility co-located with a repository: preconceptual design and life-cycle cost estimates
A program is described to examine the various alternatives for monitored retrievable storage (MRS) and interim storage (IS) of spent nuclear fuel, solidified high-level waste (HLW), and transuranic (TRU) waste until appropriate geologic repository/repositories are available. The objectives of this study are: (1) to develop a preconceptual design for an MRS/IS facility that would become the principal surface facility for a deep geologic repository when the repository is opened, (2) to examine various issues such as transportation of wastes, licensing of the facility, and environmental concerns associated with operation of such a facility, and (3) to estimate the life cycle costs of the facility when operated in response to a set of scenarios which define the quantities and types of waste requiring storage in specific time periods, which generally span the years from 1990 until 2016. The life cycle costs estimated in this study include: the capital expenditures for structures, casks and/or drywells, storage areas and pads, and transfer equipment; the cost of staff labor, supplies, and services; and the incremental cost of transporting the waste materials from the site of origin to the MRS/IS facility. Three scenarios are examined to develop estimates of life cycle costs of the MRS/IS facility. In the first scenario, HLW canisters are stored, starting in 1990, until the co-located repository is opened in the year 1998. Additional reprocessing plants and repositories are placed in service at various intervals. In the second scenario, spent fuel is stored, starting in 1990, because the reprocessing plants are delayed in starting operations by 10 years, but no HLW is stored because the repositories open on schedule. In the third scenario, HLW is stored, starting in 1990, because the repositories are delayed 10 years, but the reprocessing plants open on schedule.
Smith, R.I.; Nesbitt, J.F.
Collective systems for creative expression
This thesis defines collective systems as a unique category of creative expression through the procedures of micro and macro cycles that address the transition from connectivity to collectivity. This thesis discusses the ...
Ar?kan, Harun Burak
Modeling Hydrogen-Induced Cracking of Titanium Alloys in Nuclear Waste Repository Environments
This paper reviews the current understanding of hydrogen-induced cracking (HIC) of Ti Grade 7 and other relevant titanium alloys within the context of the current waste package design for the repository environmental conditions anticipated within the Yucca Mountain repository. The review concentrates on corrosion processes possible in the aqueous environments expected within this site. A brief background discussion of the relevant properties of titanium alloys, the hydrogen absorption process, and the properties of passive film on titanium alloys is presented as the basis for the subsequent discussion of model developments. The key corrosion processes that could occur are addressed individually. Subsequently, the expected corrosion performance of these alloys under the specific environmental conditions anticipated at Yucca Mountain is considered. It can be concluded that, based on the conservative modeling approaches adopted, hydrogen-induced cracking of titanium alloys will not occur under nuclear waste repository conditions since there will not be sufficient hydrogen in the alloy after 10,000 years of emplacement.
Proceedings of a workshop on uses of depleted uranium in storage, transportation and repository facilities
A workshop on the potential uses of depleted uranium (DU) in the repository was organized to coordinate the planning of future activities. The attendees, the original workshop objective and the agenda are provided in Appendices A, B and C. After some opening remarks and discussions, the objectives of the workshop were revised to: (1) exchange information and views on the status of the Department of Energy (DOE) activities related to repository design and planning; (2) exchange information on DU management and planning; (3) identify potential uses of DU in the storage, transportation, and disposal of high-level waste and spent fuel; and (4) define the future activities that would be needed if potential uses were to be further evaluated and developed. This summary of the workshop is intended to be an integrated resource for planning of any future work related to DU use in the repository. The synopsis of the first day`s presentations is provided in Appendix D. Copies of slides from each presenter are presented in Appendix E.
Independent Analysis of Seismicity and Rock fall Scenarios for the Yucca Mountain Repository
Yucca Mountain is located in the somewhat seismically active Basin and Range province. Future seismic activity is identified by the US Nuclear Regulatory Commission and the US National Academy of Sciences as a key scenario for safety assessment of a proposed repository at Yucca Mountain. As part of its on-going program of conducting independent analyses of scientific and technical issues that could be important to the licensing of the Yucca Mountain repository, EPRI has conducted an analysis of the combined scenarios of seismic activity and stability of emplacement drifts with respect to the long-term repository safety. In this paper we present the results of 3D finite element simulations of both static and dynamic loading of a degraded waste package. For the static case, the expected maximum static load is determined by utilizing relationships between cave height and the bulking factor. A static load representing 30 meters of broken rock was simulated using the finite element model. For the dynamic case, block size and velocity data from the most recent Drift Degradation AMR are used. Based on this, a rock block with a volume of 3.11 m{sup 3} and with an impact velocity of 4.81 m/s was simulated using the finite element model. In both cases, the results indicate that the waste package remains intact. (authors)
Apted, M.J. [Monitor Scientific, 3900 S. Wadsworth Blvd., Denver, CO 80235 (United States); Kemeny, J.M. [University of Arizona, Dept. Mining and Geological Engineering, Tucson, AZ 85721 (United States); Martin, C.D. [University of Alberta, Dept. Civil and Environmental Engineering, Edmonton, AB T6G 2W2 (Canada); James, R.J. [Anatech Corp., 5435 Oberlin Dr., San Diego, CA 92121 (United States)
Stress-corrosion-cracking studies on candidate container alloys for the Tuff Repository
Cortest Columbus Technologies, Inc. (CC Technologies) investigated the long-term performance of container materials used for high-level waste package as part of the information needed by the Nuclear Regulatory Commission (NRC) to assess the Department of Energy`s application to construct to geologic repository for high-level radioactive waste. At the direction of the NRC, the program focused on the Tuff Repository. This report summarizes the results of Stress-Corrosion-Cracking (SCC) studies performed in Tasks 3, 5, and 7 of the program. Two test techniques were used; U-bend exposures and Slow-Strain-Rate (SSR) tests. The testing was performed on two copper-base alloys (Alloy CDA 102 and Alloy CDA 175) and two Fe-Cr-Ni alloys (Alloy 304L and Alloy 825) in simulated J-13 groundwater and other simulated solutions for the Tuff Repository. These solutions were designed to simulate the effects of concentration and irradiation on the groundwater composition. All SCC testing on the Fe-Cr-Ni Alloys was performed on solution-annealed specimens and thus issues such as the effect of sensitization on SCC were not addressed.
Beavers, J.A.; Durr, C.L. [Cortest Columbus Technologies, Inc., OH (United States)
Chameleon: adaptive selection of collections
Languages such as Java and C#, as well as scripting languages like Python, and Ruby, make extensive use of Collection classes. A collection implementation represents a fixed choice in the dimensions of operation time, space utilization, and synchronization. ... Keywords: bloat, collections, java, semantic profiler
Ohad Shacham; Martin Vechev; Eran Yahav
ADVANTG Shielding Analysis for Closure Operations in an Open-Mode Repository
en-mode repository concepts could require worker entry into access drifts after placement of fuel casks in order to perform activities related to backfill, plug emplacement, routine maintenance, or performance confirmation. An ideal emplacement-drift shielding configuration would minimize dose to workers while maximizing airflow through the emplacement drifts. This paper presents a preliminary investigation of the feasibility and effectiveness of radiation shielding concepts that could be employed to facilitate worker operations in an open-mode repository. The repository model for this study includes pressurized-water reactor fuel assemblies (60 GWd/MTU burnup, 40 year post-irradiation cooldown) in packages of 32 assemblies. The closest fuel packages are 5 meters from dosimetry voxels in the access drift. The unshielded dose to workers in the access drift is 73.7 rem/hour. Prior work suggests that open-mode repository concepts similar to this one would require 15 m3/s of ventilation airflow. Shielding concepts considered here include partial concrete plugs, labyrinthine shields, and stainless steel photon attenuator grids. Maximum dose to workers in the access drift was estimated for each shielding concept using MCNP5 with variance reduction parameters generated by ADVANTG. Because airflow through the shielding is important for open-mode repositories, a semi-empirical estimate of the head loss due to each shielding configuration was also calculated. Airflow and shielding performance vary widely among the proposed shielding configurations. Although the partial plug configuration had the best airflow performance, it allowed dose rates 1500 greater than the specified target. Labyrinthine shielding concepts yield doses on the order of 1 mrem/hour with configurations that impose 3 to 11 J/kg head loss. Adding 1 cm lead lining to the airflow channels of labyrinthine designs further reduces the worker dose by 65% to 95%. Photon-attenuator concepts may reduce worker dose to as low as 29 mrem/hour with head loss on the order of 1.9 J/kg.
Bevill, Aaron M [ORNL; Radulescu, Georgeta [ORNL; Scaglione, John M [ORNL; Howard, Rob L [ORNL
Strategic Basis for License Application Planning for a Potential Yucca Mountain Repository
If Yucca Mountain, Nevada is designated as the site for development of a geologic repository for disposal of spent nuclear fuel and high-level radioactive waste, the Department of Energy (DOE) must obtain Nuclear Regulatory Commission (NRC) approval first for repository construction, then for an operating license, and, eventually, for repository closure and decommissioning. The licensing criteria defined in Code of Federal Regulations, Title 10, Part 63 (10 CFR Part 63) establish the basis for these NRC decisions. Submittal of a license application (LA) to the NRC for authorization to construct a repository at the Yucca Mountain site is, at this point, only a potential future action by the DOE. The policy process defined in the Nuclear Waste Policy Act (NWPA), as amended, for recommendation and designation of Yucca Mountain as a repository site makes it difficult to predict whether or when the site might be designated. The DOE may only submit a LA to the NRC if the site designation takes effect. In spite of this uncertainty, the DOE must take prudent and appropriate action now, and over the next several years, to prepare for development and timely submittal of a LA. This is particularly true given the need for the DOE to develop, load, and certify the operation of its electronic information system to provide access to its relevant records as part of the licensing support network (LSN) in compliance with NRC requirements six months prior to LA submittal. The DOE must also develop a LA, which is a substantially different document from those developed to support a Site Recommendation (SR) decision. The LA must satisfy NRC licensing criteria and content requirements, and address the acceptance criteria defined by the NRC in its forthcoming Yucca Mountain Review Plan (YMRP). The content of the LA must be adequate to facilitate NRC acceptance and docketing for review, and the LA and its supporting documents must provide the documented basis for the NR C findings required for a construction authorization. The LA must also support a licensing proceeding before an Atomic Safety and Licensing Board panel prior to NRC action on any decision to authorize construction. The DOE has established a strategic basis for planning that is intended to provide the framework for development of an integrated plan for activities leading to preparation and submittal of a LA.
Newberry, C. M.; Brocoum, S. J.; Gamble, R. P.; Murray, R. C.; Cline, M.
Standardized DOE Spent Nuclear Fuel Canister and Transportation System for Shipping to the National Repository
The U.S.Department of Energy�s (DOE) National Spent Nuclear Fuel Program (NSNFP), located at the Idaho National Engineering and Environmental Laboratory (INEEL), has been chartered with the responsibility for developing spent nuclear fuel (SNF) standardized canisters and a transportation cask system for shipping DOE SNF to the national repository. The mandate for this development is outlined in the Memorandum of Agreement for Acceptance of Department of Energy Spent Nuclear Fuel and High-Level Radioactive Waste that states, �EM shall design and fabricate � DOE SNF canisters for shipment to RW.� (1) It also states, �EM shall be responsible for the design, NRC certification, and fabrication of the transportation cask system for DOE SNF canisters or bare DOE SNF in accordance with 10 CFR Part 71.� (2) In fulfillment of these requirements, the NSNFP has developed four SNF standardized canister configurations and has conceptually designed a versatile transportation cask system for shipping the canisters to the national repository.1 The standardized canister sizes were derived from the national repository waste package design for co-disposal of SNF with high-level waste (HLW). One SNF canister can be placed in the center of the waste package or one can be placed in one of five radial positions, replacing a HLW canister. The internal cavity of the transportation cask was derived using the same logic, matching the size of the internal cavity of the waste package. The size of the internal cavity for the transportation cask allows the shipment of multiple canister configurations with the application of a removable basket design. The standardized canisters have been designed to be loaded with DOE SNF, placed into interim storage, shipped to the national repository, and placed in a waste package without having to be reopened. Significant testing has been completed that clearly demonstrates that the standardized canisters can safely achieve their intended design goals. The transportation cask system will include all of the standard design features, with the addition of dual containment for the shipment of failed fuel. The transportation cask system will also meet the rigorous licensing requirements of the Nuclear Regulatory Commission (NRC) to ensure that the design and the methods of fabrication employed will result in a shipping cask that will safely contain the radioactive materials under all credible accident scenarios. The standardization of the SNF canisters and the versatile design of the transportation cask system will eliminate a proliferation of designs and simplify the operations at the user sites and the national repository.
Pincock, David Lynn; Morton, Dana Keith; Lengyel, Arpad Leslie
Final Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada
TABLE OF CONTENTS Section Page 7. Repository Design, Performance, and Affected Environment .......................................................CR7-1 7.1 Repository Design ...........................................................................................................CR7-18 7.1.1 Draft EIS Repository Design ....................................................................................CR7-39 7.1.2 Supplement to the Draft EIS Flexible Design...........................................................CR7-62 18.104.22.168 Higher- and Lower-Temperature Operating Modes .................................................CR7-73 18.104.22.168 Ventilation.......................................................................................................CR7-74
Occupational Risk Consequences of the Department of Energy's Approach to Repository Design, Performance Assessment, and Operation in the Yucca Mountain License Application
EPRI has discovered several aspects of the U.S Department of Energy (DOE) proposed design and operation of the Yucca Mountain repository thatif implemented as described in the license application (LA)could result in unnecessary occupational health and safety risk to workers involved with repository-related activities. This report identifies key DOE conservatisms and focuses on the occupational risk consequences of the DOE's approach to the repository design, performance assessment, and operation.
EIA Electric Industry Data Collection
U.S. Energy Information Administration (EIA)
Steam Production EIA Electric Industry Data Collection Residential Industrial ... Monthly data on cost and quality of fuels delivered to cost-of-service plants
Recommendation by the Secretary of Energy Regarding the Suitability of the Yucca Mountain Site for a Repository Under the Nuclear Waste Policy Act of 1982
A case study on the influence of THM coupling on the near field safety of a spent fuel repository in sparsely fractured granite
geological disposal of spent CANDU fuel in Canada, a safetyhypothetical repository for spent CANDU fuel in the Canadianbuffer. The waste form: CANDU reactors in Canada are fuelled
Nguyen, T.S.
Tritium monitor and collection system
This system measures tritium on-line and collects tritium from a flowing inert gas stream. It separates the tritium from other non-hydrogen isotope contaminating gases, whether radioactive or not. The collecting portion of the system is constructed of various zirconium alloys called getters. These alloys adsorb tritium in any of its forms at one temperature and at a higher temperature release it as a gas. The system consists of four on-line getters and heaters, two ion chamber detectors, two collection getters, and two guard getters. When the incoming gas stream is valved through the on-line getters, 99.9% of it is adsorbed and the remainder continues to the guard getter where traces of tritium not collected earlier are adsorbed. The inert gas stream then exits the system to the decay chamber. Once the on-line getter has collected tritium for a predetermined time, it is valved off and the next on-line getter is valved on. Simultaneously, the first getter is heated and a pure helium purge is employed to carry the tritium from the getter. The tritium loaded gas stream is then routed through an ion chamber which measures the tritium activity. The ion chamber effluent passes through a collection getter that readsorbs the tritium and is removable from the system once it is loaded and is then replaced with a clean getter. Prior to removal of the collection getter, the system switches to a parallel collection getter. The effluent from the collection getter passes through a guard getter to remove traces of tritium prior to exiting the system. The tritium loaded collection getter, once removed, is analyzed by liquid scintillation techniques. The entire sequence is under computer control except for the removal and analysis of the collection getter. 7 figs.
Bourne, G.L.; Meikrantz, D.H.; Ely, W.E.; Tuggle, D.G.; Grafwallner, E.G.; Wickham, K.L.; Maltrud, H.R.; Baker, J.D.
