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Office of Scientific and Technical Information
Fusion Rules and Conditional Statistics in Turbulent Advection
E-Print Network [OSTI]
Fusion rules in turbulence address the asymptotic properties of many-point correlation functions when some of the coordinates are very close to each other. Here we put to experimental test some non-trivial consequences of the fusion rules for scalar correlations in turbulence. To this aim we examine passive turbulent advection as well as convective turbulence. Adding one assumption to the fusion rules one obtains a prediction for universal conditional statistics of gradient fields. We examine the conditional average of the scalar dissipation field $\\left$ for $R$ in the inertial range, and find that it is linear in $T(\\B.r+\\B.R)-T(\\B.r)$ with a fully determined proportionality constant. The implications of these findings for the general scaling theory of scalar turbulence are discussed.
Emily S. C. Ching; Victor S. L'vov; Itamar Procaccia
Reflections on Fusion's History and Implications for Fusion's Future*
confinement configurations; to demonstrate performance capability at burning plasma conditions; and to develop of achieving the plasma conditions needed for a practical fusion power system. Fusion researchers have achieved confinement fusion (ICF) researchers have achieved great success as well. Two major facilities, the National
Progress on achieving the ICF conditions needed for high gain
SciTech Connect (OSTI)
Progress during the past two years has moved us much closer to demonstrating the scientific and technological requirements for high gain ICF in the laboratory. This progress has been made possible by operating at the third harmonic of 1..mu..m light which dramatically reduces concern about hot electrons and by advances in diagnostics such as 100 ps x-ray framing cameras which greatly increase the data available from each experiment. Making use of many of these new capabilities, major improvements in confinement conditions have been achieved for ICF implosions. In particular, in an optimized hohlraum on Nova, radiation driven implosions with convergence ratio in excess of 30 (volume compression /approximately/3 /times/ 10/sup 4/) have performed essentially as predicted by spherical implosion calculations. This paper presents these results as well as examples of advances in several other areas and discusses the implications for the future of ICF with lasers and heavy ion beam drivers. 8 refs., 10 figs.
Lindl, J.D.
Achieving competitive excellence in nuclear energy: The threat of proliferation; the challenge of inertial confinement fusion
Nuclear energy will have an expanding role in meeting the twenty-first-century challenges of population and economic growth, energy demand, and global warming. These great challenges are non-linearly coupled and incompletely understood. In the complex global system, achieving competitive excellence for nuclear energy is a multi-dimensional challenge. The growth of nuclear energy will be driven by its margin of economic advantage, as well as by threats to energy security and by growing evidence of global warming. At the same time, the deployment of nuclear energy will be inhibited by concerns about nuclear weapons proliferation, nuclear waste and nuclear reactor safety. These drivers and inhibitors are coupled: for example, in the foreseeable future, proliferation in the Middle East may undermine energy security and increase demand for nuclear energy. The Department of Energy`s nuclear weapons laboratories are addressing many of these challenges, including nuclear weapons builddown and nonproliferation, nuclear waste storage and burnup, reactor safety and fuel enrichment, global warming, and the long-range development of fusion energy. Today I will focus on two major program areas at the Lawrence Livermore National Laboratory (LLNL): the proliferation of nuclear weapons and the development of inertial confinement fusion (ICF) energy.
Nuckolls, J.H.
Main achievements in research on Plasma Physics and Controlled Fusion in 2010 in Russia
The key results presented at the XXXVIII International Zvenigorod Conference on Plasma Physics and Controlled Fusion, held February 14-18, 2011 are reviewed, and the main research directions are analyzed.
Grishina, I. A.; Ivanov, V. A.; Kovrizhnykh, L. M. [Russian Academy of Sciences, Prokhorov General Physics Institute (Russian Federation)
Scientific Breakeven for Fusion Energy For the past 40 years, the IFE fusion research community has adopted: achieving a fusion gain of 1 as
scientific breakeven." E. Moses, Status of the NIF Project, Lawrence Livermore National Laboratory Report: "Laser fusion experiments, facilities, and diagnostics at Lawrence Livermore National Laboratory", by H of 1 defines scientific breakeven. (This is therefore a Livermore definition!) The recent National
Comment on Li pellet conditioning in tokamak fusion test reactor R. V. Budny
Comment on Li pellet conditioning in tokamak fusion test reactor R. V. Budny Princeton Plasma; published online 9 September 2011) Li pellet conditioning in TFTR results in a reduction of the edge technique for introducing Li is via pellet injection. This was pioneered in ALCATOR- CMOD where it was first
Budny, Robert
Integrable Boundary Conditions and W-Extended Fusion in the Logarithmic Minimal Models LM(1,p)
We consider the logarithmic minimal models LM(1,p) as `rational' logarithmic conformal field theories with extended W symmetry. To make contact with the extended picture starting from the lattice, we identify 4p-2 boundary conditions as specific limits of integrable boundary conditions of the underlying Yang-Baxter integrable lattice models. Specifically, we identify 2p integrable boundary conditions to match the 2p known irreducible W-representations. These 2p extended representations naturally decompose into infinite sums of the irreducible Virasoro representations (r,s). A further 2p-2 reducible yet indecomposable W-representations of rank 2 are generated by fusion and these decompose as infinite sums of indecomposable rank-2 Virasoro representations. The fusion rules in the extended picture are deduced from the known fusion rules for the Virasoro representations of LM(1,p) and are found to be in agreement with previous works. The closure of the fusion algebra on a finite number of representations in the extended picture is remarkable confirmation of the consistency of the lattice approach.
Paul A. Pearce; Jorgen Rasmussen; Philippe Ruelle
Integrable Boundaries, Conformal Boundary Conditions and A-D-E Fusion Rules
The $sl(2)$ minimal theories are labelled by a Lie algebra pair $(A,G)$ where $G$ is of $A$-$D$-$E$ type. For these theories on a cylinder we conjecture a complete set of conformal boundary conditions labelled by the nodes of the tensor product graph $A\\otimes G$. The cylinder partition functions are given by fusion rules arising from the graph fusion algebra of $A\\otimes G$. We further conjecture that, for each conformal boundary condition, an integrable boundary condition exists as a solution of the boundary Yang-Baxter equation for the associated lattice model. The theory is illustrated using the $(A_4,D_4)$ or 3-state Potts model.
Roger E. Behrend; Paul A. Pearce; Jean-Bernard Zuber
Hydrogen Hydrogen FusionFusionFusionFusionFusionFusion
100.000 years LNGS Laboratori Nazionali del Gran Sasso Borexino THE THERMONUCLEAR FUSION REACTIONHydrogen Hydrogen Fusion Deuterium FusionFusionFusionFusionFusionFusion THE SUN AS BOREXINO SEES
Heiz, Ulrich
Nonperturbative measurement of the local magnetic field using pulsed polarimetry for fusion reactor conditions (invited)
A novel diagnostic technique for the remote and nonperturbative sensing of the local magnetic field in reactor relevant plasmas is presented. Pulsed polarimetry [Patent No. 12/150,169 (pending)] combines optical scattering with the Faraday effect. The polarimetric light detection and ranging (LIDAR)-like diagnostic has the potential to be a local B{sub pol} diagnostic on ITER and can achieve spatial resolutions of millimeters on high energy density (HED) plasmas using existing lasers. The pulsed polarimetry method is based on nonlocal measurements and subtle effects are introduced that are not present in either cw polarimetry or Thomson scattering LIDAR. Important features include the capability of simultaneously measuring local T{sub e}, n{sub e}, and B{sub ||} along the line of sight, a resiliency to refractive effects, a short measurement duration providing near instantaneous data in time, and location for real-time feedback and control of magnetohydrodynamic (MHD) instabilities and the realization of a widely applicable internal magnetic field diagnostic for the magnetic fusion energy program. The technique improves for higher n{sub e}B{sub ||} product and higher n{sub e} and is well suited for diagnosing the transient plasmas in the HED program. Larger devices such as ITER and DEMO are also better suited to the technique, allowing longer pulse lengths and thereby relaxing key technology constraints making pulsed polarimetry a valuable asset for next step devices. The pulsed polarimetry technique is clarified by way of illustration on the ITER tokamak and plasmas within the magnetized target fusion program within present technological means.
Smith, Roger J. [University of Washington, Seattle, Washington 98195-2250 (United States)
Neutronic and thermal calculation of blanket for high power operating condition of fusion reactor
Internal (breeding region) structures of ceramic breeder blanket to accommodate high power operating conditions such as a DEMO reactor have been investigated. The conditions considered here are the maximum neutron wall load of 2.8 MW/m{sup 2} at outboard midplane corresponding to a fusion power of 3.0 GW and the coolant temperature of 200{degrees}C. Structure of a blanket is based on the layered pebble bed concept, which has been proposed by Japan since the ITER CDA. Lithium oxide with 50% enriched {sup 6}Li is used in a shape of small spherical pebbles which are filled in a 316SS can avoid its compatibility issue with Be. Beryllium around the breeder can is filled also in a shape of spherical pebbles which works not only as a neutron multiplier but also as a thermal resistant layer to maintain breeder temperature for effective in-situ tritium recovery. Diameters and packing fractions of both pebbles are {<=} 1 mm and 65%, respectively. A layer of block Be between cooling panels is introduced as a neutron multiplier (not as the thermal resistant layer) to enhance tritium breeding performance. Inlet temperature of water coolant is 200{degrees}C to meet the high temperature conditioning requirement to the first wall which is one of walls of the blanket vessel. Neutronics calculations have been carried out by one-dimensional transport code, and thermal calculations have also been carried out by one-dimensional slab code.