This system measures tritium on-line and collects tritium from a flowing inert gas stream. It separates the tritium from other non-hydrogen isotope contaminating gases, whether radioactive or not. The collecting portion of the system is constructed of various zirconium alloys called getters. These alloys adsorb tritium in any of its forms at one temperature and at a higher temperature release it as a gas. The system consists of four on-line getters and heaters, two ion chamber detectors, two collection getters, and two guard getters. When the incoming gas stream is valved through the on-line getters, 99.9% of it is adsorbed and the remainder continues to the guard getter where traces of tritium not collected earlier are adsorbed. The inert gas stream then exits the system to the decay chamber. Once the on-line getter has collected tritium for a predetermined time, it is valved off and the next on-line getter is valved on. Simultaneously, the first getter is heated and a pure helium purge is employed to carry the tritium from the getter. The tritium loaded gas stream is then routed through an ion chamber which measures the tritium activity. The ion chamber effluent passes through a collection getter that readsorbs the tritium and is removable from the system once it is loaded and is then replaced with a clean getter. Prior to removal of the collection getter, the system switches to a parallel collection getter. The effluent from the collection getter passes through a guard getter to remove traces of tritium prior to exiting the system. The tritium loaded collection getter, once removed, is analyzed by liquid scintillation techniques. The entire sequence is under computer control except for the removal and analysis of the collection getter.
Bourne, Gary L. (Idaho Falls, ID); Meikrantz, David H. (Idaho Falls, ID); Ely, Walter E. (Los Alamos, NM); Tuggle, Dale G. (Los Alamos, NM); Grafwallner, Ervin G. (Arco, ID); Wickham, Keith L. (Idaho Falls, ID); Maltrud, Herman R. (Los Alamos, NM); Baker, John D. (Blackfoot, ID)
This system measures tritium on-line and collects tritium from a flowing inert gas stream. It separates the tritium from other non-hydrogen isotope contaminating gases, whether radioactive or not. The collecting portion of the system is constructed of various zirconium alloys called getters. These alloys adsorb tritium in any of its forms at one temperature and at a higher temperature release it as a gas. The system consists of four on-line getters and heaters, two ion chamber detectors, two collection getters, and two guard getters. When the incoming gas stream is valved through the on-line getters, 99.9% of it is adsorbed and the remainder continues to the guard getter where traces of tritium not collected earlier are adsorbed. The inert gas stream then exits the system to the decay chamber. Once the on-line getter has collected tritium for a predetermined time, it is valved off and the next online getter is valved on. Simultaneously, the first getter is heated and a pure helium purge is employed to carry the tritium from the getter. The tritium loaded gas stream is then routed through an ion chamber which measures the tritium activity. The ion chamber effluent passes through a collection getter that readsorbs the tritium and is removable from the system once it is loaded and is then replaced with a clean getter. Prior to removal of the collection getter, the system switches to a parallel collection getter. The effluent from the collection getter passes through a guard getter to remove traces of tritium prior to exiting the system. The tritium loaded collection getter, once removed, is analyzed by liquid scintillation techniques. The entire sequence is under computer control except for the removal and analysis of the collection getter.
Baker, J.D.; Wickham, K.L.; Ely, W.E.; Tuggle, D.G.; Meikrantz, D.H.; Grafwaller, E.G.; Maltrud, H.R.; Bourne, G.L.
Coherent X-ray Imaging Data Bank (CXIDB): An Open Repository for CXI Experimental Data
DOE Data Explorer (OSTI)
Nowadays there are several groups around the world doing excellent work using different kinds of techniques all based on the physics of coherent X-ray imaging (CXI). Due to several reasons, including lack of a standard file format, there has been limited sharing of data which severely limits possible synergies inside the community. At the same time there is a population of researchers who do not have access to the facilities required to make such kinds of experiments, or do not have the expertise and resources necessary to carry them out. But many of them would be able to test new ideas and techniques if they would have access to the experimental data. The main goal of the Coherent X-ray Imaging Data Bank is to address these problems by creating an open repository for CXI experimental data. Such a repository provides several important benefits including: Expansion of the CXI community directly leading to an increase in the science output, the existence of an archival place for all the experimental data would ensure that such data does not gets lost forever when the group that did the experiment is no longer interested in the data, the availability of the experimental data to the entire community greatly facilitates reproducibility, leading to higher quality and more transparent science, the development of a well documented file format for CXI data facilitates data sharing and might one day lead to its emergence as a de facto standard. Current free electron laser facilities such as the LCLS are capable of producing very large amounts of data (20TB a day) and the coming European FEL is expected to increase this rate a factor of 500. The analyzes of such large bodies of data will have to be distributed through a large community to make it manageable, and this repository could be an important facilitator in this process.
Corrosion-induced gas generation in a nuclear waste repository: Reactive geochemistry and multiphase flow effect
Corrosion of steel canisters, stored in a repository for spent fuel and high-level nuclear wastes, leads to the generation and accumulation of hydrogen gas in the backfilled emplacement tunnels, which may significantly affect long-term repository safety. Previous studies used H{sub 2} generation rates based on the volume of the waste or canister material and the stoichiometry of the corrosion reaction. However, iron corrosion and H{sub 2} generation rates vary with time, depending on factors such as amount of iron, water availability, water contact area, and aqueous and solid chemistry. To account for these factors and feedback mechanisms, we developed a chemistry model related to iron corrosion, coupled with two-phase (liquid and gas) flow phenomena that are driven by gas-pressure buildup associated with H{sub 2} generation and water consumption. Results indicate that by dynamically calculating H{sub 2} generation rates based on a simple model of corrosion chemistry, and by coupling this corrosion reaction with two-phase flow processes, the degree and extent of gas pressure buildup could be much smaller compared to a model that neglects the coupling between flow and reactive transport mechanisms. By considering the feedback of corrosion chemistry, the gas pressure increases initially at the canister, but later decreases and eventually returns to a stabilized pressure that is slightly higher than the background pressure. The current study focuses on corrosion under anaerobic conditions for which the coupled hydrogeochemical model was used to examine the role of selected physical parameters on the H{sub 2} gas generation and corresponding pressure buildup in a nuclear waste repository. The developed model can be applied to evaluate the effect of water and mineral chemistry of the buffer and host rock on the corrosion reaction for future site-specific studies.
Xu, T.; Senger, R.; Finsterle, S.
National Geoscience Data Repository System, Phase II. Final report, January 30, 1995--January 28, 1997
The American Geological Institute (AGI) has completed Phase II of a project to establish a National Geoscience Data Repository System (NGDRS). The project`s primary objectives are to preserve geoscience data in jeopardy of being destroyed and to make that data available to those who have a need to use it in future investigations. These data are available for donation to the public as a result of the downsizing that has occurred in the major petroleum and mining companies in the United States for the past decade. In recent years, these companies have consolidated domestic operations, sold many of their domestic properties and relinquished many of their leases. The scientific data associated with those properties are no longer considered to be useful assets and are consequently in danger of being lost forever. The national repository project will make many of these data available to the geoscience community for the first time. To address this opportunity, AGI sought support from the Department of Energy (DOE) in 1994 to initiate the NGDRS Phase I feasibility study to determine the types and quantity of data that companies would be willing to donate. The petroleum and mining companies surveyed indicated that they were willing to donate approximately five million well logs, one hundred million miles of seismic reflection data, millions of linear feet of core and cuttings, and a variety of other types of scientific data. Based on the positive results of the Phase I study, AGI undertook Phase II of the program in 1995. Funded jointly by DOE and industry, Phase II encompasses the establishment of standards for indexing and cataloging of geoscience data and determination of the costs of transferring data from the private sector to public-sector data repositories. Pilot projects evaluated the feasibility of the project for transfer of different data types and creation of a Web-based metadata supercatalog and browser.
Bentonite alteration due to thermal-hydro-chemical processes during the early thermal period in a nuclear waste repository
After closure of an underground nuclear waste repository, the decay of radionuclides will raise temperature in the repository, and the bentonite buffer will resaturate by water inflow from the surrounding host rock. The perturbations from these thermal and hydrological processes are expected to dissipate within hundreds to a few thousand years. Here, we investigate coupled thermal-hydro-chemical processes and their effects on the short-term performance of a potential nuclear waste repository located in a clay formation. Using a simplified geometric configuration and abstracted hydraulic parameters of the clayey formation, we examine geochemical processes, coupled with thermo-hydrologic phenomena, and potential changes in porosity near the waste container during the early thermal period. The developed models were used for evaluating the mineral alterations and potential changes in porosity of the buffer, which can affect the repository performance. The results indicate that mineral alteration and associated changes in porosity induced by early thermal and hydrological processes are relatively small and are expected to not significantly affect flow and transport properties. Chlorite precipitation was obtained in all simulation cases. A maximum of one percent volume fraction of chlorite could be formed, whose process may reduce swelling and sorption capacity of bentonite clay, affecting the performance of the repository. llitisation process was not obtained from the present simulations.
Identifying potential repositories for radioactive waste: multiple criteria decision analysis and critical infrastructure systems
An approach for the analysis and management of multiple criteria critical infrastructure problems is put forth. Nuclear waste management involves complex tradeoffs under uncertainty. Among all waste either generated by nature or human activities, radioactive nuclear waste is the most toxic to human health and difficult to manage: it is known that some nuclear waste material will be radioactive and potentially dangerous for hundreds of thousands of years. This paper discusses the use of multiple criteria decision analysis techniques such as the analytic hierarchy process for recommending sites to be considered as potential repositories for nuclear waste.
Kouichi Taji; Jason K. Levy; Jens Hartmann; Michelle L. Bell; Richard M. Anderson; Benjamin F. Hobbs; Tom Feglar
Groundwater chemistry along flow paths between a proposed repository site and the accessible environment
The Nevada Nuclear Waste Storage Investigations Program of the Department of Energy is investigating Yucca Mountain in the Nevada Test Site as a possible repository location. As part of this investigation, the groundwater from all pumped wells in and near the site has been sampled and analyzed; the results are reported in this document. The speciation and solubility of nuclear waste elements in these groundwaters have been calculated using the EQ3/6 computer code. Estimates have also been made of the pH and Eh buffering capacity of the water/rock system of Yucca Mountain.
Ogard, A.E.; Kerrisk, J.F.
Engineered barrier system and waste package design concepts for a potential geologic repository at Yucca Mountain
We are using an iterative process to develop preliminary concept descriptions for the Engineered Barrier System and waste-package components for the potential geologic repository at Yucca Mountain. The process allows multiple design concepts to be developed subject to major constraints, requirements, and assumptions. Involved in the highly interactive and interdependent steps of the process are technical specialists in engineering, metallic and nonmetallic materials, chemistry, geomechanics, hydrology, and geochemistry. We have developed preliminary design concepts that satisfy both technical and nontechnical (e.g., programmatic or policy) requirements.
Short, D.W.; Ruffner, D.J.; Jardine, L.J.
NREL's Field Data Repository Supports Accurate Home Energy Analysis (Fact Sheet)
This fact sheet discusses NREL's work to develop a repository of research-level residential building characteristics and historical energy use data to support ongoing efforts to improve the accuracy of residential energy analysis tools and the efficiency of energy assessment processes. The objective of this project is to create a robust empirical data source to support the research goals of the Department of Energy's Building America program, which is to improve the efficiency of existing U.S. homes by 30% to 50%. Researchers can use this data source to test the accuracy of building energy simulation software and energy audit procedures, ultimately leading to more credible and less expensive energy analysis.
Repository CRAN
Depends maps Description Provides mailmerge methods for reading spreadsheets of addresses and other relevant information to create standardized but customizable letters. Provides a method for mapping US ZIP codes, including those of letter recipients. Provides a method for parsing and processing html code from online job postings of the American Political Science Association.
Ryan T. Moore; Andrew Reeves; Maintainer Ryan T. Moore; Lazyload Yes; Ryan T. Moore; Andrew Reeves
WTS dated September 29, 2011 Final Determination, Class 2 Modification Request (TRUPACT-III, SLB2, CH Bay), WIPP Hazardous Waste Facility Permit, R Solomon, PE, NMED dated...
Sequential evaluation of the potential geologic repository site at Yucca Mountain, Nevada, USA
This paper discusses the changes that are planned for the characterization program at Yucca Mountain due to budget changes. Yucca Mountain is the only site being studied in the US for a geologic repository. Funding for the site characterization program at Yucca Mountain program was cut by roughly one half from the 1994 projected budget to complete three major milestones. These project milestones included: (1) a time-phased determination of site suitability, and if a positive finding, (2) completion of an Environmental Impact Statement, and (3) preparation of a License Application to the US NRC to authorize repository construction. In reaction, Yucca Mountain Site Characterization Project has shifted from parallel development of these milestones to a sequenced approach with the site suitability evaluation being replaced with a management assessment. Changes to the regulatory structure for the disposal program are under consideration by DOE and the NRC. The possibility for NRC and Doe to develop a site-specific regulatory structure follows from the National Energy Policy Act of 1992 that authorized the US EPA to develop a site specific environmental standard for Yucca Mountain.
Bjerstedt, T.W.
Characterizing the Evolution of the In-Drift Environment in a Proposed Yucca Mountain Repository
This presentation provides a high-level summary of the approach taken to achieve a conceptual understanding of the chemical environments likely to exist in the proposed Yucca Mountain repository after the permanent closure of the facility. That conceptual understanding was then made quantitative through laboratory and modeling studies. This summary gives an overview of the in-drift chemical environment modeling that was needed to evaluate a Yucca Mountain repository: it describes the geological, hydrological, and geochemical aspects of the chemistry of water contacting engineered barriers and includes a summary of the technical basis that supports the integration of this information into the total system performance assessment. In addition, it presents a description of some of the most important data and processes influencing the in-drift environment, and describes how data and parameter uncertainty are propagated through the modeling. Sources of data include: (1) external studies regarding climate changes; (2) site-specific studies of the structure of the mountain and the properties of its rock layers; (3) properties of dust in the mountain and investigations of the potential for deliquescence on that dust to create solutions above the boiling point of water; (4) obtaining thermal data from a comprehensive thermal test addressing coupled processes; and (5) modeling the evolution of the in-drift environment at several scales. Model validation is also briefly addressed.
Dr. Abraham Van Luik
Selection of candidate canister materials for high-level nuclear waste containment in a tuff repository
A repository located at Yucca Mountain at the Nevada Test Site is a potential site for permanent geological disposal of high-level nuclear waste. The repository can be located in a horizon in welded tuff, a volcanic rock, which is above the static water level at this site. The environmental conditions in this unsaturated zone are expected to be air and water vapor dominated for much of the containment period. Type 304L stainless steel is the reference material for fabricating canisters to contain the solid high-level wastes. Alternative stainless alloys are considered because of possible susceptibility of 304L to localized and stress forms of corrosion. For the reprocessed glass wastes, the canisters serve as the recipient for pouring the glass with the result that a sensitized microstructure may develop because of the times at elevated temperatures. Corrosion testing of the reference and alternative materials has begun in tuff-conditioned water and steam environments. 21 references, 8 figures, 8 tables.
McCright, R.D.; Weiss, H.; Juhas, M.C.; Logan, R.W.
Two phase partially miscible flow and transport modeling in porous media: application to gas migration in a nuclear waste repository
We derive a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological repository for radioactive waste. This model includes capillary effects and the gas high diffusivity. Moreover, it is written in variables (total hydrogen mass density and liquid pressure) chosen in order to be consistent with gas appearance or disappearance. We discuss the well possedness of this model and give some computational evidences of its adequacy to simulate gas generation in a water saturated repository.
Alain Bourgeat; Mladen Jurak; Farid Sma�
National Geoscience Data Repository System: Phase 2 -- Planning and pilot study. Progress report, 1. quarter, January--March 1997
The NGDRS goal is to preserve and make geoscience and engineering data readily accessible to those who have an interest in using such data. To achieve this goal requires the careful management of the process for transferring data from data providers to the public domain and the creation of the information systems organization and infrastructure to allow data consumers to find and access the data. This report describes the NGDRS organization structure; the development of a directory of existing geoscience data repositories; the financial models for data transfer (seismic data transfer, core data transfer, and data browser); and the overall architecture of the repository system.
Garbage collection in generic libraries
This paper demonstrates a unified and garbage-collector independent way to describe the information required for precise collection. Thereby it is possible to construct, a library that can be used with various garbage collectors, without modifying the ...
Gor V. Nishanov; Sibylle Schupp
Earth Day Electronics Recycling Collection
Earth Day Electronics Recycling Collection The U.S. Department of Energy, Washington, DC in collaboration with UNICOR Federal Prison Industries C E L E B R A T E E A R T H D A Y A...
Workshop on the source term for radionuclide migration from high-level waste or spent nuclear fuel under realistic repository conditions: proceedings
Sixteen papers were presented at the workshop. The fourteen full-length papers included in the proceedings were processed separately. Only abstracts were included for the following two papers: Data Requirements Based on Performance Assessment Analyses of Conceptual Waste Packages in Salt Repositories, and The Potential Effects of Radiation on the Source Term in a Salt Repository. (LM)
Hunter, T.O.; Muller, A.B. (eds.)
CONTACTS FOR INFORMATION MANAGEMENT: Forms, Information Collection...
CONTACTS FOR INFORMATION MANAGEMENT: Forms, Information Collection (PRA), & Records CONTACTS FOR INFORMATION MANAGEMENT: Forms, Information Collection (PRA), & Records Name Contact...
Preclosure seismic design methodology for a geologic repository at Yucca Mountain. Topical report YMP/TR-003-NP
This topical report describes the methodology and criteria that the U.S. Department of Energy (DOE) proposes to use for preclosure seismic design of structures, systems, and components (SSCs) of the proposed geologic repository operations area that are important to safety. Title 10 of the Code of Federal Regulations, Part 60 (10 CFR 60), Disposal of High-Level Radioactive Wastes in Geologic Repositories, states that for a license to be issued for operation of a high-level waste repository, the U.S. Nuclear Regulatory Commission (NRC) must find that the facility will not constitute an unreasonable risk to the health and safety of the public. Section 60.131 (b)(1) requires that SSCs important to safety be designed so that natural phenomena and environmental conditions anticipated at the geologic repository operations area will not interfere with necessary safety functions. Among the natural phenomena specifically identified in the regulation as requiring safety consideration are the hazards of ground shaking and fault displacement due to earthquakes.
Searching oURspace 2010,March 18 Like our University Archives and Special Collections, the oURspace repository preserves the
record to view the full-text document. Enter simple search terms here and click SEARCH. Click URL. Click on that link to view the document. SEARCH oURspace: Enter a keyword(s) in the "Search o searches consisting of one or a couple of terms, use the initial search box on the oURspace home page
Argerami, Martin
Environmental Stress Pathway Project (ESSP) Data in EIDR, the Experimental Information and Data Repository
ESPP is developing computational models that describe and predict the behavior of gene regulatory networks in microbes in response to the environmental conditions found in DOE waste sites. The research takes place within the Virtual Institue for Microbial Stress and Survival (VIMSS). ESPP data files are stored on one of the VIMSS file servers. They include data generated by project participants, as well as links to data stored either in BioFiles or in the Experimental Data Repository. A searchable information database, EIDR, provides links to the data files and information about the data, including design information about biomass production experiments, information about the lab analyses that generated the data, and links to more detailed information, displays, or analyses. EIDR contains more than 3000 data uploads. (Specialized Interface)
Arkin, Adam (LBNL); Hazen, Terry (LBNL)
Packaging Strategies for Criticality Safety for "Other" DOE Fuels in a Repository
Since 1998, there has been an ongoing effort to gain acceptance of U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in the national repository. To accomplish this goal, the fuel matrix was used as a discriminating feature to segregate fuels into nine distinct groups. From each of those groups, a characteristic fuel was selected and analyzed for criticality safety based on a proposed packaging strategy. This report identifies and quantifies the important criticality parameters for the canisterized fuels within each criticality group to: (1) demonstrate how the �other� fuels in the group are bounded by the baseline calculations or (2) allow identification of individual type fuels that might require special analysis and packaging.
Larry L Taylor
Design and Implementation of an International Training Program on Repository Development and Management
Korea Hydro and Nuclear Power Co., Ltd. (KHNP) is an electric company in the Republic of Korea with twenty operational nuclear power plants and eight additional units that are either planned or currently under construction. Regulations require that KHNP manage the radioactive waste generated by their nuclear power plants. In the course of planning low, intermediate, and high level waste storage facilities, KHNP sought interaction with an acknowledged expert in the field of radioactive waste management and, consequently, contacted Sandia National Laboratories (SNL). KHNP has contracted with SNL to provide a year long training program on repository science. This paper discusses the design of the curriculum, specific plans for execution of the training program, and recommendations for smooth implementation of international training programs. (authors)
Vugrin, K.W. [Sandia National Laboratories Carlsbad Programs Group, Performance Assessment and Decision Analysis Department, Carlsbad, NM (United States); Twitchell, Ch.A. [Sandia National Laboratories, Carlsbad Programs Group, Center Business Operations Department, Carlsbad, NM (United States)
Seismic design and analysis considerations for high level nuclear waste repositories
A high level nuclear waste repository, like the one at Nevada`s Yucca Mountain that is being investigated for site suitability, will have some unique seismic design and analysis considerations. These are discussed, and a design philosophy that can rationally account for the unique performance objectives of such facilities is presented. A case is made for the use of DOE`s performance goal-based seismic design and evaluation methodology that is based on a hybrid ``deterministic`` and ``probabilistic`` concept. How and to what extent this methodology should be modified to adopt it for a potential site like Yucca Mountain is also outlined. Finally, the issue of designing for seismic fault rupture is discussed briefly, and the desirability of using the proposed seismic design philosophy in fault rupture evaluation is described.
Building Component Library: An Online Repository to Facilitate Building Energy Model Creation: Preprint
Component Library: Component Library: An Online Repository to Facilitate Building Energy Model Creation Preprint Katherine Fleming, Nicholas Long, and Alex Swindler To be presented at the ACEEE Summer Study on Energy Efficiency in Buildings Pacific Grove, California August 12-17, 2012 Conference Paper NREL/CP-5500-54710 May 2012 NOTICE The submitted manuscript has been offered by an employee of the Alliance for Sustainable Energy, LLC (Alliance), a contractor of the US Government under Contract No. DE-AC36-08GO28308. Accordingly, the US Government and Alliance retain a nonexclusive royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for US Government purposes. This report was prepared as an account of work sponsored by an agency of the United States government.
NSNFP Activities in Support of Repository Licensing for Disposal of DOE SNF
The U.S. Department of Energy (DOE) Office of Civilian Radioactive Waste Management is in the process of preparing the Yucca Mountain license application for submission to the Nuclear Regulatory Commission as the nation�s first geologic repository for spent nuclear fuel (SNF) and high-level waste. Because the DOE SNF will be part of the license application, there are various components of the license application that will require information relative to the DOE SNF. The National Spent Nuclear Fuel Program (NSNFP) is the organization that directs the research, development, and testing of treatment, shipment, and disposal technologies for all DOE SNF. This report documents the work activities conducted by the NSNFP and discusses the relationship between these NSNFP technical activities and the license application. A number of the NSNFP activities were performed to provide risk insights and understanding of DOE SNF disposal as well as to prepare for anticipated questions from the regulatory agency.
Henry H. Loo; Brett W.. Carlsen; Sheryl L. Morton; Larry L. Taylor; Gregg W. Wachs
Effects of microbial processes on gas generation under expected WIPP repository conditions: Annual report through 1992
Microbial processes involved in gas generation from degradation of the organic constituents of transuranic waste under conditions expected at the Waste Isolation Pilot Plant (WIPP) repository are being investigated at Brookhaven National Laboratory. These laboratory studies are part of the Sandia National Laboratories -- WIPP Gas Generation Program. Gas generation due to microbial degradation of representative cellulosic waste was investigated in short-term ( 6 months) experiments by incubating representative paper (filter paper, paper towels, and tissue) in WIPP brine under initially aerobic (air) and anaerobic (nitrogen) conditions. Samples from the WIPP surficial environment and underground workings harbor gas-producing halophilic microorganisms, the activities of which were studied in short-term experiments. The microorganisms metabolized a variety of organic compounds including cellulose under aerobic, anaerobic, and denitrifying conditions. In long-term experiments, the effects of added nutrients (trace amounts of ammonium nitrate, phosphate, and yeast extract), no nutrients, and nutrients plus excess nitrate on gas production from cellulose degradation.
Francis, A.J.; Gillow, J.B.
Saltstone is a cementitious waste form made by mixing salt solution originating from liquid waste storage tanks at the DOE Savannah River Site with a dry mix containing blast furnace slag, fly ash, and cement or lime. The wet mix is poured into a concrete repository for on-site disposal. Solidified Saltstone is a dense, alkaline, reducing, micro-porous, monolithic, cementitious matrix, containing a solution of salts within its pore structure. Sodium sulfate concentrations in the pore fluid are around 0.15 mol/L, and external sulfate attack on concrete barriers is expected to occur over time. To predict the long-term performance of concrete repositories, the STADIUM{reg_sign} code was used to simulate the reactive transport processes leading to formation of ettringite, an expansive mineral phase often associated with spalling or cracking. STADIUM{reg_sign} is a multi-ionic transport model based on a split operator approach that separates ionic movement and chemical reactions. Ionic transport is described by the extended Nernst-Planck equation for unsaturated media, and accounts for electrical coupling between ionic species, chemical activity, transport due to water content gradient, and temperature effects. STADIUM{reg_sign} does not predict whether physical damage will occur, or the impact on transport properties should fracturing occur. Thus the presence of ettringite was assumed to coincide with physical damage for the purpose of estimating effective transport properties. Effective properties for concrete barriers were estimated assuming complete hydraulic failure behind the ettringite front and unaltered properties ahead of the front. The ettringite front advances at a rate dependent on the diffusion coefficient assumed for the failed zone. A sensitivity study indicates a service life ranging from thousands to tens of thousands of years, depending on the barrier thickness and sulfate exposure conditions among other factors.
Flach, G.
Raqs Media Collective Flash Force
extended only to a couple of inches. With the invention of light bulbs, scientists started detonatingRaqs Media Collective Flash Force: A Visual History of Might, Right and Light Perhaps the greatest of light and divorcing these from the potent explosions that initially produced them. It is a history
Canales, Jimena
Musical fingerprints: collaboration around home media collections
As people collect more and more digital music, photos, and video, the growing scale of the collection challenges how families share and collaborate around home media collections. We studied the intersection between physical and digital media collections. ... Keywords: media collection, media management, music sharing
Robin Sease; David W. McDonald
THE WORLD'S Biggest Fan Collection
WORLD'S Biggest Fan Collection WORLD'S Biggest Fan Collection If you only know the Big Ass Fan Company as the preeminent designer and manufacturer of high volume, low speed fans for factories and cows, it's time you get to know us better. While we continue to lead the way in industrial and agricultural air movement, we've also refined these designs to bring the same innovation and benefits of our famous fans to circulate an ocean of air in sound-sensitive commercial spaces and homes. And when our customers said they wanted something for smaller spaces, we listened - and we think you'll like the results. We've got you covered - ceiling to floor, wall to door! Features New patented airfoil system uses 10 Powerfoil airfoils, winglets and patent-pending AirFence(tm) technology to increase
On the collective curvature radiation
The paper deals with the one possible mechanism of the pulsar radio emission, i.e., with the collective curvature radiation of the relativistic particle stream moving along the curved magnetospheric magnetic field lines. It is shown that the electromagnetic wave containing one cylindrical harmonic exp{is{\\phi}} can not be radiated by the curvature radiation mechanism, that corresponds to radiation of a charged particle moving along curved magnetic field lines. The point is that the particle in vacuum radiates the triplex of harmonics (s, s \\pm 1), so for the collective curvature radiation the wave polarization is very important and cannot be fixed a priori. For this reason the polarization of real unstable waves must be determined directly from the solution of wave equations for the media. Its electromagnetic properties should be described by the dielectric permittivity tensor \\^{\\epsilon}({\\omega},k,r), that contains the information on the reaction on all possible types of radiation.
Istomin, Ya N; Beskin, V S
Department of Energy Proposed Agency Information Collection:...
of Energy Proposed Agency Information Collection: Federal Register Notice Volume 75, No. 100 - May 25, 2010 Department of Energy Proposed Agency Information Collection. The...
of Energy Proposed Agency Information Collection: Federal Register Notice Volume 75, No. 140 - Jul. 22, 2010 Department of Energy proposed Agency Information Collection:...
Information Collection Management | Department of Energy
Information Collection Management Information Collection Management The Paperwork Reduction Act (PRA) of 1995 requires each Federal agency to seek and obtain approval from the...
Proposed Agency Information Collection: Federal Register Notice...
Proposed Agency Information Collection: Federal Register Notice Volume 76, No. 154 - Aug. 10, 2011 Proposed Agency Information Collection: Federal Register Notice Volume 76, No....
Precipitation-Front Modeling: Issues Relating to Nucleation and Metastable Precipitation in the Planned Nuclear Waste Repository at Yucca Mountain, Nevada
Mineralogic Model of Yucca Mountain, Nevada, Rev. 1. Reportfor fracture sealing at Yucca Mountain, Nevada. Journal ofWaste Repository at Yucca Mountain, Nevada J.A. Apps and
Apps, J.A.; Sonnenthal, E.L.
Characterization, propagation and analysis of aleatory and epistemic uncertainty in the 2008 performance assessment for the proposed repository for high-level radioactive waste at Yucca Mountain, Nevada
The 2008 performance assessment (PA) for the proposed repository for high-level radioactive waste at Yucca Mountain (YM), Nevada, illustrates the conceptual structure of risk assessments for complex systems. The 2008 YM PA is based on the following three ...
Clifford W. Hansen; Jon C. Helton; C�dric J. Sallaberry
Confidentiality and the Desire for Open Communication in the Transport of Radioactive Material to a National Repository
Confidentiality, Security and Confidentiality, Security and Confidentiality, Security and Confidentiality, Security and the Desire for Open the Desire for Open Communication in the Communication in the Transport of Radioactive Transport of Radioactive Material to a National Material to a National Repository Repository A presentation to the A presentation to the DOE Transportation External Coordination (TEC) DOE Transportation External Coordination (TEC) Working Group Meeting Working Group Meeting Albuquerque, NM Albuquerque, NM 21 21 - - 23 April 2004 23 April 2004 Ronald B. Pope Consultant April 2004 April 2004 Confidentiality Confidentiality - - TEC Working TEC Working Group Group - - Albuquerque Albuquerque 2 2 Objectives Objectives Address and prompt TEC discussion on issues Address and prompt TEC discussion on issues
This paper evaluates hydrogen-induced cracking (HIC) susceptibility of titanium alloys in environments anticipated in the Yucca Mountain nuclear waste repository with particular emphasis on the. effect of the oxide passive film on the hydrogen absorption process of titanium alloys being evaluated. The titanium alloys considered in this review include Ti 2, 5 , 7, 9, 11, 12, 16, 17, 18, 24 and 29. In general, the concentration of hydrogen in a titanium alloy can increase due to absorption of atomic hydrogen produced from passive general corrosion of that alloy or galvanic coupling of it to a less noble metal. It is concluded that under the exposure conditions anticipated in the Yucca Mountain repository, the HIC of titanium drip shield will not occur because there will not be sufficient hydrogen in the metal even after 10,000 years of emplacement. Due to the conservatisms adopted in the current evaluation, this assessment is considered very conservative.