Sagawa, H.; Shimakawa, S.; Kuroda, T. [Oarai Research Establishement of JAERI, Ibaraki (Japan)] [and others
Multisensor Fusion of Ground-based and Airborne Remote Sensing Data for Crop Condition Assessment
provide applicators with guidance equipment configurations that can result in herbicide savings and optimized applications in other crops. The main focus of this research was to apply sensor fusion technology to ground-based and airborne imagery data...
Zhang, Huihui
Ceramics for fusion applications
Ceramics are required for a variety of uses in both near-term fusion devices and in commercial powerplants. These materials must retain adequate structural and electrical properties under conditions of neutron, particle, and ionizing irradiation; thermal and applied stresses; and physical and chemical sputtering. Ceramics such as Al/sub 2/O/sub 3/, MgAl/sub 2/O/sub 4/, BeO, Si/sub 3/N/sub 4/ and SiC are currently under study for fusion applications, and results to date show widely-varying response to the fusion environment. Materials can be identified today which will meet initial operating requirements, but improvements in physical properties are needed to achieve satisfactory lifetimes for critical applications.
Clinard, F.W. Jr.
VERIFICATION BASED ECG BIOMETRICS WITH CARDIAC IRREGULAR CONDITIONS USING HEARTBEAT LEVEL propose an ECG based robust human verification system for both healthy and cardiac irregular conditions% relatively on the PTB database. Index Terms-- ECG biometrics, beat normalization, outlier re- moval
Li, Xin
Extensive remote handling and conservative plasma conditions to enable fusion nuclear science R&D using a component testing facility
nuclear science R&D using a component testing facility Y.K.M. Peng 1), T.W. Burgess 1), A.J. Carroll 1), C. This use aims to test components in an integrated fusion nuclear environment, for the first email@example.com Abstract. The use of a fusion component testing facility to study and establish, during the ITER era
Princeton Plasma Physics Laboratory
Effects of Fusion Zone Size and Failure Mode on Peak Load and Energy Absorption of Advanced High Strength Steel Spot Welds under Lap Shear Loading Conditions
This paper examines the effects of fusion zone size on failure modes, static strength and energy absorption of resistance spot welds (RSW) of advanced high strength steels (AHSS) under lap shear loading condition. DP800 and TRIP800 spot welds are considered. The main failure modes for spot welds are nugget pullout and interfacial fracture. Partial interfacial fracture is also observed. Static weld strength tests using lap shear samples were performed on the joint populations with various fusion zone sizes. The resulted peak load and energy absorption levels associated with each failure mode were studied for all the weld populations using statistical data analysis tools. The results in this study show that AHSS spot welds with conventionally required fusion zone size of can not produce nugget pullout mode for both the DP800 and TRIP800 welds under lap shear loading. Moreover, failure mode has strong influence on weld peak load and energy absorption for all the DP800 welds and the TRIP800 small welds: welds failed in pullout mode have statistically higher strength and energy absorption than those failed in interfacial fracture mode. For TRIP800 welds above the critical fusion zone level, the influence of weld failure modes on peak load and energy absorption diminishes. Scatter plots of peak load and energy absorption versus weld fusion zone size were then constructed, and the results indicate that fusion zone size is the most critical factor in weld quality in terms of peak load and energy absorption for both DP800 and TRIP800 spot welds.
Sun, Xin; Stephens, Elizabeth V.; Khaleel, Mohammad A.
Electron Screening Effect on Stellar Thermonuclear Fusion
thermonuclear fusions and show that these scenarios do not apply to stellar conditions. c ? 2013 WILEY
K. -h. Spatschek; M. Bonitz; T. Klinger; U. Ebert; C. Franck; A. V. Keudell; D. Naujoks; M. Dewitz; A. Y. Potekhin; G. Chabrier
55Fe effect on enhancing ferritic steel He/dpa ratio in fission reactor irradiations to simulate fusion conditions
How to increase the ferritic steel He(appm)/dpa ratio in a fission reactor neutron spectrum is an important question for fusion reactor material testing. An early experiment showed that the accelerated He(appm)/dpa ratio of about 2.3 was achieved for 96% enriched 54Fe in iron with 458.2 effective full power days (EFPD) irradiation in the High Flux Isotope Reactor (HFIR), ORNL. Greenwood suggested that the transmutation produced 55Fe has a thermal neutron helium production cross section which may have an effect on this result. In the current work, the ferritic steel He(appm)/dpa ratio is studied in the neutron spectrum of HFIR with 55Fe thermal neutron helium production taken into account. The available ENDF-b format 55Fe incident neutron cross section file from TENDL, Netherlands, is first input into the calculation model. A benchmark calculation for the same sample as used in the aforementioned experiment was used to adjust and evaluate the TENDL 55Fe (n, a) cross section values. The analysis shows a decrease of a factor of 6700 for the TENDL 55Fe (n, a) cross section in the intermediate and low energy regions is required in order to fit the experimental results. The best fit to the cross section value at thermal neutron energy is about 27 mb. With the adjusted 55Fe (n, a) cross sections, calculation show that the 54Fe and 55Fe isotopes can be enriched by the isotopic tailoring technique in a ferritic steel sample irradiated in HFIR to significantly enhance the helium production rate. The results show that a 70% enriched 54Fe and 30% enriched 55Fe ferritic steel sample would produce a He(appm)/dpa ratio of about 13 initially in the HFIR peripheral target position (PTP). After one year irradiation, the ratio decreases to about 10. This new calculation can be used to guide future isotopic tailoring experiments designed to increase the He(appm)/dpa ratio in fission reactors. A benchmark experiment is suggested to be performed to evaluate the 55Fe (n, a) cross section at thermal energy.
Liu, Haibo; Abdou, Mohamed A.; Greenwood, Lawrence R.
After many years of fusion research, the conditions needed for a DT fusion reactor have been approached on the Tokamak Fusion Test Reactor (TFTR). For the first time the
, is observed to increase in DT, relative to D plasmas, by 20% and the n i (0) T i (0) t E product by 55 supershot and limiterHmode discharges. Extensive lithium pellet injection increased the confinement time. Demonstrating the production of »10 MW of fusion power. In this paper, a brief description will be given
Hammett, Greg
Lower Hybrid antennas for nuclear fusion experiments
The nuclear fusion research goal is to demonstrate the feasibility of fusion power for peaceful purposes. In order to achieve the conditions similar to those expected in an electricity-generating fusion power plant, plasmas with a temperature of several hundreds of millions of degrees must be generated and sustained for long periods. For this purpose, RF antennas delivering multi-megawatts of power to magnetized confined plasma are commonly used in experimental tokamaks. In the gigahertz range of frequencies, high power phased arrays known as "Lower Hybrid" (LH) antennas are used to extend the plasma duration. This paper reviews some of the technological aspects of the LH antennas used in the Tore Supra tokamak and presents the current design of a proposed 20 MW LH system for the international experiment ITER.
Hillairet, Julien; Bae, Young-Soon; Bai, X; Balorin, C; Baranov, Y; Basiuk, V; B�coulet, A; Belo, J; Berger-By, G; Br�mond, S; Castaldo, C; Ceccuzzi, S; Cesario, R; Corbel, E; Courtois, X; Decker, J; Delmas, E; Delpech, L; Ding, X; Douai, D; Ekedahl, A; Goletto, C; Goniche, M; Guilhem, D; Hertout, P; Imbeaux, F; Litaudon, X; Magne, R; Mailloux, J; Mazon, D; Mirizzi, F; Mollard, P; Moreau, P; Oosako, T; Petrzilka, V; Peysson, Y; Poli, S; Preynas, M; Prou, M; Saint-Laurent, F; Samaille, F; Saoutic, B
PLASMA-PHYSICS-21 Heavy ion driven reactor-size double shell inertial fusion targets*
Inertial Confinement Fusion (ICF) is considered as an alternative to Magnetic Confinement Fusion to achieve controlled thermonuclear fusion. The main goal is to exploit the energy released from thermonuclear fusion reactions
M. C. Serna Moreno; N. A. Tahir; J. J. L�pez Cela; A. R. Piriz; D. H. H. Hoffmann
Research on fusion neutron sources
The use of fusion devices as powerful neutron sources has been discussed for decades. Whereas the successful route to a commercial fusion power reactor demands steady state stable operation combined with the high efficiency required to make electricity production economic, the alternative approach to advancing the use of fusion is free of many of complications connected with the requirements for economic power generation and uses the already achieved knowledge of Fusion physics and developed Fusion technologies. 'Fusion for Neutrons' (F4N), has now been re-visited, inspired by recent progress achieved on comparably compact fusion devices, based on the Spherical Tokamak (ST) concept. Freed from the requirement to produce much more electricity than used to drive it, a fusion neutron source could be efficiently used for many commercial applications, and also to support the goal of producing energy by nuclear power. The possibility to use a small or medium size ST as a powerful or intense steady-state fusion neutron source (FNS) is discussed in this paper in comparison with the use of traditional high aspect ratio tokamaks. An overview of various conceptual designs of compact fusion neutron sources based on the ST concept is given and they are compared with a recently proposed Super Compact Fusion Neutron Source (SCFNS), with major radius as low as 0.5 metres but still able to produce several MW of neutrons in a steady-state regime.