G. De; K. Mon; G. Gordon; D. Shoesmith; F. Hua
Geology and hydrogeology of the proposed nuclear waste repository at Yucca Mountain, Nevada and the surrounding area
In late 1987 Congress issued an amendment to the Nuclear Waste Policy Act of 1982 which directed the characterization of Yucca Mountain, Nevada as the only remaining potential site for the Nation`s first underground high-level radioactive waste repository. The evaluation of a potential underground repository is guided and regulated by policy established by the Department of Energy (DOE), Nuclear Regulatory Commission (NRC), Environmental Protection Agency (EPA), Department of Transportation (DOT), and the US Congress. The Yucca Mountain Project is the responsibility of the DOE. The purpose of this field trip is to introduce the present state of geologic and hydrologic knowledge concerning this site. This report describes the field trip. 108 refs., 6 figs., 1 tab.
Mattson, S.R.; Broxton, D.E.; Crowe, B.M.; Buono, A.; Orkild, P.P.
Numerical modeling of gas migration at a proposed repository for low and intermediate level nuclear wastes at Oberbauenstock, Switzerland
Hydrologic impacts of corrosive gas release from a hypothetical L/ILW nuclear waste repository at Oberbauenstock are explored by means of numerical simulation. A schematic two dimensional vertical section through the mountain is modeled with the simulator TOUGH, which describes two-phase flow of water and gas in porous and fractured media. Two reference cases are considered which represent the formations as a porous and as a fractured-porous (dual permeability) medium, respectively. Both cases predict similar and rather modest pressure increases, from ambient 10 bars to near 25 bars at the repository level. These results are to be considered preliminary because important parameters affecting two-phase flow, such as relative permeabilities of a fractured medium, are not well known at present. 24 refs., 15 figs., 5 tabs.
Pruess, K.
Program on Technology Innovation: Effects of Seismicity and Rockfall on Long-Term Performance of the Yucca Mountain Repository
As part of the effort to obtain regulatory approval for construction, it is necessary to estimate the effects due to seismic activity and rockfall on long-term performance of the candidate high level radioactive waste and spent nuclear fuel repository at Yucca Mountain, Nevada. Previously, EPRI analyzed the consequences of a single seismic event (EPRI report 1011812, September 2005). The present report is the latest of a series of independent EPRI assessments of Yucca Mountain project-related activities....
Evaluation of the Candidate High-Level Radioactive Waste Repository at Yucca Mountain Using Total System Performance Assessment: Phase 5
A successful license application for the candidate spent-fuel and high level waste (HLW) repository at Yucca Mountain depends on a robust demonstration of long-term safety. This report presents EPRI's independent review to identify any conservatisms in the U.S. Depawrtment of Energy's (DOE's) Phase 5 Yucca Mountain Total System Performance Assessment (TSPA). The review specifically identifies key facility components, makes recommendations regarding technical development work priorities, and evaluates ove...
Verifying the CICS File Control API with Z/Eves: An experiment in the verified software repository
Parts of the CICS transaction processing system were modelled formally in the 1980s in a collaborative project between IBM UK Hursley Park and Oxford University Computing Laboratory. Z was used to capture a precise description of the behaviour of various ... Keywords: File API, Grand challenge in verified software, IBM CICS, Mechanical proof, Theorem proving, Verification challenge problems, Verified software repository, Z notation, Z/Eves
Leo Freitas; Jim Woodcock; Yichi Zhang
Review of scenario selection approaches for performance assessment of high-level waste repositories and related issues.
The selection of scenarios representing plausible realizations of the future conditions-with associated probabilities of occurrence-that can affect the long-term performance of a high-level radioactive waste (HLW) repository is the commonly used method for treating the uncertainty in the prediction of the future states of the system. This method, conventionally referred to as the ``scenario approach,`` while common is not the only method to deal with this uncertainty; other method ``ch as the environmental simulation approach (ESA), have also been proposed. Two of the difficulties with the scenario approach are the lack of uniqueness in the definition of the term ``scenario`` and the lack of uniqueness in the approach to formulate scenarios, which relies considerably on subjective judgments. Consequently, it is difficult to assure that a complete and unique set of scenarios can be defined for use in a performance assessment. Because scenarios are key to the determination of the long-term performance of the repository system, this lack of uniqueness can present a considerable challenge when attempting to reconcile the set of scenarios, and their level of detail, obtained using different approaches, particularly among proponents and regulators of a HLW repository.
Banano, E.J. [Beta Corporation International, Albuquerque, NM (United States); Baca, R.G. [Southwest Research Inst., San Antonio, TX (United States). Center for Nuclear Waste Regulatory Analyses
State-of-the-art for evaluating the potential impact of tectonism and volcanism on a radioactive waste repository
Most estimates of the time required for safe isolation of radioactive wastes from the biosphere range from 100,000 to 1,000,000 years. For such long time spans, it is necessary to assess the potential effects of geologic processes such as volcanism and tectonic activity on the integrity of geologic repositories. Predictions of geologic phenomena can be based on probabilistic models, which assume a random distribution of events. The necessary historic and geologic records are rarely available to provide an adequate data base for such predictions. The observed distribution of volcanic and tectonic activity is not random, and appears to be controlled by extremely complex deterministic processes. The advent of global plate tectonic theory in the past two decades has been a giant step toward understanding these processes. At each potential repository site, volcanic and tectonic processes should be evaluated to provide the most thorough possible understanding of those deterministic processes. Based on this knowledge, judgements will have to be made as to whether or not the volcanic and tectonic processes pose unacceptable risk to the integrity of the repository. This report describes the potential hazards associated with volcanism and tectonism, and the means for evaluating these processes.
Data Packages in Hanford Site's Administrative Record (AR) and Public Information Repository (PIR)
In 1989, the Department of Energy joined with the Washington State Department of Ecology and the U.S. Environmental Protection Agency in signing the Hanford Federal Facility Agreement and Consent Order more commonly known as the Tri-Party Agreement (TPA). The TPA outlines legally enforceable milestones for Hanford cleanup over the next several decades. The AR is the body of documents and information that is considered or relied upon to arrive at a final decision for remedial action or hazardous waste management. An AR is established for each operable unit (OU); treatment, storage, or disposal unit (TSD); or Expedited Response Action (ERA) group and will contain all documents having information considered in arriving at a Record of Decision or permit. Documents become part of the AR after they have been designated as an AR by the TPA or after EPA, DOE, or other official parties have identified a document or set of documents for inclusion. Furthermore, AR documents are to be kept in a Public Information Repository (PIR).Thousands of data packages that support the AR documents are available to the public in the Hanford PIR.
Verification and benchmarking of PORFLO: an equivalent porous continuum code for repository scale analysis
The objective of this work was to perform an assessment of prediction capabilities and features of the PORFLO code in relation to its intended use in the Basalt Waste Isolation Project. This objective was to be accomplished through a code verification and benchmarking task. Results were to be documented which either support correctness of prediction capabilities or identify areas of intended application in which the code exhibits weaknesses. A test problem set consisting of 10 problems was developed. Results of PORFLO simulations of these problems were provided for use in this work. The 10 problems were designed to test the three basic computational capabilities or categories of the code. Broken down by physical process, these are heat transfer, fluid flow, and radionuclide transport. Two verification problems were included within each of these categories. They were problems designed to test basic features of PORFLO for which analytical solutions are available for use as a known comparison basis. Hence they are referred to as verification problems. Of the remaining four problems, one repository scale problem representative of intended PORFLO use within BWIP was included in each of the three basic capabilities categories. The remaining problem was a case specifically designed to test features of decay and retardation in radionuclide transport. These four problems are referred to as benchmarking problems, because results computed with an additional computer code were used as a basis for comparison. 38 figures.
Eyler, L.L.; Budden, M.J.
Development of models for use in the assessment of waste repository performance
Any repository suitable for the disposal of radioactive waste comprises a combination of various man-made and natural barriers which aim to prevent transfer of the radionuclides from the canister to the external environment. Our group has developed the techniques needed to model the equilibrium chemistry of complex multicomponent rock/water systems over a range of ionic strengths and temperatures. These models, show remarkable agreement with field measurements when applied to natural systems. They have been applied successfully to interpret a variety of geochemical processes: studies of ancient and modern marine evaporite systems, studies of the solar evaporation of seawater studies of mineral formation in lakes and in fluid inclusions. At present our models are limited to the components of the seawater system (Na{sup +}, Mg{sup 2+}, Ca{sup 2+}, H{sup +}, SO{sub 4}{sup 2{minus}}, HCO{sub 3}{sup {minus}}, CO{sub 3}{sup 2{minus}}, CO{sub 2}), together with the borate species and SiO{sub 2}. 2 tabs.
Dickson, A.G. (Scripps Institution of Oceanography, San Diego, CA (USA). Marine Physical Lab.); Weare, J.H. (California Univ., San Diego, La Jolla, CA (USA). Dept. of Chemistry)
Total System Performance Assessment, 1993: An evaluation of the potential Yucca Mountain repository
Total System Performance Assessments are an important component in the evaluation of the suitability of Yucca Mountain, Nevada as a potential site for a mined geologic repository for the permanent disposal of high-level radioactive wastes in the United States. The Total System Performance Assessments are conducted iteratively during site characterization to identify issues which should be addressed by the characterization and design activities as well as providing input to regulatory/licensing and programmatic decisions. During fiscal years 1991 and 1992, the first iteration of Total System Performance Assessment (hereafter referred to as TSPA 1991) was completed by Sandia National Laboratories and Pacific Northwest Laboratory. Beginning in fiscal year 1993, the Civilian Radioactive Waste Management System Management and Operating Contractor was assigned the responsibility to plan, coordinate, and contribute to the second iteration of Total System Performance Assessment (hereafter referred to as TSPA 1993). This document presents the objectives, approach, assumptions, input, results, conclusions, and recommendations associated with the Management and Operating Contractor contribution to TSPA 1993. The new information incorporated in TSPA 1993 includes (1) revised estimates of radionuclide solubilities (and their thermal and geochemical dependency), (2) thermal and geochemical dependency of spent fuel waste alteration and glass dissolution rates, (3) new distribution coefficient (k{sub d}) estimates, (4) revised estimates of gas-phase velocities and travel times, and (5) revised hydrologic modeling of the saturated zone which provides updated estimates of the advective flux through the saturated zone.
Andrews, R.W.; Dale, T.F.; McNeish, J.A.
Nucleic Acid Database: a Repository of Three-Dimensional Information about Nucleic Acids
The Nucleic Acid Database (NDB) provides 3-D structural information about nucleic acids.� It is a relational database designed to facilitate the easy search for nucleic acid structures using any of the stored primary or derived structural features. Reports can then be created describing any properties of the selected structures and structures may be viewed in several different formats, including the mmCIF format, the NDB Atlas format, the NDB coordinate format, or the PDB coordinate format. Browsing the images of the structures can also be done through the galleries of the X-ray Atlas or the NMR Atlas, available on this website. The images are created directly from coordinates in the NDB repository.� More than 3500 structures can be searched, viewed, and included in preformatted reports.This website also includes a number of specialized tools and interfaces. The NDB maintains the mmCIF Web site (macromolecular Crystallographic Information File), the IUCr-approved data representation for macromolecular structures. (Specialized Interface)
Berman, H.M.; Olson, W.K.; Beveridge, D.L.; Westbrook, J.; Gelbin, A.; Demeny, T.; Hsieh, S.H.; Srinivasan, A.R.; Schneider, B.
Microbial processes involved in gas generation from degradation of the organic constituents of transuranic waste under conditions expected at the Waste Isolation Pilot Plant (WIPP) repository are being investigated at Brookhaven National Laboratory. These laboratory studies are part of the Sandia National Laboratories -- WIPP Gas Generation Program. Gas generation due to microbial degradation of representative cellulosic waste was investigated in short-term (< 6 months) and long-term (> 6 months) experiments by incubating representative paper (filter paper, paper towels, and tissue) in WIPP brine under initially aerobic (air) and anaerobic (nitrogen) conditions. Samples from the WIPP surficial environment and underground workings harbor gas-producing halophilic microorganisms, the activities of which were studied in short-term experiments. The microorganisms metabolized a variety of organic compounds including cellulose under aerobic, anaerobic, and denitrifying conditions. In long-term experiments, the effects of added nutrients (trace amounts of ammonium nitrate, phosphate, and yeast extract), no nutrients, and nutrients plus excess nitrate on gas production from cellulose degradation.
Geotechnical support and topical studies for nuclear waste geologic repositories: Annual report, fiscal year 1987
This multidisciplinary project was initiated in fiscal year 1986. It comprises 11 reports in two major interrelated tasks: The technical assistance part of the project includes reviewing the progress of the major projects in the DOE Office of Civilian Radioactive waste Management (OCRWM) Program and advising the Engineering and Geotechnology Division on significant technical issues facing each project; analyzing geotechnical data, reports, tests, surveys and plans for the different projects; reviewing and commenting on major technical reports and other program documents such as Site Characterization Plans (SCP) and Study Plans; and providing scientific and technical input at technical meetings. The topical studies activity comprises studies on scientific and technical ions and issues of significance to in-situ testing, test analysis methods, and site characterization of nuclear waste geologic repositories. The subjects of study were selected based on discussions with DOE staff. One minor topic is a preliminary consideration and planning exercise for postclosure monitoring studies. The major task, with subtasks involving various geoscience disciplines, is a study of the mechanical, hydraulic, geophysical and geochemical properties of fractures in geologic rock masses.
Energy Science and Technology Software Center (OSTI)
002339WKSTN00 The Process Manager Collective Library� http://sourceforge.net/projects/pmgrcollective/�
TNA Data Collection Tool | Department of Energy
TNA Data Collection Tool TNA Data Collection Tool TNA Data Collection Tool The Training Needs Assessment (TNA) Data Collection Tool Instructions provides detailed guidance on how to complete the TNA Data Collection Tool. It is a good idea to print this document prior to completing the TNA Data Collection Tool. The TNA Data Collection Tool is an Excel spreadsheet that the organization's designating training POC will use to populate their organizations training needs. The training POC will enter mission critical training needs as well as competencies needed to meet their organization's mission. FY14 TNA Data Collection Tool Instructions FY14 TNA Data Collection Tool.xlsx Description FY14 TNA Data Collection Tool More Documents & Publications Reference Buildings by Building Type: Small office
A vitrification technology utilizing a lanthanide borosilicate (LaBS) glass appears to be a viable option for dispositioning excess weapons-useable plutonium that is not suitable for processing into mixed oxide (MOX) fuel. A significant effort to develop a glass formulation and vitrification process to immobilize plutonium was completed in the mid-1990s to support the Plutonium Immobilization Program (PIP). Further refinement of the vitrification process was accomplished as part of the Am/Cm solution vitrification project. The LaBS glass formulation was found to be capable of immobilizing in excess of 10 wt% Pu and to be very tolerant of the impurities accompanying the plutonium material streams. Thus, this waste form would be suitable for dispositioning plutonium owned by the Department of Energy-Office of Environmental Management (DOE-EM) that may not be well characterized and may contain high levels of impurities. The can-in-canister technology demonstrated in the PIP could be utilized to dispose of the vitrified plutonium in the federal radioactive waste repository. The can-in-canister technology involves placing small cans of the immobilized Pu form into a high level waste (HLW) glass canister fitted with a rack to hold the cans and then filling the canister with HLW glass. Testing was completed to demonstrate that this technology could be successfully employed with little or no impact to current Defense Waste Processing Facility (DWPF) operation and that the resulting canisters were essentially equivalent to the present HLW glass canisters to be dispositioned in the federal repository. The performance of wastes in the repository and, moreover, the performance of the entire repository system is being evaluated by the Department of Energy-Office of Civilian Radioactive Waste Management (DOE-RW) using a Total System Performance Assessment (TSPA) methodology. Technical bases documents (e.g., Analysis/Modeling Reports (AMR)) that address specific issues regarding waste form performance are being used to develop process models as input to the TSPA analyses. In this report, models developed in five AMRs for waste forms currently slated for disposition in the repository are evaluated for their applicability to waste forms with plutonium immobilized in LaBS glass using the can-in-canister technology. Those AMRs address: high-level waste glass degradation; radionuclide inventory; in-package chemistry; dissolved concentration limits of radioactive elements; and colloid-associated radionuclide concentrations. Based on evaluation of how the models treated HLW glass and similarities in the corrosion behaviors of borosilicate HLW glasses and LaBS glass, the models in the AMRs were deemed to be directly applicable to the disposition of excess weapons-useable plutonium. The evaluations are summarized.
Marra, J
CBNTiJALKESEARCHLIBRAKY DOCUMENT COLLECTION
" 9 " 9 0 0 3 ' 9 ,^ r.V- ou 15 -^ CBNTiJALKESEARCHLIBRAKY DOCUMENT COLLECTION n P - - 5 9 0 0 3 1 9 DE05 900319 The Abundances of the Elements Hans E. Suess U.S. geological Surveys \, aeoiogififl and Harold C. Urey Department of Chemistry and Institute for Nuclear Studies University of Chicago ^ Chicagos Illinois ' i v j \ ^ \1>^ I 9 S S MASTDI *OSICE plStltJEFUKT I S ILLEGIBLE TO A A DES!?rB f l i f SpCSUTOE? SATISFACTORY REPRODUCTIOH DtSlUffiVnOR OF TMS KKUMERT fS BmiMfTED DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or
Data Collection Class-8.pub
Long Haul Long Haul Operations and Fuel Economy Analysis Research Brief Oak Ridge National Laboratory managed by UT-Battelle, LLC for the U.S. Department of Energy under Contract number DE-AC05-00OR22725 Research Areas Freight Flows Passenger Flows Supply Chain Efficiency Transportation: Energy Environment Safety Security Vehicle Technologies A s part of a long-term study sponsored by the U.S. Department of Energy (DOE) Of- fice of Vehicle Technologies (OVT), the Oak Ridge National Laboratory (ORNL) in conjunction with a number of industry partners (Michelin Americas Research Company - Michelin), have collected data and information related to Class -8 heavy truck long-haul operations in real-world highway environments. Six Class-8 tractors and ten
Panels for collecting solar energy
A solar energy collecting panel is described for heating by solar radiation a liquid circulating in a section of piping and constituted by a flat rectangular box thermally closed by a cover transparent to solar radiation and containing the said section of piping. The said box is constituted by a stamped metal sheet whose surface is less than 1 M squared and also contains a stamped copper tray in intimate contact with the piping section, the said tray supporting by itself the transparent cover and being thermally spaced from the box, the insulating pad being constituted by a in situ moulded block of rigid foam. Such a panel is intended to be used for feeding a central heating system and/or a hot water distribution system, especially for household purposes or swimming pools.
Neny, M.
Devices for collecting chemical compounds
A device for sampling chemical compounds from fixed surfaces and related methods are disclosed. The device may include a vacuum source, a chamber and a sorbent material. The device may utilize vacuum extraction to volatilize the chemical compounds from a fixed surface so that they may be sorbed by the sorbent material. The sorbent material may then be analyzed using conventional thermal desorption/gas chromatography/mass spectrometry (TD/GC/MS) instrumentation to determine presence of the chemical compounds. The methods may include detecting release and presence of one or more chemical compounds and determining the efficacy of decontamination. The device may be useful in collection and analysis of a variety of chemical compounds, such as residual chemical warfare agents, chemical attribution signatures and toxic industrial chemicals.
Scott, Jill R; Groenewold, Gary S
Particle collection enhancement by acoustics
The overall objective of this project is to demonstrate pulse combustion induced acoustic enhancement of coal ash agglomeration and sulfur capture efficiency at conditions typical of proposed direct coal-fired turbines. The MTCI proprietary approach results in agglomerates that allow the use of conventional cyclones to achieve very high particulate collection efficiency and eliminates the need for barrier filters which pose concerns regarding durability and economics. The goal of the program is to support the mission of the Department of Energy (DOE) for developing coal-fired combustion gas turbines. The MTCI concept can be packaged either as a hot flue gas clean-up subsystem for the existing combustor island configurations or as an alterative primary pulse combustor island with integrated sulfur capture, particulate agglomeration and capture, alkali gettering and NO{sub x} emissions control.
Mansour, M.N.; Chandran, R.R.; Duqum, J.N. [Manufacturing and Technology Conversion International, Inc., Columbia, MD (United States); Scaroni, A.W.; Koopman, G.H. [Pennsylvania State Univ., University Park, PA (United States); Loth, J.L. [West Virginia Univ., Morgantown, WV (United States)
Long-Term Environmental Monitoring of an Operating Deep Geologic Nuclear Waste Repository
In the present energy dilemma in which we find ourselves, the magnitude of humanity's energy needs requires that we embrace a multitude of various energy sources and applications. Nuclear energy must be a major portion of the distribution. One often-cited strategic hurdle to the commercial production of nuclear energy is the apparent lack of an acceptable nuclear waste repository. This issue has been quietly addressed at the U. S. Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP; see http://www.wipp.energy.gov), the closest population center of significant size being Carlsbad, New Mexico. WIPP has been operating for about nine years, disposing of over 250,000 drum-equivalents of nuclear waste. From the standpoint of addressing operational and environmental risk, as well as public fear, WIPP has had extensive human health and environmental monitoring. The Carlsbad Environmental Monitoring and Research Center is in the Institute for Energy and the Environment, in the College of Engineering at New Mexico State University. Located in Carlsbad, NM, CEMRC has been the independent monitoring facility for the area around WIPP from 1993 to the present, i.e., from six years before disposal operations began to nine years of waste disposal operations (www.cemcr.org). Based on the radiological analyses of monitoring samples completed to date for area residents and site workers, and for selected aerosols, soils, sediments, drinking water and surface waters, there is no evidence of increases in radiological contaminants in the region of WIPP that could be attributed to releases from WIPP. Levels of radiological and non-radiological analytes measured since operations began in 1999 have been within the range of baseline levels measured previously, and are within the ranges measured by other entities at the State and local levels since well before disposal phase operations began in 1999. (authors)
Conca, J.; Kirchner, Th.; Monk, J.; Sage, S. [Carlsbad Environmental Monitoring and Research Center, IEE NMSU, 1400 University Drive, Carlsbad, NM (United States)
April 1 - June 30, 2008 April 1 - June 30, 2008 DOE Site Manager: Jalena Maestas This report summarizes current project status, activities implemented during April through June 2008, and provides a schedule of planned near term activities, for the Monticello Mill Tailings Site (MMTS) and the Monticello Vicinity Properties (MVP) NPL sites. This report also includes repository and Pond 4 leachate collection data, quarterly site inspection results, and site meteorological monitoring data. 1.0 MMTS Activities/Status Repository and Pond 4 * Monthly and quarterly inspection of the repository identified no abnormalities. * Shrub seedlings planted last fall had a poor survival rate. * New damage to shrubs and vole infestation is not evident. * Monthly inspection of Pond 4 identified no abnormalities.
.. ' \ MONTICELLO NPL SITES FFA QUARTERLY REPORT: October 1 -December 31, 2008 DOE Site Manager: Jalena Dayvault JR 7CJ7 This report summarizes current project status and activities implemented during October tiU'ough December 2008, and provides a schedule of planned near term activities for the Monticello MIII Tailings Site (MMTS) and the Monticello Vicinity Properties (MVP) NPL sites. This report also includes repository and Pond 4 leachate collection data, quarterly site inspection repmis, site meteorological data, and monitoring summary for tlw ex situ ground water treatment system. 1.0 MMTS Activities/Status Repository and Pond 4 · * Monthly and quarterly inspection of the repository identified no abnormalities (see attached repmis). .
Ya ri a bsod Collection 5
last updated by World Oral Literature Project staff on Wednesday, Tuesday, June 8, 2010 This Accession Form for Individual Recordings: Collection / Collector Name Ya ri a bsod Collection/Sha bo don �grub rdo rje and Skal dbang skyid ???????...
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MPI Collective Operations over IP Multicast
Many common implementations of Message Passing Interface (MPI) implement collective operations over point-to-point operations. This work examines IP multicast as a framework for collective operations. IP multicast is not reliable. If a receiver is not ...
Hsiang Ann Chen; Yvette O. Carrasco; Amy W. Apon
Intensifying the collective use of public place
The premise of the thesis states that to intensify the collective use of public place there must exist a broad collective understanding of physical constituents that 'build' spatial relationships. These spatial understandings ...
Aldrich, Darrell E. (Darrell Eugene)
Numerical study of the thm effects on the near-field safety of a hypothetical nuclear waste repository - bmt1 of the decovalex iii project. part 1: conceptualization and characterization of the problems and summary of results
071, Power Reactor and Nuclear Fuel Development Corporation,safety assessment of a nuclear fuel waste repository in aPower Reactor and Nuclear Fuel Development Corporation.
Anisotropic collective flow of a Lorentz gas
Analytical results for the anisotropic collective flow of a Lorentz gas of massless particles scattering on fixed centres are presented.
Nicolas Borghini; Clement Gombeaud
Home Energy Score Data Collection Sheet
Energy Score - Data Collection 1 Energy Score - Data Collection 1 Revised 6/12/2013 Home Energy Scoring Tool Data Collection Sheet Location Information Address: ________________________________ City: ________________ State: _____ Zip: ______ Assessment Type: Initial / Test / Corrected / QA / Alternative EEM (Energy Efficiency Measures) / Final Assessment Date: _________________ Qualified Assessor: ______________________________ Comments: ________________________________________________________________________ __________________________________________________________________________________ __________________________________________________________________________________ __________________________________________________________________________________
Forming test collections with no system pooling
Forming test collection relevance judgments from the pooled output of multiple retrieval systems has become the standard process for creating resources such as the TREC, CLEF, and NTCIR test collections. This paper presents a series of experiments examining ... Keywords: evaluation of qrel sets, test collection formation
Mark Sanderson; Hideo Joho
Cost Comparison for the Transfer of Select Calcined Waste Canisters to the Monitored Geologic Repository at Yucca Mountain, NV
This report performs a life-cycle cost comparison of three proposed canister designs for the shipment and disposition of Idaho National Laboratory high-level calcined waste currently in storage at the Idaho Nuclear Technology and Engineering Center to the proposed national monitored geologic repository at Yucca Mountain, Nevada. Concept A (2 � 10-ft) and Concept B (2 � 15-ft) canisters are comparable in design, but they differ in size and waste loading options and vary proportionally in weight. The Concept C (5.5 � 17.5-ft) canister (also called the �super canister�), while similar in design to the other canisters, is considerably larger and heavier than Concept A and B canisters and has a greater wall thickness. This report includes estimating the unique life-cycle costs for the three canister designs. Unique life-cycle costs include elements such as canister purchase and filling at the Idaho Nuclear Technology and Engineering Center, cask preparation and roundtrip consignment costs, final disposition in the monitored geologic repository (including canister off-loading and placement in the final waste disposal package for disposition), and cask purchase. Packaging of the calcine "as-is" would save $2.9 to $3.9 billion over direct vitrification disposal in the proposed national monitored geologic repository at Yucca Mountain, Nevada. Using the larger Concept C canisters would use 0.75 mi less of tunnel space, cost $1.3 billion less than 10-ft canisters of Concept A, and would be complete in 6.2 years.
Michael B. Heiser; Clark B. Millet
A literature review of coupled thermal-hydrologic-mechanical-chemical processes pertinent to the proposed high-level nuclear waste repository at Yucca Mountain
A literature review has been conducted to determine the state of knowledge available in the modeling of coupled thermal (T), hydrologic (H), mechanical (M), and chemical (C) processes relevant to the design and/or performance of the proposed high-level waste (HLW) repository at Yucca Mountain, Nevada. The review focuses on identifying coupling mechanisms between individual processes and assessing their importance (i.e., if the coupling is either important, potentially important, or negligible). The significance of considering THMC-coupled processes lies in whether or not the processes impact the design and/or performance objectives of the repository. A review, such as reported here, is useful in identifying which coupled effects will be important, hence which coupled effects will need to be investigated by the US Nuclear Regulatory Commission in order to assess the assumptions, data, analyses, and conclusions in the design and performance assessment of a geologic reposit``. Although this work stems from regulatory interest in the design of the geologic repository, it should be emphasized that the repository design implicitly considers all of the repository performance objectives, including those associated with the time after permanent closure. The scope of this review is considered beyond previous assessments in that it attempts with the current state-of-knowledge) to determine which couplings are important, and identify which computer codes are currently available to model coupled processes.
Manteufel, R.D.; Ahola, M.P.; Turner, D.R.; Chowdhury, A.H. [Southwest Research Inst., San Antonio, TX (United States). Center for Nuclear Waste Regulatory Analyses
This work was performed through the University of North Dakota (UND) Chemical Engineering Department with assistance from UND's Energy & Environmental Research Center. This research was undertaken in response to the U.S. Department of Energy Federal Technology Center Program Solicitation No. DE-PS26-99FT40479, Support of Advanced Coal Research at U.S. Universities and Colleges. Specifically, this research was in support of the UCR Core Program and addressees Topic 1, Improved Hot-Gas Contaminant and Particulate Removal Techniques, introducing an advanced design for particulate removal. Integrated gasification combined cycle (IGCC) offers the potential for very high efficiency and clean electric generation. In IGCC, the product gas from the gasifier needs to be cleaned of particulate matter to avoid erosion and high-temperature corrosion difficulties arising with the turbine blades. Current methods involve cooling the gases to {approx}100 C to condense alkalis and remove sulfur and particulates using conventional scrubber technology. This ''cool'' gas is then directed to a turbine for electric generation. While IGCC has the potential to reach efficiencies of over 50%, the current need to cool the product gas for cleaning prior to firing it in a turbine is keeping IGCC from reaching its full potential. The objective of the current project was to develop a highly reliable particulate collector system that can meet the most stringent turbine requirements and emission standards, can operate at temperatures above 1500 F, is applicable for use with all U.S. coals, is compatible with various sorbent injection schemes for sulfur and alkali control, can be integrated into a variety of configurations for both pressurized gasification and combustion, increases allowable face velocity to reduce filter system capital cost, and is cost-competitive with existing technologies. The collector being developed is a new concept in particulate control called electrostatically enhanced barrier filter collection (EBFC). This concept combines electrostatic precipitation (ESP) with candle filters in a single unit. Similar technology has been recently proven on a commercial scale for atmospheric applications, but needed to be tested at high temperatures and pressures. The synergy obtained by combining the two control technologies into a single system should actually reduce filter system capital and operating costs and make the system more reliable. More specifically, the ESP is expected to significantly reduce candle filter load and also to limit ash reintrainment, allowing for full recovery of baseline pressure drop during backpulsing of the filters.
John Erjavec; Michael D. Mann; Ryan Z. Knutson; Michael L. Swanson; Michael E. Collings
Geothermal evaluation and analysis of the Yucca Mountain Repository, Nevada; Final report, July 1, 1989--December 31, 1989
This is the final report on the geothermal analysis and evaluation for the proposed nuclear waste repository at Yucca Mountain, for the period of July 1, 1989 to December 31, 1989. Heat flow values were derived by measuring the thermal conductivities of samples taken from selected exploratory wells. Temperature gradients are recorded from the same wells. By using computer generated contour maps of the area, another interpretation of the heat-flow can be derived. Results of the mapping do not coincide with the past observations of the data. Another method used to evaluate the heat-flow of Yucca Mountain was to compare the temperature-depth relationship of the area. (MB)
Iterators can be independent �from� their collections
External iterators pose problems for alias control mechanisms: they have access to collection interals and yet are not accessible from the collection; they may be used in contexts that are unaware of the collection. And yet iterators can benefit from alias control because iterators may fail �unexpectedly � when their collections are modified. We explain a novel aliasing annotation �from � that indicates when a collection intends to delegate its access to internals to a new object and how it can be given semantics using a fractional permission system. We sketch how a static analysis using permissions can statically detect possible concurrent modification exceptions. 1.