Gryaznevich, M. P. [Tokamak Solutions UK, Culham Science Centre, Abingdon, OXON, OX133DB (United Kingdom)
Multinational achievement: PPPL collaborates on record fusion...
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
at the edge of the gas near the interior walls of the tokamak. Controlling these fast-growing instabilities, called "edge localized modes" (ELMs), produced a record life...
Thermonuclear Fusion Research Progress and the Way to the Reactor
The paper reviews the progress of fusion research and its prospects for electricity generation. It starts with a reminder of the principles of thermonuclear fusion and a brief discussion of its potential role in the future of the world energy production. The reactions allowing energy production by fusion of nuclei in stars and on earth and the conditions required to sustain them are reviewed. At the high temperatures required for fusion (hundred millions kelvins), matter is completely ionized and has reached what is called its 4th state: the plasma state. The possible means to achieve these extreme temperatures is discussed. The remainder of the paper focuses on the most promising of these approaches, magnetic confinement. The operating principles of the presently most efficient machine of this type -- the tokamak -- is described in some detail. On the road to producing energy with fusion, a number of obstacles have to be overcome. The plasma, a fluid that reacts to electromagnetic forces and carries currents and charges, is a complex medium. Fusion plasma is strongly heated and is therefore a good example of a system far from equilibrium. A wide variety of instabilities can grow in this system and lead to self-organized structures and spontaneous cycles. Turbulence is generated that degrades the confinement and hinders easy achievement of long lasting hot plasmas. Physicists have learned how to quench turbulence, thereby creating sort of insulating bottles inside the plasma itself to circumvent this problem. The recent history of fusion performance is outlined and the prospect of achieving power generation by fusion in a near future is discussed in the light of the development of the 'International Tokamak Experimental Reactor' project ITER.
Koch, Raymond [Laboratory for Plasma Physics, Royal Military Academy, Association EURATOM - Belgian State, 1000 Brussels (Belgium)
Realizing Technologies for Magnetized Target Fusion
Researchers are making progress with a range of magneto-inertial fusion (MIF) concepts. All of these approaches use the addition of a magnetic field to a target plasma, and then compress the plasma to fusion conditions. The beauty of MIF is that driver power requirements are reduced, compared to classical inertial fusion approaches, and simultaneously the compression timescales can be longer, and required implosion velocities are slower. The presence of a sufficiently large Bfield expands the accessibility to ignition, even at lower values of the density-radius product, and can confine fusion alphas. A key constraint is that the lifetime of the MIF target plasma has to be matched to the timescale of the driver technology (whether liners, heavy ions, or lasers). To achieve sufficient burn-up fraction, scaling suggests that larger yields are more effective. To handle the larger yields (GJ level), thick liquid wall chambers are certainly desired (no plasma/neutron damage materials problem) and probably required. With larger yields, slower repetition rates ({approx}0.1-1 Hz) for this intrinsically pulsed approach to fusion are possible, which means that chamber clearing between pulses can be accomplished on timescales that are compatible with simple clearing techniques (flowing liquid droplet curtains). However, demonstration of the required reliable delivery of hundreds of MJ of energy, for millions of pulses per year, is an ongoing pulsed power technical challenge.
Wurden, Glen A. [Los Alamos National Laboratory
Fusion Residues
We discuss when and how the Verlinde dimensions of a rational conformal field theory can be expressed as correlation functions in a topological LG theory. It is seen that a necessary condition is that the RCFT fusion rules must exhibit an extra symmetry. We consider two particular perturbations of the Grassmannian superpotentials. The topological LG residues in one perturbation, introduced by Gepner, are shown to be a twisted version of the $SU(N)_k$ Verlinde dimensions. The residues in the other perturbation are the twisted Verlinde dimensions of another RCFT; these topological LG correlation functions are conjectured to be the correlation functions of the corresponding Grassmannian topological sigma model with a coupling in the action to instanton number.
Kenneth Intriligator
Fusion power production in TFTR
Up to 9.3 MW of fusion power has been produced from deuterium-tritium (DT) fusion reactions in the Tokamak Fusion Test Reactor (TFTR). The total fusion yield from a single plasma pulse has reached 6.5 MJ. The experiments in TFTR with deuterium-tritium plasmas fueled and heated by neutral beam injection span wide ranges in plasma and operating conditions. Through the use of lithium pellet conditioning to control the edge recycling, the plasma confinement in TFTR has been improved to the point where the stability of the plasma to pressure driven modes is limiting the fusion power for plasma currents up to 2.5 MA. The central energy and fusion power densities in these plasmas are comparable to those expected in a thermalized DT reactor, such as ITER.
Bell, M.G.; Budny, R.V. [Princeton Univ., NJ (United States). Plasma Physics Lab.; Barnes, C.W. [Los Alamos National Lab., NM (United States)] [and others
Compatibility of Physics and Engineering in Magnetic Fusion White Paper on Magnetic Fusion Priorities
Compatibility of Physics and Engineering in Magnetic Fusion White Paper on Magnetic Fusion.edu (Dated: July 14, 2012) The compatibility of the requirements of physics and engineering is the fundamental issue in the achievement of useful magnetic fusion energy. Issues that must be addressed include
The National Ignition Facility and the Path to Fusion Energy
The National Ignition Facility (NIF) is operational and conducting experiments at the Lawrence Livermore National Laboratory (LLNL). The NIF is the world's largest and most energetic laser experimental facility with 192 beams capable of delivering 1.8 megajoules of 500-terawatt ultraviolet laser energy, over 60 times more energy than any previous laser system. The NIF can create temperatures of more than 100 million degrees and pressures more than 100 billion times Earth's atmospheric pressure. These conditions, similar to those at the center of the sun, have never been created in the laboratory and will allow scientists to probe the physics of planetary interiors, supernovae, black holes, and other phenomena. The NIF's laser beams are designed to compress fusion targets to the conditions required for thermonuclear burn, liberating more energy than is required to initiate the fusion reactions. Experiments on the NIF are focusing on demonstrating fusion ignition and burn via inertial confinement fusion (ICF). The ignition program is conducted via the National Ignition Campaign (NIC) - a partnership among LLNL, Los Alamos National Laboratory, Sandia National Laboratories, University of Rochester Laboratory for Laser Energetics, and General Atomics. The NIC program has also established collaborations with the Atomic Weapons Establishment in the United Kingdom, Commissariat a Energie Atomique in France, Massachusetts Institute of Technology, Lawrence Berkeley National Laboratory, and many others. Ignition experiments have begun that form the basis of the overall NIF strategy for achieving ignition. Accomplishing this goal will demonstrate the feasibility of fusion as a source of limitless, clean energy for the future. This paper discusses the current status of the NIC, the experimental steps needed toward achieving ignition and the steps required to demonstrate and enable the delivery of fusion energy as a viable carbon-free energy source.
Moses, E
Achievements, Awards
AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc Documentation RUCProductstwrmrAre the Effects ofAboutTestAccountingTiO (110):Achievements,
(Fusion energy research)
This report discusses the following topics: principal parameters achieved in experimental devices (FY88); tokamak fusion test reactor; Princeton beta Experiment-Modification; S-1 Spheromak; current drive experiment; x-ray laser studies; spacecraft glow experiment; plasma deposition and etching of thin films; theoretical plasma; tokamak modeling; compact ignition tokamak; international thermonuclear experimental reactor; Engineering Department; Project Planning and Safety Office; quality assurance and reliability; and technology transfer.
Phillips, C.A. (ed.)
Magnetized Target Fusion Collaboration. Final report
Nuclear fusion has the potential to satisfy the prodigious power that the world will demand in the future, but it has yet to be harnessed as a practical energy source. The entry of fusion as a viable, competitive source of power has been stymied by the challenge of finding an economical way to provide for the confinement and heating of the plasma fuel. It is the contention here that a simpler path to fusion can be achieved by creating fusion conditions in a different regime at small scale (~ a few cm). One such program now under study, referred to as Magnetized Target Fusion (MTF), is directed at obtaining fusion in this high energy density regime by rapidly compressing a compact toroidal plasmoid commonly referred to as a Field Reversed Configuration (FRC). To make fusion practical at this smaller scale, an efficient method for compressing the FRC to fusion gain conditions is required. In one variant of MTF a conducting metal shell is imploded electrically. This radially compresses and heats the FRC plasmoid to fusion conditions. The closed magnetic field in the target plasmoid suppresses the thermal transport to the confining shell, thus lowering the imploding power needed to compress the target. The undertaking described in this report was to provide a suitable target FRC, as well as a simple and robust method for inserting and stopping the FRC within the imploding liner. The FRC must also survive during the time it takes for the metal liner to compress the FRC target. The initial work at the UW was focused on developing adequate preionization and flux trapping that were found to be essential in past experiments for obtaining the density, flux and most critically, FRC lifetime required for MTF. The timescale for testing and development of such a source can be rapidly accelerated by taking advantage of a new facility funded by the Department of Energy. At this facility, two inductive plasma accelerators (IPA) were constructed and tested. Recent experiments with these IPAs have demonstrated the ability to rapidly form, accelerate and merge two hypervelocity FRCs into a compression chamber. The resultant FRC that was formed was hot (T{sub ion} ~ 400 eV), stationary, and stable with a configuration lifetime several times that necessary for the MTF liner experiments. The accelerator length was less than 1 meter, and the time from the initiation of formation to the establishment of the final equilibrium was less than 10 microseconds. With some modification, each accelerator can be made capable of producing FRCs suitable for the production of the target plasma for the MTF liner experiment. Based on the initial FRC merging/compression results, the design and methodology for an experimental realization of the target plasma for the MTF liner experiment can now be defined. The construction and testing of the key components for the formation of the target plasma at the Air Force Research Laboratory (AFRL) will be performed on the IPA experiment, now at MSNW. A high density FRC plasmoid will be formed and accelerated out of each IPA into a merging/compression chamber similar to the imploding liner at AFRL. The properties of the resultant FRC plasma (size, temperature, density, flux, lifetime) will be obtained. The process will be optimized, and a final design for implementation at AFRL will be carried out. When implemented at AFRL it is anticipated that the colliding/merging FRCs will then be compressed by the liner. In this manner it is hoped that ultimately a plasma with ion temperatures reaching the 10 keV range and fusion gain near unity can be obtained.