John Boyland
Feasibility Study on the Enlargement of the Surface Repository for LILW at Mochovce, Slovak Republic
In the Slovak Republic the sources of radioactive waste include the operation of the Mochovce and Bohunice nuclear power plants, decommissioning activities currently carried out and/or planned at Bohunice and elsewhere, as well as the use of radioactive sources in research, industry, and medicine. Pursuant to the Slovak policy low and intermediate level radioactive waste (LILW) containing predominantly short-lived radionuclides (LILW-SL), which is amenable for surface disposal, shall be disposed of at the National Radioactive Waste Repository (NRR) at Mochovce, which was designed to take all Slovak LILW-SL and which currently is in routine operation. The NRR site covers approximately 11 ha, currently only some 20 % of this area is used with two double rows of 20 reinforced concrete vaults each. The dimensions of a vault are 17.4 x 5.4 x 5.5 m, with an effective volume of 510 m{sup 3}. The total capacity of the two existing double rows (80 vaults) is enough to accommodate a net volume of radioactive waste of 22,320 m{sup 3}. Until the end of 2006 some 17 % of that capacity had already been used up. The NRR can receive in addition to the waste resulting from decommissioning the Bohunice A1 NPP pilot power reactor (under decommissioning since 1979) all the routinely produced Slovak waste until approximately 2020. However, the early shutdown of the Bohunice V1 Unit 1 end of 2006 and the planned shutdown of Unit 2 in 2008 with their following decommissioning will require additional disposal capacity well ahead of the initial time schedule. In this context it appears meaningful, to analyze anew the regulatory boundary conditions, existing disposal options and the corresponding waste categories. The main purpose of the feasibility study is to analyze alternatives for optimization of LILW management in the Slovak Republic as well as for the enlargement of the NRR at Mochovce, which will allow to dispose of the waste generated by the decommissioning of the nuclear power plants Bohunice A1 and V1 as well as waste arising from the operation of the Mochovce and Bohunice V2 NPPs and institutional waste. This paper describes the situation in the field of waste disposal in the Slovak Republic, the reasons leading to the decision of enlarging the NRR, the approach developed to select the optimum solution out of eight different enlargement variants, and first proposals and concepts for the enlargement of the NRR developed in the course of the project. (authors)
Haverkamp, B.; Biurrun, E. [DBE Technology GmbH, Peine (Germany); Sanchez Sudon, J. [INITEC NUCLEAR S.A., Madrid (Spain); Sedliak, D. [Jadrova a vyrad'ovacia spoloenost', a.s., Jaslovske Bohunice (Slovakia)
Draft Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spend Nuclear Fuel and High-Leval Radioactive Waste at Yucca Mountain, Nye County, Nevada
Draft Draft Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada U.S. Department of Energy Office of Civilian Radioactive Waste Management DOE/EIS-0250F-S1D October 2007 Table of Contents Summary Draft Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada Summary U.S. Department of Energy Office of Civilian Radioactive Waste Management DOE/EIS-0250F-S1D October 2007 Printed on recycled paper with soy ink. COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) TITLE: Draft Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal
Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada Volume I Impact Analyses Chapters 1 through 13 U.S. Department of Energy Office of Civilian Radioactive Waste Management DOE/EIS-0250F-S1D October 2007 Printed on recycled paper with soy ink. COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) TITLE: Draft Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada (DOE/EIS-0250F-S1D) (Repository SEIS). CONTACTS: For more information about this document, For general information on the DOE NEPA process, write
Areal power density: A preliminary examination of underground heat transfer in a potential Yucca Mountain repository and recommendations for thermal design approaches; Yucca Mountain Site Characterization Project
The design of the potential Yucca Mountain repository is subject to many thermal goals related to the compliance of the site with federal regulations. This report summarizes a series of sensitivity studies that determined the expected temperatures near the potential repository. These sensitivity studies were used to establish an efficient loading scheme for the spent fuel canisters and a maximum areal power density based strictly on thermal goals. Given the current knowledge of the site, a design-basis areal power density of 80 kW/acre can be justified based on thermal goals only. Further analyses to investigate the impacts of this design-basis APD on mechanical and operational aspects of the potential repository must be undertaken before a final decision is made.
Hertel, E.S. Jr.; Ryder, E.E.
Southern Nevada residents` views about the Yucca Mountain high-level nuclear waste repository and related issues: A comparative analysis of urban and rural survey data
two separate surveys were undertaken in 1988 to ascertain southern Nevadans` views about the Yucca Mountain repository and related issues. The first of these studies focused on the attitudes and perceptions of residents in the Las Vegas metropolitan area. The second study addressed similar issues, but focused on the views of residents in six rural communities in three counties adjacent to the Yucca Mountain site. However, parallel findings from the two data sets have not been jointly analyzed in order to identify ways in which the views and orientations of residents in the rural and urban study areas may be similar or different. The purpose of this report is to develop and present a comparative assessment of selected issues addressed in the rural and urban surveys. Because both urban and rural populations would potentially be impacted by the Yucca Mountain repository, such an analysis will provide important insights into possible repository impacts on the well-being of residents throughout southern Nevada.
Krannich, R.S.; Little, R.L. [Utah State Univ., Logan, UT (United States); Mushkatel, A.; Pijawka, K.D.; Jones, P. [Arizona State Univ., Tempe, AZ (United States)
Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, vertical emplacement mode: Volume 1
This Conceptual Design Report describes the conceptual design of a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. Waste receipt, processing, packing, and other surface facility operations are described. Operations in the shafts underground are described, including waste hoisting, transfer, and vertical emplacement. This report specifically addresses the vertical emplacement mode, the reference design for the repository. Waste retrieval capability is described. The report includes a description of the layout of the surface, shafts, and underground. Major equipment items are identified. The report includes plans for decommissioning and sealing of the facility. The report discusses how the repository will satisfy performance objectives. Chapters are included on basis for design, design analyses, and data requirements for completion of future design efforts. 105 figs., 52 tabs.
Progress report on the results of testing advanced conceptual design metal barrier materials under relevant environmental conditions for a tuff repository
This report discusses the performance of candidate metallic materials envisioned for fabricating waste package containers for long-term disposal at a possible geological repository at Yucca Mountain, Nevada. Candidate materials include austenitic iron-base to nickel-base alloy (AISI 304L, AISI 316L, and Alloy 825), high-purity copper (CDA 102), and copper-base alloys (CDA 613 and CDA 715). Possible degradation modes affecting these container materials are identified in the context of anticipated environmental conditions at the repository site. Low-temperature oxidation is the dominant degradation mode over most of the time period of concern (minimum of 300 yr to a maximum of 1000 yr after repository closure), but various forms of aqueous corrosion will occur when water infiltrates into the near-package environment. The results of three years of experimental work in different repository-relevant environments are presented. Much of the work was performed in water taken from Well J-13, located near the repository, and some of the experiments included gamma irradiation of the water or vapor environment. The influence of metallurgical effects on the corrosion and oxidation resistance of the material is reviewed; these effects result from container fabrication, welding, and long-term aging at moderately elevated temperatures in the repository. The report indicates the need for mechanisms to understand the physical/chemical reactions that determine the nature and rate of the different degradation modes, and the subsequent need for models based on these mechanisms for projecting the long-term performance of the container from comparatively short-term laboratory data. 91 refs., 17 figs., 16 tabs.
McCright, R.D.; Halsey, W.G.; Van Konynenburg, R.A.
Vitrification treatment options for disposal of greater-than-Class-C low-level waste in a deep geologic repository
The Department of Energy (DOE), in keeping with their responsibility under Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985, is investigating several disposal options for greater-than-Class C low-level waste (GTCC LLW), including emplacement in a deep geologic repository. At the present time vitrification, namely borosilicate glass, is the standard waste form assumed for high-level waste accepted into the Civilian Radioactive Waste Management System. This report supports DOE`s investigation of the deep geologic disposal option by comparing the vitrification treatments that are able to convert those GTCC LLWs that are inherently migratory into stable waste forms acceptable for disposal in a deep geologic repository. Eight vitrification treatments that utilize glass, glass ceramic, or basalt waste form matrices are identified. Six of these are discussed in detail, stating the advantages and limitations of each relative to their ability to immobilize GTCC LLW. The report concludes that the waste form most likely to provide the best composite of performance characteristics for GTCC process waste is Iron Enriched Basalt 4 (IEB4).
Fullmer, K.S.; Fish, L.W.; Fischer, D.K.
Salton Sea Geothermal Field, California, as a near-field natural analog of a radioactive waste repository in salt
Since high concentrations of radionuclides and high temperatures are not normally encountered in salt domes or beds, finding an exact geologic analog of expected near-field conditions in a mined nuclear waste repository in salt will be difficult. The Salton Sea Geothermal Field, however, provides an opportunity to investigate the migration and retardation of naturally occurring U, Th, Ra, Cs, Sr and other elements in hot brines which have been moving through clay-rich sedimentary rocks for up to 100,000 years. The more than thirty deep wells drilled in this field to produce steam for electrical generation penetrate sedimentary rocks containing concentrated brines where temperatures reach 365/sup 0/C at only 2 km depth. The brines are primarily Na, K, Ca chlorides with up to 25% of total dissolved solids; they also contain high concentrations of metals such as Fe, Mn, Li, Zn, and Pb. This report describes the geology, geophysics and geochemistry of this system as a prelude to a study of the mobility of naturally occurring radionuclides and radionuclide analogs within it. The aim of this study is to provide data to assist in validating quantitative models of repository behavior and to use in designing and evaluating waste packages and engineered barriers. 128 references, 33 figures, 13 tables.
Elders, W.A.; Cohen, L.H.
National Geoscience Data Repository System: Phase 2, Planning and pilot study. Progress report, February--April 1995
The American Geological Institute (AGI) recently completed the first phase of a multiphase program to study and implement a National Geoscience Data Repository System (NGDRS) to capture and preserve valuable geoscientific data. They study was initiated in response to the fact that tens of billions of dollars worth of domestic eological and geophysical data are in jeopardy of being irrevocably lost or destroyed as a consequence of the ongoing downsizing of the US energy and minerals industry. The NGDRS would serve as an important and valuable source of information for the entire geoscience community for a variety of applications, including environmental protection, water resource management, global change studies, reducing risks from earthquakes and other geologic hazards, and basic and applied research. The repository system would also contain critical data that would enable domestic energy and minerals companies to expand their exploration and production programs in the United States for increased recovery of domestic oil, gas, and mineral resources. Progress is reported on the second phase of this program.
Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project
This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE`s Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ``current information`` or ``available evidence.``
Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C. [Science Applications International Corp., Las Vegas, NV (United States); Ballou, L.B.; Revelli, M.A. [Lawrence Livermore National Lab., CA (United States); Ducharme, A.R.; Shephard, L.E. [Sandia National Labs., Albuquerque, NM (United States); Dudley, W.W.; Hoxie, D.T. [Geological Survey, Denver, CO (United States); Herbst, R.J.; Patera, E.A. [Los Alamos National Lab., NM (United States); Judd, B.R. [Decision Analysis Co., Portola Valley, CA (United States); Docka, J.A.; Rickertsen, L.D. [Weston Technical Associates, Washington, DC (United States)
National Geoscience Data Repository System: Phase 2 -- Planning and pilot study. Progress report 1. quarter, February--April, 1995
The American Geological Institute (AGI) recently completed the first phase of a multiphase program to study and implement a National Geoscience Data Repository System (NGDRS) to capture and preserve valuable geoscientific data. The study was initiated in response to the fact that tens of billions of dollars worth of domestic geological and geophysical data are in jeopardy of being irrevocably lost or destroyed as a consequence of the ongoing downsizing of the US energy and minerals industry. The NGDRS would serve as an important and valuable source of information for the entire geoscience community for a variety of applications, including environmental protection, water resource management, global change studies, reducing risks from earthquakes and other geologic hazards, and basic and applied research. The repository system would also contain critical data that would enable domestic energy and minerals companies to expand their exploration and production programs in the US for increased recovery of domestic oil, gas, and mineral resources. The proposed Phase 2 study has four major components: planning and specification; directory of geoscience data centers; pilot projects; and steering committee operations.
Critical assessment of seismic and geomechanics literature related to a high-level nuclear waste underground repository
A comprehensive literature assessment has been conducted to determine the nature and scope of technical information available to characterize the seismic performance of an underground repository and associated facilities. Significant deficiencies were identified in current practices for prediction of seismic response of underground excavations in jointed rock. Conventional analytical methods are based on a continuum representation of the host rock mass. Field observations and laboratory experiments indicate that, in jointed rock, the behavior of the joints controls the overall performance of underground excavations. Further, under repetitive seismic loading, shear displacement develops progressively at block boundaries. Field observations correlating seismicity and groundwater conditions have provided significant information on hydrological response to seismic events. However, lack of a comprehensive model of geohydrological response to seismicity has limited the transportability conclusions from field observations. Based on the literature study, matters requiring further research in relation to the Yucca Mountain repository are identified. The report focuses on understanding seismic processes in fractured tuff, and provides a basis for work on the geohydrologic response of a seismically disturbed rock mass. 220 refs., 43 figs., 11 tabs.
Kana, D.D.; Vanzant, B.W.; Nair, P.K. [Southwest Research Inst., San Antonio, TX (USA). Center for Nuclear Waste Regulatory Analyses; Brady, B.H.G. [ITASCA Consulting Group, Inc., Minneapolis, MN (USA)
Potential influence of organic compounds on the transport of radionuclides from a geologic repository. Assessment of effectiveness of geologic isolation systems
This study identifies organic compounds that may be present in a repository and outlines plausible interactions and mechanisms that may influence the forms and chemical behavior of these compounds. A review of the literature indicates that large quantities of organic radioactive wastes are generated by the nuclear industry and if placed in a repository could increase or decrease the leach rate and sorption characteristics of waste radionuclides. The association of radionuclides with organic matter can render the nuclides soluble or insoluble depending on the particular nuclide and such parameters as the pH, Eh, and temperature of the hydrogeologic system as well as the properties of the organic compounds themselves. 44 references.
Silviera, D.J.
Spore collection and elimination apparatus and method
The present invention is for a spore collection apparatus and its method of use. The portable spore collection apparatus includes a suction source, a nebulizer, an ionization chamber and a filter canister. The suction source collects the spores from a surface. The spores are activated by heating whereby spore dormancy is broken. Moisture is then applied to the spores to begin germination. The spores are then exposed to alpha particles causing extinction.
Czajkowski, Carl (South Jamesport, NY); Warren, Barbara Panessa (Port Jefferson, NY)
Collective motion in quantum diffusive environment
The general problem of dissipation in macroscopic large-amplitude collective motion and its relation to energy diffusion of intrinsic degrees of freedom of a nucleus is studied. By applying the cranking approach to the nuclear many-body system, a set of coupled dynamical equations for the collective classical variable and the quantum mechanical occupancies of the intrinsic nuclear states is derived. Different dynamical regimes of the intrinsic nuclear motion and its consequences on time properties of collective dissipation are discussed.
V. M. Kolomietz; S. � berg; S. V. Radionov
Collective Bargaining Agreement | Department of Energy
Collective Bargaining Agreement Collective Bargaining Agreement Collective Bargaining Agreement This collective bargaining agreement is entered into to prescribe certain rights and obligations of the employees of the Department of Energy (DOE) Headquarters represented by the National Treasury Employees Union and to delineate procedures which are designed to meet the special requirements and needs of DOE Headquarters. The provisions of this agreement have been negotiated and should be interpreted in a manner consistent with the requirements of an effective and efficient Department. The Department of Energy (DOE) Headquarters and the National Treasury Employees Union are dedicated to partnership efforts designed to assure success for our respective organizations and to maintain a cooperative and constructive
Collective Impact for Zero Net Energy Homes
Collective Impact For ZNERH SAM RASHKIN Chief Architect, BTO Building America Annual Stakeholder Meeting April 30, 2013 Strategy for Social Change Collective Impact: The commitment of a group of important actors from different sectors to a common agenda for solving a specific social problem. "Collective Impact" by John Kania and Mark Kramer Stanford Social Innovation Review Winter 2011 2 | INNOVATION & INTEGRATION: Transforming the Energy Efficiency Market Buildings.Energy.gov Examples of Collective Impact "Remarkable Exceptions" * Strive Public Education in Greater Cincinnati * Elizabeth River Project in Southeast Virginia * Shape Up Childhood Obesity Summerville, MA 3 | INNOVATION & INTEGRATION: Transforming the Energy Efficiency Market Buildings.Energy.gov
Data Collection and Mapping | Open Energy Information
Open Energy Info (EERE)
Data Collection and Mapping Data Collection and Mapping Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Data Collection and Mapping Details Activities (0) Areas (0) Regions (0) NEPA(0) Exploration Technique Information Exploration Group: Field Techniques Exploration Sub Group: Data Collection and Mapping Parent Exploration Technique: Field Techniques Information Provided by Technique Lithology: Map surface geology and hydrothermal alteration. Bulk and trace element analysis of rocks, minerals, and sediments. Identify and document surface geology and mineralogy. Rapid and unambiguous identification of unknown minerals.[1] Stratigraphic/Structural: Locates active faults in the area of interest. Map fault and fracture patterns, kinematic information
Data Collection for Project Management and Performance
Data Collection for Project Management and Performance Donald Macdonald November 19, 2009 DOE's PM Approach Provide DOE with project information to allow DOE to adequately...