John Slough
Fusion energy
ScienceCinema (OSTI)
Larry Baylor explains how the US ITER team is working to prevent solar flare-like events at a fusion energy reactor that will be like a small sun on earth
Baylor, Larry
Information integration for data fusion
Data fusion has been identified by the Department of Defense as a critical technology for the U.S. defense industry. Data fusion requires combining expertise in two areas - sensors and information integration. Although data fusion is a rapidly growing area, there is little synergy and use of common, reusable, and/or tailorable objects and models, especially across different disciplines. The Laboratory-Directed Research and Development project had two purposes: to see if a natural language-based information modeling methodology could be used for data fusion problems, and if so, to determine whether this methodology would help identify commonalities across areas and achieve greater synergy. The project confirmed both of the initial hypotheses: that the natural language-based information modeling methodology could be used effectively in data fusion areas and that commonalities could be found that would allow synergy across various data fusion areas. The project found five common objects that are the basis for all of the data fusion areas examined: targets, behaviors, environments, signatures, and sensors. Many of the objects and the specific facts related to these objects were common across several areas and could easily be reused. In some cases, even the terminology remained the same. In other cases, different areas had their own terminology, but the concepts were the same. This commonality is important with the growing use of multisensor data fusion. Data fusion is much more difficult if each type of sensor uses its own objects and models rather than building on a common set. This report introduces data fusion, discusses how the synergy generated by this LDRD would have benefited an earlier successful project and contains a summary information model from that project, describes a preliminary management information model, and explains how information integration can facilitate cross-treaty synergy for various arms control treaties.
Bray, O.H.
Safety of magnetic fusion facilities: Requirements
This Standard identifies safety requirements for magnetic fusion facilities. Safety functions are used to define outcomes that must be achieved to ensure that exposures to radiation, hazardous materials, or other hazards are maintained within acceptable limits. Requirements applicable to magnetic fusion facilities have been derived from Federal law, policy, and other documents. In addition to specific safety requirements, broad direction is given in the form of safety principles that are to be implemented and within which safety can be achieved.
Measuring time of flight of fusion products in an inertial electrostatic confinement fusion device for spatial profiling of fusion reactions
A new diagnostic has been developed that uses the time of flight (TOF) of the products from a nuclear fusion reaction to determine the location where the fusion reaction occurred. The TOF diagnostic uses charged particle detectors on opposing sides of the inertial electrostatic confinement (IEC) device that are coupled to high resolution timing electronics to measure the spatial profile of fusion reactions occurring between the two charged particle detectors. This diagnostic was constructed and tested by the University of Wisconsin-Madison Inertial Electrostatic Confinement Fusion Group in the IEC device, HOMER, which accelerates deuterium ions to fusion relevant energies in a high voltage ({approx}100 kV), spherically symmetric, electrostatic potential well [J. F. Santarius, G. L. Kulcinski, R. P. Ashley, D. R. Boris, B. B. Cipiti, S. K. Murali, G. R. Piefer, R. F. Radel, T. E. Radel, and A. L. Wehmeyer, Fusion Sci. Technol. 47, 1238 (2005)]. The TOF diagnostic detects the products of D(d,p)T reactions and determines where along a chord through the device the fusion event occurred. The diagnostic is also capable of using charged particle spectroscopy to determine the Doppler shift imparted to the fusion products by the center of mass energy of the fusion reactants. The TOF diagnostic is thus able to collect spatial profiles of the fusion reaction density along a chord through the device, coupled with the center of mass energy of the reactions occurring at each location. This provides levels of diagnostic detail never before achieved on an IEC device.
Donovan, D. C. [Sandia National Laboratories, 7011 East Avenue, Livermore, California 94550 (United States); Boris, D. R. [Naval Research Laboratory, 4555 Overlook Avenue, South West, Washington, DC 20375 (United States); Kulcinski, G. L.; Santarius, J. F. [Fusion Technology Institute, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, Wisconsin 53706 (United States); Piefer, G. R. [Phoenix Nuclear Labs, 2555 Industrial Drive, Madison, Wisconsin 53713 (United States)
Fusion materials irradiations at MaRIE's fission fusion facility
Los Alamos National Laboratory's proposed signature facility, MaRIE, will provide scientists and engineers with new capabilities for modeling, synthesizing, examining, and testing materials of the future that will enhance the USA's energy security and national security. In the area of fusion power, the development of new structural alloys with better tolerance to the harsh radiation environments expected in fusion reactors will lead to improved safety and lower operating costs. The Fission and Fusion Materials Facility (F{sup 3}), one of three pillars of the proposed MaRIE facility, will offer researchers unprecedented access to a neutron radiation environment so that the effects of radiation damage on materials can be measured in-situ, during irradiation. The calculated radiation damage conditions within the F{sup 3} match, in many respects, that of a fusion reactor first wall, making it well suited for testing fusion materials. Here we report in particular on two important characteristics of the radiation environment with relevancy to radiation damage: the primary knock-on atom spectrum and the impact of the pulse structure of the proton beam on temporal characteristics of the atomic displacement rate. With respect to both of these, analyses show the F{sup 3} has conditions that are consistent with those of a steady-state fusion reactor first wall.
Pitcher, Eric J [Los Alamos National Laboratory
Introduction Minimal Fusion Systems
Introduction Minimal Fusion Systems Maximal Parabolics Results Minimal Fusion Systems Ellen Henke University of Birmingham Ellen Henke Minimal Fusion Systems #12;Introduction Minimal Fusion Systems Maximal Parabolics Results Contents 1 Introduction 2 Minimal Fusion Systems 3 Maximal Parabolics 4 Results Ellen
Thévenaz, Jacques
E-Print Network 3.0 - achievable plutonium decontamination Sample...
a problem The Mediterranean Antinuclear Watch (MANW) is a non - Summary: to the greenhouse effect. New Generation reactors to achieve the reuse of spent fuel. Fusion...
Socio-economic Aspects of Fusion
Fusion power systems, if developed and deployed, would have many attractive features including power production not dependant on weather or solar conditions, flexible siting, and minimal carbon dioxide production. In this paper, we quantify the benefit of these features. In addition, fusion deployment scenarios are developed for the last half of this century and these scenarios are analyzed for resource requirements and waste production.
J.A. Schmidt
Fusion Power Associates Fusion Energy Sciences Program
experiments Further work on inertial fusion energy technology Take advantage of opportunities in HEDP on several smaller experiments Further work on inertial fusion energy technology · Focus IFE first wall
Role of Fusion Energy in a Sustainable Global Energy Strategy
Fusion can play an important role in sustainable global energy because it has an available and unlimited fuel supply and location not restricted by climate or geography. Further, it emits no greenhouse gases. It has no potential for large energy releases in an accident, and no need for more than about 100 years retention for radioactive waste disposal. Substantial progress in the realization of fusion energy has been made during the past 20 years of research. It is now possible to produce significant amounts of energy from controlled deuterium and tritium (DT) reactions in the laboratory. This has led to a growing confidence in our ability to produce burning plasmas with significant energy gain in the next generation of fusion experiments. As success in fusion facilities has underpinned the scientific feasibility of fusion, the high cost of next-step fusion facilities has led to a shift in the focus of international fusion research towards a lower cost development path and an attractive end product. The increasing data base from fusion research allows conceptual fusion power plant studies, of both magnetic and inertial confinement approaches to fusion, to translate commercial requirements into the design features that must be met if fusion is to play a role in the world's energy mix; and identify key R and D items; and benchmark progress in fusion energy development. This paper addresses the question, ''Is mankind closer or farther away from controlled fusion than a few decades ago?'' We review the tremendous scientific progress during the last 10 years. We use the detailed engineering design activities of burning plasma experiments as well as conceptual fusion power plant studies to describe our visions of attractive fusion power plants. We use these studies to compare technical requirements of an attractive fusion system with present achievements and to identify remaining technical challenges for fusion. We discuss scenarios for fusion energy deployment in the energy market.
Sheffield, J.
Production and measurement of engineered surfaces for inertial confinement fusion research
Inertial Confinement Fusion uses the optical energy from a very high power laser to implode spherical capsules that contain a fuel mixture of deuterium and tritium. The capsules are made of either Beryllium, plastic, or glass and range from 0.1 mm to 2 mm in diameter. As a capsule implodes, thereby compressing the fuel to reach nuclear fusion conditions, it achieves temperatures of millions of degrees Centigrade and very high pressures. In this state, the capsule materials act like fluids and often a low density fluidic material will push on a higher density material which can be a very unstable condition depending upon the smoothness of the interface between the two materials. This unstable condition is called a hydrodynamic instabillity which results in the mixing of the two materials. If the mixing occurs between the fuel and a non-fuel material, it can stop the fusion reaction just like adding significant amounts of water to gasoline can stop the operation of an automobile. Another region in the capsule where surface roughness can cause capsule performance degradation is at a joint. For instance, many capsules are made of hemispheres that are joined together. If the joint surfaces are too rough, then there will an effective reduction in density at the joint. This density reduction can cause a non-uniform implosion which will reduce the fusion energy coming out of the capsule.
Day, Robert D [Los Alamos National Laboratory; Hatch, Douglas J [Los Alamos National Laboratory; Rivera, Gerald [Los Alamos National Laboratory
Final report on the Magnetized Target Fusion Collaboration
Nuclear fusion has the potential to satisfy the prodigious power that the world will demand in the future, but it has yet to be harnessed as a practical energy source. The entry of fusion as a viable, competitive source of power has been stymied by the challenge of finding an economical way to provide for the confinement and heating of the plasma fuel. It is the contention here that a simpler path to fusion can be achieved by creating fusion conditions in a different regime at small scale (~ a few cm). One such program now under study, referred to as Magnetized Target Fusion (MTF), is directed at obtaining fusion in this high energy density regime by rapidly compressing a compact toroidal plasmoid commonly referred to as a Field Reversed Configuration (FRC). To make fusion practical at this smaller scale, an efficient method for compressing the FRC to fusion gain conditions is required. In one variant of MTF a conducting metal shell is imploded electrically. This radially compresses and heats the FRC plasmoid to fusion conditions. The closed magnetic field in the target plasmoid suppresses the thermal transport to the confining shell, thus lowering the imploding power needed to compress the target. The undertaking to be described in this proposal is to provide a suitable target FRC, as well as a simple and robust method for inserting and stopping the FRC within the imploding liner. The timescale for testing and development can be rapidly accelerated by taking advantage of a new facility funded by the Department of Energy. At this facility, two inductive plasma accelerators (IPA) were constructed and tested. Recent experiments with these IPAs have demonstrated the ability to rapidly form, accelerate and merge two hypervelocity FRCs into a compression chamber. The resultant FRC that was formed was hot (T&ion ~ 400 eV), stationary, and stable with a configuration lifetime several times that necessary for the MTF liner experiments. The accelerator length was less than 1 meter, and the time from the initiation of formation to the establishment of the final equilibrium was less than 10 microseconds. With some modification, each accelerator was made capable of producing FRCs suitable for the production of the target plasma for the MTF liner experiment. Based on the initial FRC merging/compression results, the design and methodology for an experimental realization of the target plasma for the MTF liner experiment can now be defined. A high density FRC plasmoid is to be formed and accelerated out of each IPA into a merging/compression chamber similar to the imploding liner at AFRL. The properties of the resultant FRC plasma (size, temperature, density, flux, lifetime) are obtained in the reevant regime of interest. The process still needs to be optimized, and a final design for implementation at AFRL must now be carried out. When implemented at AFRL it is anticipated that the colliding/merging FRCs will then be compressed by the liner. In this manner it is hoped that ultimately a plasma with ion temperatures reaching the 10 keV range and fusion gain near unity can be obtained.
INL Fusion Safety Program - Staff
Brad Merrill Fusion Safety Program Group Leader Group Leader for the Fusion Safety Program. Technical lead for computer code development for fusion safety. Work in licensing,...
Multinational achievement: PPPL collaborates on record fusion plasma in
AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment SurfacesResource ProgramModification andinterface1JUNInformation Resourcestokamak in
COLLOQUIUM: Achieving 10MW Fusion Power in TFTR: a Retrospective |
AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to someone6Energy, science, andAnalysis15 CNMSHydraulicLab 15,
Bemerkungen zur "kalten Fusion"
Steven Jones et al. reported to have observed nuclear fusion at room temperature. They observed this "cold fusion" by electrolyzing heavy water. Later experiments confirmed these observations. These experiments confirmed the generation of strong electric fields within the deuterided metals. These electric fields accelerate the deuterons to keV energies and allow the observed nuclear fusion. Roman Sioda and I suggested a theoretical description of this nuclear fusion. Our "extended micro hot fusion" scenario explains how nuclear fusion can be generated over a long time within deuterided metals. Moreover we predicted the explosion of large pieces of deuterided metals. This article reviews the "cold fusion" work of Steven Jones et al. and discusses the fracto-fusion scenario. I show that the extended micro hot fusion scenario can explain the observed neutron emissions, neutron bursts, and heat bursts.
Rainer W. Kuehne
Kuehne, R W
Method of achieving the controlled release of thermonuclear energy
DOE Patents [OSTI]
A method of achieving the controlled release of thermonuclear energy by illuminating a minute, solid density, hollow shell of a mixture of material such as deuterium and tritium with a high intensity, uniformly converging laser wave to effect an extremely rapid build-up of energy in inwardly traveling shock waves to implode the shell creating thermonuclear conditions causing a reaction of deuterons and tritons and a resultant high energy thermonuclear burn. Utilizing the resulting energy as a thermal source and to breed tritium or plutonium. The invention also contemplates a laser source wherein the flux level is increased with time to reduce the initial shock heating of fuel and provide maximum compression after implosion; and, in addition, computations and an equation are provided to enable the selection of a design having a high degree of stability and a dependable fusion performance by establishing a proper relationship between the laser energy input and the size and character of the selected material for the fusion capsule.
Brueckner, Keith A. (Ann Arbor, MI)
Macron Formed Liner Compression as a Practical Method for Enabling Magneto-Inertial Fusion
The entry of fusion as a viable, competitive source of power has been stymied by the challenge of finding an economical way to provide for the confinement and heating of the plasma fuel. The main impediment for current nuclear fusion concepts is the complexity and large mass associated with the confinement systems. To take advantage of the smaller scale, higher density regime of magnetic fusion, an efficient method for achieving the compressional heating required to reach fusion gain conditions must be found. The very compact, high energy density plasmoid commonly referred to as a Field Reversed Configuration (FRC) provides for an ideal target for this purpose. To make fusion with the FRC practical, an efficient method for repetitively compressing the FRC to fusion gain conditions is required. A novel approach to be explored in this endeavor is to remotely launch a converging array of small macro-particles (macrons) that merge and form a more massive liner inside the reactor which then radially compresses and heats the FRC plasmoid to fusion conditions. The closed magnetic field in the target FRC plasmoid suppresses the thermal transport to the confining liner significantly lowering the imploding power needed to compress the target. With the momentum flux being delivered by an assemblage of low mass, but high velocity macrons, many of the difficulties encountered with the liner implosion power technology are eliminated. The undertaking to be described in this proposal is to evaluate the feasibility achieving fusion conditions from this simple and low cost approach to fusion. During phase I the design and testing of the key components for the creation of the macron formed liner have been successfully carried out. Detailed numerical calculations of the merging, formation and radial implosion of the Macron Formed Liner (MFL) were also performed. The phase II effort will focus on an experimental demonstration of the macron launcher at full power, and the demonstration of megagauss magnetic field compression by a small array of full scale macrons. In addition the physics of the compression of an FRC to fusion conditions will be undertaken with a smaller scale MFL. The timescale for testing will be rapidly accelerated by taking advantage of other facilities at MSNW where the target FRC will be created and translated inside the MFL just prior to implosion of the MFL. Experimental success would establish the concept at the ��?proof of principle� level and the following phase III effort would focus on the full development of the concept into a fusion gain device. Successful operation would lead to several benefits in various fields. It would have application to high energy density physics, as well as nuclear waste transmutation and alternate fission fuel cycles. The smaller scale device could find immediate application as an intense source of neutrons for diagnostic imaging and non-invasive object interrogation.
Slough, John
FESAC FUSION SIMULATION PROJECT (FSP) PANEL REPORT William Tang1
power plant (DEMO), further science and technology is needed to achieve the 2500 MW of continuous power1 FESAC FUSION SIMULATION PROJECT (FSP) PANEL REPORT William Tang1 , Riccardo Betti2 , Jeffrey) to FESAC, Dr. Raymond Orbach clearly identifies the overarching objective of the proposed Fusion Simulation
Charge exchange recombination spectroscopy on fusion devices
For fusion, obtaining reliable measurements of basic plasma parameters like ion and electron densities and temperatures is a primary goal. For theory, measurements are needed as a function of time and space to understand plasma transport and confinement with the ultimate goal of achieving economic nuclear fusion power. Electron profile measurements and plasma spectroscopy for the plasma ions are introduced. With the advent of Neutral Beam auxiliary plasma heating, Charge Exchange Recombination Spectroscopy provides accurate and time resolved measurements of the ions in large volume fusion devices. In acknowledgement of Nicol Peacock's role in the development of these techniques, still at the forefront of plasma fusion research, this paper describes the evolution of this diagnostic method.
Duval, B. P. [Centre de Recherches en Physique des Plasmas, EPFL, Lausanne (Switzerland)
Superheavy Elements - Achievements and Challenges
The search for superheavy elements (SHE) has yielded exciting results for both the 'cold fusion' approach with reactions employing Pb and Bi targets and the ''hot fusion'' reactions with {sup 48}Ca beams on actinide targets. The most recent activities at GSI were the successful production of a more neutron rich isotope of element 112 in the reaction {sup 48}Ca+{sup 238}U confirming earlier result from FLNR, and the attempt to synthesize an isotope with Z 120 in the reaction {sup 64}Ni+{sup 238}U. Apart from the synthesis of new elements, advanced nuclear structure studies for heavy and super heavy elements promise a detailed insight in the properties of nuclear matter under the extreme conditions of high Z and A. The means are evaporation residue(ER)-{alpha}-{alpha} and -{alpha}-{gamma} coincidence techniques applied after separation of the reaction products from the beam. Recent examples of interesting physics to be discovered in this region of the chart of nuclides are the investigation of K-isomers observed for {sup 252,254}No and indicated for {sup 270}Ds. Fast chemistry and precision mass measurements deliver in addition valuable information on the fundamental properties of the SHE.