Charge-collection mechanisms of heterostructure FETs
Ion- and laser-induced charge-collection transients measured for AlGaAs/InGaAs heterostructure insulated-gate field-effect transistors (HIGFETs) reveal evidence for two mechanisms of enhanced charge collection: a channel-modulation mechanism that dominates the charge-collection processes at positive gate biases and can persist for several nanoseconds; and a parasitic bipolar transistor mechanism that shows a sensitive dependence on the density of free carriers injected into the device, and is complete within a few hundred picoseconds. The results reinforce the utility of the laser technique for investigating the charge-collection mechanisms of semiconductor devices.
McMorrow, D.; Melinger, J.S.; Thantu, N.; Campbell, A.B. (Naval Research Lab., Washington, DC (United States)); Weatherford, T.R.; Knudson, A.R.; Tran, L.H. (SFA, Inc., Landover, MD (United States)); Peczalski, A. (Honeywell, Inc., Bloomington, MN (United States))
Advanced Vehicle Testing Activity - Data Collection Partners
Data Collection Partners Last Updated: Wednesday, September 25, 2013 Copyright 2014 Idaho National Laboratory SecurityPrivacy DOE Idaho URL: http:avt.inel.govpartners...
Microalgae Culture Collection: 1984-1985
The Microalgae Culture Collection at the Solar Energy Research Institute has been established for the maintenance and distribution of strains that have been characterized for biomass fuel applications.
Geothermal Technologies Legacy Collection Data Service | Data...
Geothermal Technologies Legacy Collection Data Service Consumer Data Apps Challenges Resources About Blogs Let's Talk Feedback Consumer You are here Data.gov Communities ...
The Department of Energy (DOE) invites public comment on DOE's request the Office of Management and Budget (OMB) to extend for three years the emergency Information Collection...
Water Data Collection in the 2007 CBECS
Gasoline and Diesel Fuel Update (EIA)
Water Data Collection in the 2007 CBECS CBECS 2007 - Release date: August 28, 2012 Did you know? Select water data results are described in the accompanying report, Energy...
Optimization Online - Social Cognitive Maps, Swarm Collective ...
Mar 2, 2005 ... Abstract: Swarm Intelligence (SI) is the property of a system whereby the collective behaviors of (unsophisticated) entities interacting locally�...
Measured Collection Efficiencies for Cloud Drops
The collection efficiency has been measured for 15 size pairs of relatively uncharged drops in over 400 experimental runs. The results indicate that collection efficiencies fall in a narrow range of 0.60 to 0.70 even though the collector drop was ...
K. V. Beard; Harry T. Ochs III
Guidance » Information Collection Management Guidance » Information Collection Management Information Collection Management The Paperwork Reduction Act (PRA) of 1995 requires each Federal agency to seek and obtain approval from the Office of Management and Budget (OMB) before undertaking a collection of information directed to 10 or more persons (including operations of Government-owned, contractor-operated facilities). Under the PRA, OMB approval for each information collection instrument can last a maximum of 3 years. This site provides information about the Paperwork Reduction Act's requirements and guidance in fulfilling those requirements. DOE's Chief Information Officer (CIO) is the Senior Official responsible for DOE's compliance with the Paperwork Reduction Act. Office of Management and
Current Status and Potential Impacts Regarding the Proposed Development of a Rail Line to the Yucca Mountain Nuclear Waste Repository
This paper provides a description of the current status regarding the proposed development of a rail line to the Yucca Mountain Nuclear Waste Repository in Nye County, Southern Nevada, which includes potential impacts analyzed during the National Environmental Policy Act (NEPA) process, and the subsequent creation of an Environmental Impact Statement (EIS) for the rail line. Potential impacts are addressed within the context of impacts to natural and human environmental resources found within the geographic area of the proposed federal project. Potential impacts to these resources have been fully analyzed in the Rail Alignment Draft EIS (DEIS). This paper includes a summary of the potential impacts analyzed in the DEIS. Examples of potential impacts include land use conflicts, air quality, water use, and impacts to biological and cultural resources, among others. In conclusion: Based on its obligations under the NWPA and its decision to select the mostly rail scenario for the transportation of spent nuclear fuel and high-level radioactive waste, DOE needs to ship these materials by rail in Nevada to a repository at Yucca Mountain. DOE prepared the Rail Alignment EIS to provide the background, data, information, and analyses to help decision makers and the public understand the potential environmental impacts that could result from constructing and operating a railroad for shipment of spent nuclear fuel, high-level radioactive waste, and other materials from an existing rail line in Nevada to a repository at Yucca Mountain. This railroad would consist of a rail line, railroad operations support facilities, and other related infrastructure. DOE will use the Rail Alignment EIS to decide whether to construct and operate the proposed railroad, and if so, to: - Select a rail alignment (Caliente rail alignment or Mina rail alignment) in which to construct the railroad; - Select the common segments and alternative segments within either a Caliente rail alignment or a Mina rail alignment. The Department would use the selected common segments and alternative segments to identify the public lands to be included in right-of-way applications; - Decide where to construct proposed railroad operations support facilities; - Decide whether to restrict use of the rail line to DOE trains, or whether to allow commercial shippers to operate over the rail line; and - Determine what mitigation measures to implement. (authors)
Lanthrum, G. [U.S. Department of Energy, Office of Civilian Radioactive Waste Management, Washington, DC (United States); Gunnerson, J. [Booz Allen Hamilton, Las Vegas, NV (United States)
Social impacts of hazardous and nuclear facilities and events: Implications for Nevada and the Yucca Mountain high-level nuclear waste repository; [Final report
Social impacts of a nuclear waste repository are described. Various case studies are cited such as Rocky Flats Plant, the Feed Materials Production Center, and Love Canal. The social impacts of toxic contamination, mitigating environmental stigma and loss of trust are also discussed.
Freudenburg, W.R. [Wisconsin Univ., Madison, WI (United States)] Wisconsin Univ., Madison, WI (United States); Carter, L.F.; Willard, W. [Washington State Univ., Pullman, WA (United States)] Washington State Univ., Pullman, WA (United States); Lodwick, D.G. [Miami Univ., Oxford, OH (United States)] Miami Univ., Oxford, OH (United States); Hardert, R.A. [Arizona State Univ., Tempe, AZ (United States)] Arizona State Univ., Tempe, AZ (United States); Levine, A.G. [State Univ. of New York, Buffalo, NY (United States). Dept. of Sociology] State Univ. of New York, Buffalo, NY (United States). Dept. of Sociology; Kroll-Smith, S. [New Orleans Univ., LA (United States)] New Orleans Univ., LA (United States); Couch, S.R. [Pennsylvania State Univ., University Park, PA (United States)] Pennsylvania State Univ., University Park, PA (United States); Edelstein, M.R. [Ramapo College, Mahwah, NJ (United States)] Ramapo College, Mahwah, NJ (United States)
Searching oURspace for Information on the Indian Act 2010, March 18 The oURspace digital repository contains both primary and secondary resources on the Indian
that link to read the full text of the item. Enter Indian Act in the Search oURSpace text box. This search the search further, the term "Canada" was used in addition to "Indian Act." Search other repositoriesSearching oURspace for Information on the Indian Act 2010, March 18 The oURspace digital
Water-Steel Canister Interaction and H2 Gas Pressure Buildup in aNuclear Waste Repository
Corrosion of steel canisters, stored in a repository forspent fuel and high-level waste, leads to hydrogen gas generation in thebackfilled emplacement tunnels, which may significantly affect long-termrepository safety. Previous modeling studies used a constant H2generation rate. However, iron corrosion and H2 generation rates varywith time, depending on factors such as water chemistry, wateravailability, and water contact area. To account for these factors andfeedback mechanisms, we developed a chemistry model related to ironcorrosion, coupled with two-phase (liquid and gas) flow phenomena thatare driven by gas pressure buildup and water consumption. Resultsindicate that if H2 generation rates are dynamically calculated based ona chemistry model, the degree and extent of gas pressure buildup are muchsmaller compared to a simulation in which the coupling between flow andreactive transport mechansism is neglected.
Xu, Tianfu; Senger, Rainer; Finstele, Stefan
Unsaturated flow and transport through fractured rock related to high-level waste repositories; Final report, Phase 3
Research results are summarized for a US Nuclear Regulatory Commission contract with the University of Arizona focusing on field and laboratory methods for characterizing unsaturated fluid flow and solute transport related to high-level radioactive waste repositories. Characterization activities are presented for the Apache Leap Tuff field site. The field site is located in unsaturated, fractured tuff in central Arizona. Hydraulic, pneumatic, and thermal characteristics of the tuff are summarized, along with methodologies employed to monitor and sample hydrologic and geochemical processes at the field site. Thermohydrologic experiments are reported which provide laboratory and field data related to the effects conditions and flow and transport in unsaturated, fractured rock. 29 refs., 17 figs., 21 tabs.
Evans, D.D.; Rasmussen, T.C. [Arizona Univ., Tucson, AZ (USA). Dept. of Hydrology and Water Resources
Notices ELECTION ASSISTANCE COMMISSION Agency Information Collection
23 Federal Register 23 Federal Register / Vol. 76, No. 180 / Friday, September 16, 2011 / Notices ELECTION ASSISTANCE COMMISSION Agency Information Collection Activities: Proposed Collection; Comment Request; Election Assistance Commission's Voting System Test Laboratory Program Manual, Version 1.0 AGENCY: U.S. Election Assistance Commission (EAC). ACTION: Notice; comment request. SUMMARY: As part of its continuing effort to reduce paperwork and respondent burden in accordance with the Paperwork Reduction Act of 1995, the U.S. Election Assistance Commission (EAC) invites the general public and other Federal agencies to take this opportunity to comment on EAC's request to renew an existing information collection, EAC's Voting System Test Laboratory Program Manual, Version
Collective Neutrino Flavor Transformation In Supernovae
We examine coherent active-active channel neutrino flavor evolution in environments where neutrino-neutrino forward scattering can engender large-scale collective flavor transformation. We point out a key quantity, the "total effective energy", which is conserved in several important regimes. Using this concept, we analyze collective neutrino and antineutrino flavor oscillation in the "synchronized" mode and what we term the "bi-polar" mode. We thereby are able to explain why large collective flavor mixing can develop on short timescales even when vacuum mixing angles are small in, e.g., a dense gas of initially pure $\
Huaiyu Duan; George M. Fuller; Yong-Zhong Qian
Repository Integration Program: RIP performance assessment and strategy evaluation model theory manual and user`s guide
This report describes the theory and capabilities of RIP (Repository Integration Program). RIP is a powerful and flexible computational tool for carrying out probabilistic integrated total system performance assessments for geologic repositories. The primary purpose of RIP is to provide a management tool for guiding system design and site characterization. In addition, the performance assessment model (and the process of eliciting model input) can act as a mechanism for integrating the large amount of available information into a meaningful whole (in a sense, allowing one to keep the ``big picture`` and the ultimate aims of the project clearly in focus). Such an integration is useful both for project managers and project scientists. RIP is based on a `` top down`` approach to performance assessment that concentrates on the integration of the entire system, and utilizes relatively high-level descriptive models and parameters. The key point in the application of such a ``top down`` approach is that the simplified models and associated high-level parameters must incorporate an accurate representation of their uncertainty. RIP is designed in a very flexible manner such that details can be readily added to various components of the model without modifying the computer code. Uncertainty is also handled in a very flexible manner, and both parameter and model (process) uncertainty can be explicitly considered. Uncertainty is propagated through the integrated PA model using an enhanced Monte Carlo method. RIP must rely heavily on subjective assessment (expert opinion) for much of its input. The process of eliciting the high-level input parameters required for RIP is critical to its successful application. As a result, in order for any project to successfully apply a tool such as RIP, an enormous amount of communication and cooperation must exist between the data collectors, the process modelers, and the performance. assessment modelers.
Information Collection Requests/Paper Reduction Act | Department...
Information Collection RequestsPaper Reduction Act Information Collection RequestsPaper Reduction Act Training Presentation on the on Information Collection and the Paper...
In order to demonstrate the feasibility of geological disposal of spent CANDU fuel in Canada, a safety assessment was performed for a hypothetical repository in the Canadian Shield. The assessment shows that such repository would meet international criteria for dose rate; however, uncertainties in the assumed evolution of the repository were identified. Such uncertainties could be resolved by the consideration of coupled Thermal-Hydro-Mechanical-Chemical (THMC) processes. In Task A of the DECOVALEX-THMC project, THM models were developed within the framework of the theory of poroelasticity. Such model development was performed in an iterative manner, using experimental data from laboratory and field tests. The models were used to perform near-field simulations of the evolution of the repository in order to address the above uncertainties. This paper presents the definition and rationale of task A and the results of the simulations. From a repository safety point of view, the simulations predict that the maximum temperature would be well below the design target of 100 C, however the load on the container can marginally exceed the design value of 15 MPa. However, the most important finding from the simulations is that a rock damage zone could form around the emplacement borehole. Such damage zone can extend a few metres from the walls of the emplacement holes, with permeability values that are orders of magnitude higher than the initial values. The damage zone has the potential to increase the radionuclide transport flux from the geosphere; the effect of such an increase should be taken into account in the safety assessment and mitigated if necessary by the provision of sealing systems.
Nguyen, T.S.; Borgesson, L.; Chijimatsu, M.; Hernelind, J.; Jing, L.; Kobayashi, A.; Rutqvist, J.
16 TRUCK ROLL STABILITY DATA COLLECTION AND ANALYSIS S. S. Stevens, Principal Investigator S. M. Chin K. A. Hake H. L. Hwang J. P. Rollow L. F. Truett July 2001 Prepared for the...
Bio-inspired collective analog computation
In this thesis, I present electronic circuit systems that mimic collective analog com- putation found in biology. By combining the advantages of analog and digital computation, these systems can lead to highly complex, ...
Woo, Sung Sik, S.M. Massachusetts Institute of Technology
Collective Modes of Quantum Hall Stripes
The collective modes of striped phases in a quantum Hall system are computed using the time-dependent Hartree-Fock approximation. Uniform stripe phases are shown to be unstable to the formation of modulations along the stripes, so that within the Hartree-Fock approximation the groundstate is a stripe crystal. Such crystalline states are generically gapped at any finite wavevector; however, in the quantum Hall system the interactions of modulations among different stripes is found to be remarkably weak, leading to an infinite collection of collective modes with immeasurably small gaps. The resulting long wavelength behavior is derivable from an elastic theory for smectic liquid crystals. Collective modes for the phonon branch are computed throughout the Brillouin zone, as are spin wave and magnetoplasmon modes. A soft mode in the phonon spectrum is identified for partial filling factors sufficiently far from 1/2, indicating a second order phase transition. The modes contain several other signatures that should be experimentally
R. C�t�; H. A. Fertig
Enlarging paraphrase collections through generalization and instantiation
This paper presents a paraphrase acquisition method that uncovers and exploits generalities underlying paraphrases: paraphrase patterns are first induced and then used to collect novel instances. Unlike existing methods, ours uses both bilingual parallel ...