Ackermann, Dieter [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Planckstr. 1, D-64291 Darmstadt (Germany)
Fusion Plasmas Martin Greenwald
. Despite the cold war, which raged for another 30 years, controlled fusion research became a modelFusion Plasmas Martin Greenwald Encyclopedia of Electrical and Electronic Engineering, John Webster - editor, published by John Wiley & Sons, New York (1999) #12;Controlled Fusion For half a century
Greenwald, Martin
Fusion Power Associates 34th Annual Meeting
/symmetry on the NIF #12;This is the time to promote innovation in achieving ignition and gain in the laboratory understanding what is required to demonstrate ignition on the National Ignition Facility (NIF) · Direct drive is a viable option for inertial confinement fusion (ICF) ignition relatively modest improvements to the NIF
Fusion Power Associates, 2011 Annual Meeting 1 General Fusion
7 Plasma Injector 10 people $3M 1 year #12;Fusion Power Associates, 2011 Annual Meeting 8 Density people $3.5M 14 months #12;Fusion Power Associates, 2011 Annual Meeting 11 Plasma Compression ExperimentsFusion Power Associates, 2011 Annual Meeting 1 General Fusion #12;Fusion Power Associates, 2011
50 Years of Fusion Research Fusion Innovation Research and Energy
, .... · Controlled Thermonuclear Fusion had great potential Uncontrolled Thermonuclear fusion demonstrated in 19521 50 Years of Fusion Research Dale Meade Fusion Innovation Research and Energy® Princeton, NJ SOFE 2009 June 1, 2009 San Diego, CA 92101 #12;2 #12;2 #12;3 Fusion Prior to Geneva 1958 · A period of rapid
Anomaly Detection for Resilient Control Systems Using Fuzzy-Neural Data Fusion Engine
Resilient control systems in critical infrastructures require increased cyber-security and state-awareness. One of the necessary conditions for achieving the desired high level of resiliency is timely reporting and understanding of the status and behavioral trends of the control system. This paper describes the design and development of a neural-network based data-fusion system for increased state-awareness of resilient control systems. The proposed system consists of a dedicated data-fusion engine for each component of the control system. Each data-fusion engine implements three-layered alarm system consisting of: (1) conventional threshold-based alarms, (2) anomalous behavior detector using self-organizing maps, and (3) prediction error based alarms using neural network based signal forecasting. The proposed system was integrated with a model of the Idaho National Laboratory Hytest facility, which is a testing facility for hybrid energy systems. Experimental results demonstrate that the implemented data fusion system provides timely plant performance monitoring and cyber-state reporting.
Ondrej Linda; Milos Manic; Timothy R. McJunkin
Microscopic study of Ca$+$Ca fusion
We investigate the fusion barriers for reactions involving Ca isotopes $\\mathrm{^{40}Ca}+\\mathrm{^{40}Ca}$, $\\mathrm{^{40}Ca}+\\mathrm{^{48}Ca}$, and $\\mathrm{^{48}Ca}+\\mathrm{^{48}Ca}$ using the microscopic time-dependent Hartree-Fock theory coupled with a density constraint. In this formalism the fusion barriers are directly obtained from TDHF dynamics. We also study the excitation of the pre-equilibrium GDR for the $\\mathrm{^{40}Ca}+\\mathrm{^{48}Ca}$ system and the associated $\\gamma$-ray emission spectrum. Fusion cross-sections are calculated using the incoming-wave boundary condition approach. We examine the dependence of fusion barriers on collision energy as well as on the different parametrizations of the Skyrme interaction.
R. Keser; A. S. Umar; V. E. Oberacker
The European Fusion Programme
The long-term objective of the European fusion programme is the harnessing of the power of fusion to help meet mankind's future energy needs.This paper describes the current research programme, the unique organisational character of the fusion programme, and European and world-wide co-operation. The future evolution of the programme as part of the European Research Area and the developments currently taking place in preparation for the possible construction of ITER, the next major step towards the realisation of fusion power, are discussed.
Antidormi, R.; Bartlett, D.; Bruhns, H. [European Commission (Belgium)
Indecomposable Fusion Products
We analyse the fusion products of certain representations of the Virasoro algebra for c=-2 and c=-7 which are not completely reducible. We introduce a new algorithm which allows us to study the fusion product level by level, and we use this algorithm to analyse the indecomposable components of these fusion products. They form novel representations of the Virasoro algebra which we describe in detail. We also show that a suitably extended set of representations closes under fusion, and indicate how our results generalise to all (1,q) models.
Matthias R. Gaberdiel; Horst G. Kausch
Fusion Energy Sciences
Large Scale Production Computing and Storage Requirements for Fusion Energy Sciences: Target 2017 The NERSC Program Requirements Review "Large Scale Production Computing and...
Path toward fusion energy
A brief history of the fusion research program is given. Some of the problems that plagued the developmental progress are described. (MOW)
Furth, H.P.
D-D Nuclear Fusion Using Different Size Pyroelectric Crystals
D-D Nuclear Fusion Using Different Size Pyroelectric Crystals A. M. Kovanen, D. J. Gillich, T. Z the conditions for D-D fusion in pyroelectric crystal accelerators. Three different pyroelectric crystal sizes are with the Department of Mechanical, Aerospace and Nuclear Engineering, Rensselaer Polytechnic Institute, Troy, NY. A. M
Danon, Yaron
Frontier of Fusion Research: Path to the Steady State Fusion Reactor by Large Helical Device
The ITER, the International Thermonuclear Experimental Reactor, which will be built in Cadarache in France, has finally started this year, 2006. Since the thermal energy produced by fusion reactions divided by the external heating power, i.e., the Q value, will be larger than 10, this is a big step of the fusion research for half a century trying to tame the nuclear fusion for the 6.5 Billion people on the Earth. The source of the Sun's power is lasting steadily and safely for 8 Billion years. As a potentially safe environmentally friendly and economically competitive energy source, fusion should provide a sustainable future energy supply for all mankind for ten thousands of years. At the frontier of fusion research important milestones are recently marked on a long road toward a true prototype fusion reactor. In its own merits, research into harnessing turbulent burning plasmas and thereby controlling fusion reaction, is one of the grand challenges of complex systems science.After a brief overview of a status of world fusion projects, a focus is given on fusion research at the National Institute for Fusion Science (NIFS) in Japan, which is playing a role of the Inter University Institute, the coordinating Center of Excellence for academic fusion research and by the Large Helical Device (LHD), the world's largest superconducting heliotron device, as a National Users' facility. The current status of LHD project is presented focusing on the experimental program and the recent achievements in basic parameters and in steady state operations. Since, its start in a year 1998, a remarkable progress has presently resulted in the temperature of 140 Million degree, the highest density of 500 Thousand Billion/cc with the internal density barrier (IDB) and the highest steady average beta of 4.5% in helical plasma devices and the largest total input energy of 1.6 GJ, in all magnetic confinement fusion devices. Finally, a perspective is given of the ITER Broad Approach program as an integrated part of ITER and Development of Fusion Energy project Agreement. Moreover, the relationship with the NIFS' new parent organization the National Institutes of Natural Sciences and with foreign research institutions is briefly explained.
Motojima, Osamu [National Institute for Fusion Science, Toki-shi, Gifu-ken, 509-5292 (Japan)
Magnetized Target Fusion (MTF): Principles, Status, and International Collaboration
Magnetized target fusion (MTF) is an approach to thermonuclear fusion that is intermediate between the two extremes of inertial and magnetic confinement. Target plasma preparation is followed by compression to fusion conditions. The use of a magnetic field to reduce electron thermal conduction and potentially enhance DT alpha energy deposition allows the compression rate to be drastically reduced relative to that for inertial confinement fusion. This leads to compact systems with target driver power and intensity requirements that are orders of magnitude lower than for ICF. A liner on plasma experiment has been proposed to provide a firm proof of principle for MTF.
Kirkpatrick, R.C.
Distribution Category: Magnetic Fusion Energy
. Abdou Fusion Power Program October 1982 Invited paper presented at the International Conference by Mohamed A. Abdou ABSTRACT Key technological problems that influence tritium breeding in fusion blankets
Abdou, Mohamed
On Lithium Wall and Performance of Magnetic Fusion Device S. I. Krasheninnikov1
On Lithium Wall and Performance of Magnetic Fusion Device S. I. Krasheninnikov1 , L. E. Zakharov2 It is shown that lithium walls resulting in zero recycling conditions at the edge of magnetic fusion device strong impact of fully absorbing lithium walls on the performance of magnetic fusion devices have been
Krstic, Miroslav
January 25, 2008/ARR 1 Heat and Mass Transfer in Fusion Energy
January 25, 2008/ARR 1 Heat and Mass Transfer in Fusion Energy Applications: from the "Very Cold, CA January 25, 2008 #12;January 25, 2008/ARR 2 Unique Set of Conditions Associated with Fusion · Realization of fusion energy imposes considerable challenges in the areas of engineering, physics and material
Raffray, A. René
DENSE MATTER IN LASER DRIVEN FUSION ! LABORATORY EXPERIMENTS R.L. Mc Crory and J. Wilson
irradiation to heat and compress a target containing thermonuclear fuel to fusion conditions. This is stillDENSE MATTER IN LASER DRIVEN FUSION ! LABORATORY EXPERIMENTS R.L. Mc Crory and J. Wilson Laboratory. The high power lasers in quaestion were constructed with laser fusion studies as the goal, i
Boyer, Edmond
Fusion Chamber Technology Publications
1. Abdou, M.A., The APEX Team, Ying, A., Morley, N., Gulec, K., Smolentsev, S., Kotschenreuther, M-248, 2001. 2. Mohamed Abdou and the APEX Team, Exploring novel high power density concepts for attractive fusion systems, Fusion Engineering and Design, vol. 45, pp. 145-167, 1999. 3. Abdou, M. A., Ying, A., Lu
California at Los Angeles, University of
Channeling of Fusion Alpha-Particle Power Using Minority Ion Catalysis A. I. Zhmoginov and N. J. Fisch
, with electrons kept cold, so that the effective fusion reactivity can be increased [911]. The meansChanneling of Fusion Alpha-Particle Power Using Minority Ion Catalysis A. I. Zhmoginov and N. J greatly facilitate controlled nuclear fusion. The parameter range for achieving this temperature disparity
"50" Years of Fusion Research Fusion Innovation Research and Energy
Classified US Program on Controlled Thermonuclear Fusion (Project Sherwood) carried out until 1958 when"50" Years of Fusion Research Dale Meade Fusion Innovation Research and Energy® Princeton, NJ Fi P th SFusion Fire Powers the Sun "W d t if k f i k ""We need to see if we can make fusion work
E-Print Network 3.0 - activity fusion reactions Sample Search...
condition E is energy confinement time Only three reactions can be used within a thermonuclear fusion... is energy confinement time Only three ... Source: Mauel,...
The National Ignition Facility and the Promise of Inertial Fusion Energy
The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory (LLNL) in Livermore, CA, is now operational. The NIF is the world's most energetic laser system capable of producing 1.8 MJ and 500 TW of ultraviolet light. By concentrating the energy from its 192 extremely energetic laser beams into a mm{sup 3}-sized target, NIF can produce temperatures above 100 million K, densities of 1,000 g/cm{sup 3}, and pressures 100 billion times atmospheric pressure - conditions that have never been created in a laboratory and emulate those in planetary interiors and stellar environments. On September 29, 2010, the first integrated ignition experiment was conducted, demonstrating the successful coordination of the laser, cryogenic target system, array of diagnostics and infrastructure required for ignition demonstration. In light of this strong progress, the U.S. and international communities are examining the implication of NIF ignition for inertial fusion energy (IFE). A laser-based IFE power plant will require a repetition rate of 10-20 Hz and a laser with 10% electrical-optical efficiency, as well as further development and advances in large-scale target fabrication, target injection, and other supporting technologies. These capabilities could lead to a prototype IFE demonstration plant in the 10- to 15-year time frame. LLNL, in partnership with other institutions, is developing a Laser Inertial Fusion Engine (LIFE) concept and examining in detail various technology choices, as well as the advantages of both pure fusion and fusion-fission schemes. This paper will describe the unprecedented experimental capabilities of the NIF and the results achieved so far on the path toward ignition. The paper will conclude with a discussion about the need to build on the progress on NIF to develop an implementable and effective plan to achieve the promise of LIFE as a source of carbon-free energy.
Moses, E I
BUILDING MOMENTUM ACHIEVING EXCELLENCE AnnuAlRepoRtofDonoRs July 1, 2013 June 30, 2014 #12;the '82 Douglas R. Cliggott '78 Lecturer UMass Amherst Jeanette Cole^ Associate Chair & Director UMass Amherst David J. Der Hagopian '72 (Retired) CEO Ravago Holdings Americare George R. Ditomassi Jr. '57, '96
Mountziaris, T. J.
POLICIES FOR ACHIEVING ENERGY JUSTICE IN SOCIETY: BEST PRACTICES FOR APPLYING SOLAR ENERGY) Project Center for Energy and Environmental Policy University of Delaware First Publication in July 2010 FOR APPLYING SOLAR ENERGY TECHNOLOGIES TO LOW-INCOME HOUSING Final Report A Renewable Energy Applications
Delaware, University of
strategic directions achievement"
jacaranda tree that graces the University of Sydney Quadrangle was planted in the 1920s. It has become inspired by achievement.......... 2 University structure and organisation.... 3 Research and innovation of existing practice - constructive but confronting. We seek sustainable economic development, and this means
Viglas, Anastasios
Achieving Sustainability Cindy Carlsson
Achieving Sustainability at MnDOT Cindy Carlsson MnDOT Office of Policy Analysis, Research and Innovation 22nd Annual Transportation Research Conference May 24, 2011 #12;Sustainable practices respect Sustainability #12;Environmental Sustainability Sustainable practices · Are compatible with and may enhance
Minnesota, University of
Achieving Sustainability Cindy Carlsson Mn/DOT Office of Policy Analysis, Research and Innovation April 21, 2011 #12;Sustainability Is Not New Mn/DOT has long been a leader in CSS and environmental excellence. . . . . . so we're well along on the path to sustainability! #12;Today Sustainability is More
Fusion Energy Sciences Program Mission
Fusion Energy Sciences Program Mission The Fusion Energy Sciences (FES) program leads the national for an economically and environmentally attractive fusion energy source. The National Energy Policy states that fusion power has the long-range potential to serve as an abundant and clean source of energy and recommends
RESEARCH HIGHLIGHTS State of fusion
RESEARCH HIGHLIGHTS State of fusion In the 1950s,the promise of controlled nuclear fusion, although there is still some way to go to realize the dream,the latest status report on fusion research for continued optimism. Nuclear fusion power relies on the energy released when two light atomic nuclei fuse
Loss, Daniel
Fusion Energy Program Presentation to
International Thermonuclear Experimental Reactor Plasma Technologies Fusion Technologies Advanced MaterialsFusion Energy Program Presentation to Field Work Proposals Washington, D.C. N. Anne Davies Associate Director for Fusion energy Office of Energy Research March23, 1994 #12;FUSION ENERGY PROGRAM FYI
Spherical torus fusion reactor
The object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.
Martin Peng, Y.K.M.
Requirements and Design Envelope for Volumetric Neutron Source Fusion Facilities for Fusion Nuclear Technology Development
The paper shows that timely development of fusion nuclear technology (FNT) components, e.g. blanket, for DEMO requires the construction and operation of a fusion facility parallel to ITER. This facility, called VNS, will be dedicated to testing, developing and qualifying FNT components and material combinations. Without VNS, i.e. with ITER alone, the confidence level in achieving DEMO operating goals has been quantified and is unacceptably low (< 1 %). An attractive design envelope for VNS exists. Tokamak VNS designs with driven plasma (Q ~ 1-3), steady state plasma operation and normal copper toroidal field coils lead to small sized devices with moderate cost.
Abdou, M [University of California, Los Angeles] [University of California, Los Angeles; Peng, Yueng Kay Martin [ORNL] [ORNL
How Fusion Energy Works
Broader source: Energy.gov [DOE]
Fusion energy is the energy source of the sun and all of the stars. As part of How Energy Works, we'll cover everything from fuel sources to plasma physics and beyond.
Project ACHIEVE final report
Project ACHIEVE was a math/science academic enhancement program aimed at first year high school Hispanic American students. Four high schools -- two in El Paso, Texas and two in Bakersfield, California -- participated in this Department of Energy-funded program during the spring and summer of 1996. Over 50 students, many of whom felt they were facing a nightmare future, were given the opportunity to work closely with personal computers and software, sophisticated calculators, and computer-based laboratories -- an experience which their regular academic curriculum did not provide. Math and science projects, exercises, and experiments were completed that emphasized independent and creative applications of scientific and mathematical theories to real world problems. The most important outcome was the exposure Project ACHIEVE provided to students concerning the college and technical-field career possibilities available to them.
Generalized Fusion Potentials
Recently, DiFrancesco and Zuber have characterized the RCFTs which have a description in terms of a fusion potential in one variable, and proposed a generalized potential to describe other theories. In this note we give a simple criterion to determine when such a generalized description is possible. We also determine which RCFTs can be described by a fusion potential in more than one variable, finding that in fact all RCFTs can be described in such a way, as conjectured by Gepner.
Ofer Aharony
Cold nuclear fusion
Recent accelerator experiments on fusion of various elements have clearly demonstrated that the effective cross-sections of these reactions depend on what material the target particle is placed in. In these experiments, there was a significant increase in the probability of interaction when target nuclei are imbedded in a conducting crystal or are a part of it. These experiments open a new perspective on the problem of so-called cold nuclear fusion.