Atsushi Fujita; Pierre Isabelle; Roland Kuhn
Document image collection using Amazon's Mechanical Turk
We present findings from a collaborative effort aimed at testing the feasibility of using Amazon's Mechanical Turk as a data collection platform to build a corpus of document images. Experimental design and implementation workflow are described. Preliminary ...
Audrey Le; Jerome Ajot; Mark Przybocki; Stephanie Strassel
Microsoft Word - DOEDataCollection031307.doc
Collection of DOE-Specific Data Elements in PADSWeb Collection of DOE-Specific Data Elements in PADSWeb Beginning in FY 2007, updating of certain DOE-specific data elements on FPDS-NG reportable awards will be permitted through the PADSWeb online forms. The data elements that will be collected are as follows: Retirement Date Contracting Officer Technical Representative Cognizant DOE Office E-Government Contract Specialist Cognizant Federal Agency OSTI Deliverable The DOE-specific data elements will be accessible via a redesigned version of the Miscellaneous Change form. Though the specific intent of this redesign is to provide update capability for the FPDS-NG reportable awards, this form will remain available for updating all awards collected in the PADSWeb application.
Ya ri a bsod Collection 1
last updated by World Oral Literature Project staff on Wednesday, Tuesday, June 8, 2010 Accession Form for Individual Recordings: Collection / Collector Name Ya ri a bsod Collection/Sha bo don �grub rdo rje and Skal dbang skyid ???????... of title Unknown Description (to be used in archive entry) At one time, Ya ri a bsod went to steal horses in Rta bo and was shot and injured. As he lay dying he sang this song to describe his situation. ???????????????????????????? ?????????...
Ya ri a bsod Collection 3
last updated by World Oral Literature Project staff on Wednesday, Tuesday, June 8, 2010 Accession Form for Individual Recordings: Collection / Collector Name Ya ri a bsod Collection/Sha bo don �grub rdo rje and Skal dbang skyid ???????... ??????????????????????????????? Genre or type (i.e. epic, song, ritual) Persuasion Song ??? ??????????????? Name of recorder (if different from collector) Date of recording February 2007 ????? ?????????????????????????? Place of recording Gtsang Village, Rta bo Town...
A method and apparatus for collecting isotopes having a high vapor pressure, such as isotopes of mercury, in a calutron are described. Heretofore, the collected material would vaporize and escape from the ion receiver as fast as it was received. By making the receiver of pure silver, the mercury isotopes form a nonvolatile amalgam with the silver at the water cooled temperature of the receiver, and the mercury is thus retained.
Leyshon, W.E.
Collecting operational event data for statistical analysis
This report gives guidance for collecting operational data to be used for statistical analysis, especially analysis of event counts. It discusses how to define the purpose of the study, the unit (system, component, etc.) to be studied, events to be counted, and demand or exposure time. Examples are given of classification systems for events in the data sources. A checklist summarizes the essential steps in data collection for statistical analysis.
Atwood, C.L.
Automated Sample collection and Analysis unit
Autoramp is an atmospheric radionuclide collection and analysis unit designed for unattended operation. A large volume of air passes through one of 31 filter cartridges which is then moved from a sampling chamber and past a bar code reader, to a shielded enclosure. The collected dust-borne radionuclides are counted with a high resolution germanium gamma-ray detector. An analysis is made and the results are transmitted to a central station that can also remotely control the unit.
Latner, Norman; Sanderson, Colin G.; Negro, Vincent C.
Transforming Big Data into Collective Awareness
Integrating social and sensor networks can transform big data, if treated as a knowledge commons, into a higher form of collective awareness that can motivate users to self-organize and create innovative solutions to various socioeconomic problems. The ... Keywords: Information management,Data handling,Data storage systems,Social network services,Computational modeling,Social factors,Smart grids,Data privacy,knowledge commons,big data,collective awareness,self-organizing systems
Jeremy Pitt, Aikaterini Bourazeri, Andrzej Nowak, Magda Roszczynska, Agnieszka Rychwalska, Inmaculada Rodriguez, Maite Lopez, Monica Florea, Mihai Sanduleac
Progress in validation of structural codes for radioactive waste repository applications in bedded salt
Over the last nine years, coordinated activities in laboratory database generation, constitutive model formulation, and numerical code capability development have led to an improved ability of thermal/structural codes to predict the creep deformation of underground rooms in bedded salt deposits. In the last year, these codes have been undergoing preliminary validation against an extensive database collected from the large scale underground structural in situ tests at the Waste Isolation Pilot Plant (WIPP) in Southeastern New Mexico. This validation exercise has allowed prediction capabilities to be evaluated for accuracy. We present here a summary of the predictive capability and the nature of the in situ database involved in the validation exercise. The WIPP validation exercise has proven to be especially productive. 7 refs., 4 figs., 1 tab.
Munson, D.E. (Sandia National Labs., Albuquerque, NM (USA)); DeVries, K.L. (RE/SPEC, Inc., Rapid City, SD (USA))
Financial Metrics Data Collection Protocol, Version 1.0
Brief description of data collection process and plan that will be used to collect financial metrics associated with sustainable design.
Fowler, Kimberly M.; Gorrissen, Willy J.; Wang, Na
Survey of Physical and Chemical Properties of Soils Collected From Former Manufactured Gas Plant Sites
This report presents technical information and data from a study of the physical and chemical nature of soils at former manufactured gas plant (MGP) sites. Included in the report is a comparison of chemical analysis methods for determination of monocyclic aromatic hydrocarbons (MAHs), polycyclic aromatic hydrocarbons (PAHs), and total petroleum hydrocarbons (TPH). One of the specific objectives of the research was determining relationships between total soil and leachate concentrations of analytes of int...
Advances in understanding solar energy collection materials
Understanding solar energy collection materials Understanding solar energy collection materials Advances in understanding solar energy collection materials A LANL team and collaborators have made advances in the understanding of how carbon nanotubes move charges created by light. November 9, 2012 Efficient energy transport in photovoltaic carbon nanomaterials Efficient energy transport in photovoltaic carbon nanomaterials. A LANL team and collaborators have made advances in the understanding of how carbon nanotubes move charges created by light. The research has applications for cheap, all-carbon-based photovoltaics and light detection elements. Their work measures exciton transport (excitons are small packets of energy made up of positive and negative charges) in carbon nanotubes at room temperature in a colloidal environment. A colloid is a substance that
National Human Radiobiological Tissue Repository (NHRTR) at the United States Transuranium and Uranium Registries
The NHRTR, one component of the USTUR, contains frozen tissues, tissue solutions, microscope slides, and paraffin blocks that were collected by the USTUR at the autopsy of workers with documented intakes of plutonium, americium, uranium, and thorium. The samples are available to qualified scientists for further research. Thousands of frozen, ashed, dried, and plastic embedded bone samples from the radium studies carried out by Argonne National Laboratory, Argonne Cancer Research Hospital, the Massachusetts Institute of Technology, and the New Jersey Radium Research Project are available and linked by case number to de-identified, published case data. These data include the person's source of exposure (dial painter, therapeutic injection, etc.), estimated body burden, radiochemical results, and medical history. Other samples, including organs and whole body donations, have come from volunteer donors who were impacted by elements such as plutonium, throium, etc. See the USTUR website for information on how to apply for research samples or how to become a volunteer donor. [Information taken from http://www.ustur.wsu.edu/NHRTR/index.html#
Some Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository Study (The Yucca Mountain Project)
The safe disposal of radioactive waste requires that the waste be isolated from the environment until radioactive decay has reduced its toxicity to innocuous levels for plants, animals, and humans. All of the countries currently studying the options for disposing of high-level nuclear waste (HLW) have selected deep geologic formations to be the primary barrier for accomplishing this isolation. In U.S.A., the Nuclear Waste Policy Act of 1982 (as amended in 1987) designated Yucca Mountain in Nevada as the potential site to be characterized for high-level nuclear waste (HLW) disposal. Long-term containment of waste and subsequent slow release of radionuclides into the geosphere will rely on a system of natural and engineered barriers including a robust waste containment design. The waste package design consists of a highly corrosion resistant Ni-based Alloy 22 cylindrical barrier surrounding a Type 316 stainless steel inner structural vessel. The waste package is covered by a mailbox-shaped drip shield composed primarily of Ti Grade 7 with Ti Grade 24 structural support members. The U.S. Yucca Mountain Project has been studying and modeling the degradation issues of the relevant materials for some 20 years. This paper reviews the state-of-the-art understanding of the degradation processes based on the past 20 years studies on Yucca Mountain Project (YMP) materials degradation issues with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the 10,000 years regulatory period. This paper provides an overview of the current understanding of the likely degradation behavior of the waste package and drip shield in the repository after the permanent closure of the facility. The degradation scenario discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced cracking of Alloy 22 and titanium alloys. The effects of microbial activity and radiation on degradation of Alloy 22 and titanium alloys are also discussed. Further, for titanium alloys, the effects of fluorides, bromides, calcium ions, and galvanic coupling to less noble metals are further considered. It is concluded that, as far as materials degradation is concerned, the materials and design adopted in the U.S. Yucca Mountain Project will provide sufficient safety margins within the 10,000-years regulatory period.
F. Hua; P. Pasupathi; N. Brown; K. Mon
Draft Supplemental Environmental Impact Statement for a Geologice Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mounta
v v COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) TITLE: Draft Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada - Nevada Rail Transportation Corridor (DOE/EIS-0250F-S2D; the Nevada Rail Corridor SEIS), and Draft Environmental Impact Statement for a Rail Alignment for the Construction and Operation of a Railroad in Nevada to a Geologic Repository at Yucca Mountain, Nye County, Nevada (DOE/EIS-0369D; the Rail Alignment EIS) CONTACTS: For more information about this document, write or call: For general information on the DOE NEPA process, write or call: U.S. Department of Energy Office of Civilian Radioactive Waste Management
Bridging the Gap in the Chemical Thermodynamic Database for Nuclear Waste Repository: Studies of the Effect of Temperature on Actinide Complexation
Recent results of thermodynamic studies on the complexation of actinides (UO{sub 2}{sup 2+}, NpO{sub 2}{sup +} and Pu{sup 4+}) with F{sup -}, SO{sub 4}{sup 2-} and H{sub 2}PO{sub 4}{sup -}/HPO{sub 4}{sup 2-} at elevated temperatures are reviewed. The data indicate that, for all systems except the 1:1 complexation of Np(V) with HPO{sub 4}{sup 2-}, the complexation of actinides is enhanced by the increase in temperature. The enhancement is primarily due to the increase in the entropy term (T{Delta}S) that exceeds the increase in the enthalpy ({Delta}H) as the temperature is increased. These data bridge the gaps in the chemical thermodynamic database for nuclear waste repository where the temperature could remain significantly higher than 25 C for a long time after the closure of the repository.
Rao, Linfeng; Tian, Guoxin; Xia, Yuanxian; Friese, Judah I.; Zanonato, PierLuigi; Di Bernardo, Plinio
Systems study of the feasibility of high-level nuclear waste fractionation for thermal stress control in a geologic repository: appendices
This study assesses the benefits and costs of fractionating the cesium and strontium (Cs/Sr) components in commercial high-level waste (HLW) to a separate waste stream for the purpose of reducing geologic-repository thermal stresses in the region of the HLW. The major conclusion is that the Cs/Sr fractionation concept offers the prospect of a substantial total system cost advantage for HLW disposal if reduced HLW package temperatures in a basalt repository are desired. However there is no cost advantage if currently designated maximum design temperatures are acceptable. Aging the HLW for 50 to 100 years can accomplish similar results at equivalent or lower costs. Volume II contains appendices for: (1) thermal analysis supplement; (2) fractionation process experimental results supplement; (3) cost analysis supplement; and (4) radiological risk analysis supplement.
McKee, R.W.; Elder, H.K.; McCallum, R.F.; Silviera, D.J.; Swanson, J.L.; Wiles, L.E.
Report to Congress on the potential use of lead in the waste packages for a geologic repository at Yucca Mountain, Nevada
In the Report of the Senate Committee on Appropriations accompanying the Energy and Water Appropriation Act for 1989, the Committee directed the Department of Energy (DOE) to evaluate the use of lead in the waste packages to be used in geologic repositories for spent nuclear fuel and high-level waste. The evaluation that was performed in response to this directive is presented in this report. This evaluation was based largely on a review of the technical literature on the behavior of lead, reports of work conducted in other countries, and work performed for the waste-management program being conducted by the DOE. The initial evaluation was limited to the potential use of lead in the packages to be used in the repository. Also, the focus of this report is post closure performance and not on retrievability and handling aspects of the waste package. 100 refs., 8 figs., 15 tabs.
Ambiguous queries: test collections need more sense
Although there are many papers examining ambiguity in Information Retrieval, this paper shows that there is a whole class of ambiguous word that past research has barely explored. It is shown that the class is more ambiguous than other word types and ... Keywords: ambiguous queries, diversity, test collections
Mark Sanderson
Predictive modeling for collections of accounts receivable
It is commonly agreed that accounts receivable (AR) can be a source of financial difficulty for firms when they are not efficiently managed and are underperforming. Experience across multiple industries shows that effective management of AR and overall ... Keywords: accounts receivable, invoice to cash, knowledge discovery, order to cash, payment collection, predictive modeling
Sai Zeng; Ioana Boier-Martin; Prem Melville; Conrad Murphy; Christian A. Lang
Natural Gas Data Collection and Estimation
Reports and Publications (EIA)
This presentation to the Oklahoma Independent Petroleum Association gives an overview of the EIA natural gas data collection system, Oklahoma natural gas statistics, recent changes in monthly natural gas production statistics, and the May 2010 short-term natural gas forecast. The presentation focuses on the EIA-914, the "Monthly Natural Gas Production Report," and recent changes to this survey's estimation methodology.
Information Center
A geometric approach to collective motion
We introduce the total s-energy of a multiagent system and bound its maximum asymptotic value. This gives us a new analytical device to study the convergence rate of bidirectional agreement dynamics. We use it to bound the convergence rate of ... Keywords: agreement dynamics, collective motion, total s-energy
Bernard Chazelle
Metal current collect protected by oxide film
Provided are low-cost, mechanically strong, highly electronically conductive current collects and associated structures for solid-state electrochemical devices, techniques for forming these structures, and devices incorporating the structures. The invention provides solid state electrochemical devices having as current interconnects a ferritic steel felt or screen coated with a protective oxide film.
Jacobson, Craig P. (Lafayette, CA); Visco, Steven J. (Berkeley, CA); DeJonghe, Lutgard C. (Lafayette, CA)
Modeling the World from Internet Photo Collections
There are billions of photographs on the Internet, comprising the largest and most diverse photo collection ever assembled. How can computer vision researchers exploit this imagery? This paper explores this question from the standpoint of 3D scene modeling ... Keywords: 3D navigation, 3D scene analysis, Internet imagery, Photo browsers, Structure from motion
Noah Snavely; Steven M. Seitz; Richard Szeliski
Laboratory Measurements of Collection Efficiencies for Accretion
Collection efficiencies for accretion were measured for six pairs of nearly unchanged drops. Cloud droplets of 11 and 17 ?m and collector drops between 100 and 400 ?m radius were used. The resulting efficiencies were in the 51�70% range and all ...
Harry T. Ochs III; K. V. Beard
Draft Supplemental Environmental Impact for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada
Options to Elements of the Proposed Action Options to Elements of the Proposed Action TABLE OF CONTENTS Section Page A. Options to Elements of the Proposed Action .....................................................................................A-1 A.1 Wastewater Treatment at the Repository Option.........................................................................A-1 A.1.1 Potential Benefits of the Premanufactured Wastewater Treatment Facility..........................A-2 A.1.2 Potential Environmental Impacts of the Premanufactured Wastewater Treatment Facility .................................................................................................................A-2 A.2 Reduced Transportation, Aging, and Disposal Canister Use Option...........................................A-2
Comments Regarding In-Drift Chemistry Related to Corrosion of Containment Barriers at the Candidate Spent Fuel and HLW Repository at Yucca Mountain, Nevada