Tsyganov, E. N., E-mail: email@example.com [University of Texas Southwestern Medical Center at Dallas (United States)
ITER Fusion Energy
ITER (in Latin ?the way?) is designed to demonstrate the scientific and technological feasibility of fusion energy. Fusion is the process by which two light atomic nuclei combine to form a heavier over one and thus release energy. In the fusion process two isotopes of hydrogen ? deuterium and tritium ? fuse together to form a helium atom and a neutron. Thus fusion could provide large scale energy production without greenhouse effects; essentially limitless fuel would be available all over the world. The principal goals of ITER are to generate 500 megawatts of fusion power for periods of 300 to 500 seconds with a fusion power multiplication factor, Q, of at least 10. Q ? 10 (input power 50 MW / output power 500 MW). The ITER Organization was officially established in Cadarache, France, on 24 October 2007. The seven members engaged in the project ? China, the European Union, India, Japan, Korea, Russia and the United States ? represent more than half the world?s population. The costs for ITER are shared by the seven members. The cost for the construction will be approximately 5.5 billion Euros, a similar amount is foreseen for the twenty-year phase of operation and the subsequent decommissioning.
Dr. Norbert Holtkamp
Liquid Vortex Shielding for Fusion Energy Applications
Swirling liquid vortices can be used in fusion chambers to protect their first walls and critical elements from the harmful conditions resulting from fusion reactions. The beam tube structures in heavy ion fusion (HIF) must be shielded from high energy particles, such as neutrons, x-rays and vaporized coolant, that will cause damage. Here an annular wall jet, or vortex tube, is proposed for shielding and is generated by injecting liquid tangent to the inner surface of the tube both azimuthally and axially. Its effectiveness is closely related to the vortex tube flow properties. 3-D particle image velocimetry (PIV) is being conducted to precisely characterize its turbulent structure. The concept of annular vortex flow can be extended to a larger scale to serve as a liquid blanket for other inertial fusion and even magnetic fusion systems. For this purpose a periodic arrangement of injection and suction holes around the chamber circumference are used, generating the layer. Because it is important to match the index of refraction of the fluid with the tube material for optical measurement like PIV, a low viscosity mineral oil was identified and used that can also be employed to do scaled experiments of molten salts at high temperature.
Bardet, Philippe M. [University of California, Berkeley (United States); Supiot, Boris F. [University of California, Berkeley (United States); Peterson, Per F. [University of California, Berkeley (United States); Savas, Oemer [University of California, Berkeley (United States)
Fusion Energy Division progress report, 1 January 1990--31 December 1991
The Fusion Program of the Oak Ridge National Laboratory (ORNL), a major part of the national fusion program, encompasses nearly all areas of magnetic fusion research. The program is directed toward the development of fusion as an economical and environmentally attractive energy source for the future. The program involves staff from ORNL, Martin Marietta Energy systems, Inc., private industry, the academic community, and other fusion laboratories, in the US and abroad. Achievements resulting from this collaboration are documented in this report, which is issued as the progress report of the ORNL Fusion Energy Division; it also contains information from components for the Fusion Program that are external to the division (about 15% of the program effort). The areas addressed by the Fusion Program include the following: experimental and theoretical research on magnetic confinement concepts; engineering and physics of existing and planned devices, including remote handling; development and testing of diagnostic tools and techniques in support of experiments; assembly and distribution to the fusion community of databases on atomic physics and radiation effects; development and testing of technologies for heating and fueling fusion plasmas; development and testing of superconducting magnets for containing fusion plasmas; development and testing of materials for fusion devices; and exploration of opportunities to apply the unique skills, technology, and techniques developed in the course of this work to other areas (about 15% of the Division`s activities). Highlights from program activities during 1990 and 1991 are presented.
Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.
Fusion Energy Division: Annual progress report, period ending December 31, 1987
The Fusion Program of Oak Ridge National Laboratory (ORNL), a major part of the national fusion program, carries out research in nearly all areas of magnetic fusion. Collaboration among staff from ORNL, Martin Marietta Energy Systems, Inc., private industry, the academic community, and other fusion laboratories, in the United States and abroad, is directed toward the development of fusion as an energy source. This report documents the program's achievements during 1987. Issued as the annual progress report of the ORNL Fusion Energy Division, it also contains information from components of the Fusion Program that are external to the division (about 15% of the program effort). The areas addressed by the Fusion Program include the following: experimental and theoretical research on magnetic confinement concepts, engineering and physics of existing and planned devices, development and testing of diagnostic tools and techniques in support of experiments, assembly and distribution to the fusion community of databases on atomic physics and radiation effects, development and testing of technologies for heating and fueling fusion plasmas, development and testing of superconducting magnets for containing fusion plasmas, and development and testing of materials for fusion devices. Highlights from program activities are included in this report. 126 figs., 15 tabs.
Morgan, O.B. Jr.; Berry, L.A.; Sheffield, J.
Environmental Conditions Environmental Conditions
Environmental Conditions Environmental Conditions Appendix II The unique geology, hydrology and instream habitat. This chapter examines how environmental conditions in the Deschutes watershed affect, the discussion characterizes the environmental conditions within three watershed areas: the Lower Deschutes
OAK A271 ADVANCED FUSION TECHNOLOGY RESEARCH AND DEVELOPMENT ANNUAL REPORT TO THE US DEPARTMENT OF ENERGY. The General Atomics (GA) Advanced Fusion Technology Program seeks to advance the knowledge base needed for next-generation fusion experiments, and ultimately for an economical and environmentally attractive fusion energy source. To achieve this objective, they carry out fusion systems design studies to evaluate the technologies needed for next-step experiments and power plants, and they conduct research to develop basic and applied knowledge about these technologies. GA's Advanced Fusion Technology program derives from, and draws on, the physics and engineering expertise built up by many years of experience in designing, building, and operating plasma physics experiments. The technology development activities take full advantage of the GA DIII-D program, the DIII-D facility and the Inertial Confinement Fusion (ICF) program and the ICF Target Fabrication facility.
Z, ZX, and X-1: A Realistic Path to High Fusion Yield
Z-pinches now constitute the most energetic and powerful sources of x-rays available by a large margin. The Z accelerator at Sandia National Laboratories has produced 1.8 MJ of x-ray energy, 280 TW of power, and hohlraum temperatures of 200 eV. These advances are being applied to inertial confinement fusion (ICF) experiments on Z. The requirements for high fusion yield are exemplified in the target to be driven by the X-1 accelerator. X-1 will drive two z-pinches, each producing 7 MJ of x-ray energy and about 1000 TW of x-ray power. Together, these radiation sources will heat a hohlraum containing the 4-mm diameter ICF capsule to a temperature exceeding 225 eV for about 10 ns, with the pulse shape required to drive the capsule to high fusion yield, in the range of 200--1000 MJ. Since X-1 consists of two identical accelerators, it is possible to mitigate the technical risk of high yield by constructing one accelerator. This accelerator, ZX, will bridge the gap from Z to X-1 by driving an integrated target experiment with a very efficient energy source, ZX will also provide experimental condition that the full specifications of the X-1 accelerator for high yield are achievable, and that a realistic path to high fission yield exists.
Advances in Inertial Confinement Fusion at the National Ignition Facility (NIF)
The 192-beam National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory (LLNL) in Livermore, CA, is now operational and conducting experiments. NIF, the flagship facility of the U.S. Inertial Confinement Fusion (ICF) Program, will achieve high-energy-density conditions never previously obtained in the laboratory - temperatures over 100 million K, densities of 1,000 g/cm3, and pressures exceeding 100 billion atmospheres. Such conditions exist naturally only in the interiors of the stars and during thermonuclear burn. Demonstration of ignition and thermonuclear burn in the laboratory is a major NIF goal. To date, the NIF laser has demonstrated all pulse shape, beam quality, energy, and other specifications required to meet the ignition challenge. On March 10, 2009, the NIF laser delivered 1.1 MJ of ultraviolet laser energy to target chamber center, approximately 30 times more energy than any previous facility. The ignition program at NIF is the National Ignition Campaign (NIC), a national collaboration for ignition experimentation with participation from General Atomics, LLNL, Los Alamos National Laboratory (LANL), Sandia National Laboratories (SNL), and the University of Rochester Laboratory for Laser Energetics (LLE). The achievement of ignition at NIF will demonstrate the scientific feasibility of ICF and focus worldwide attention on fusion as a viable energy option. A particular energy concept under investigation is the LIFE (Laser Inertial Fusion Energy) scheme. The LIFE engine is inherently safe, minimizes proliferation concerns associated with the nuclear fuel cycle, and can provide a sustainable carbon-free energy generation solution in the 21st century. This talk will describe NIF and its potential as a user facility and an experimental platform for high-energy-density science, NIC, and the LIFE approach for clean, sustainable energy.
FUSION NUCLEAR SCIENCE PROGRAM & SUPPORTING FUSION NUCLEAR SCIENCE FACILITY (FNSF): UPDATE · It was well recognized there were also critical materials and technology issues that needed to be addressed in order to apply the knowledge we gained about burning plasma state #12;FUSION NUCLEAR SCIENCE PROGRAM
Realization of Fusion Energy: An alternative fusion roadmap
Realization of Fusion Energy: An alternative fusion roadmap Farrokh Najmabadi Professor of Electrical & Computer Engineering Director, Center for Energy Research UC San Diego International Fusion Road of emerging nations, energy use is expected to grow ~ 4 fold in this century (average 1.6% annual growth rate
Ceramics for fusion devices
Ceramics are required for a number of applications in fusion devices, among the most critical of which are magnetic coil insulators, windows for RF heating systems, and structural uses. Radiation effects dominate consideration of candidate materials, although good pre-irradiation properties are a requisite. Materials and components can be optimized by careful control of chemical and microstructural content, and application of brittle material design and testing techniques. Future directions for research and development should include further extension of the data base in the areas of electrical, structural, and thermal properties; establishment of a fission neutron/fusion neutron correlation including transmutation gas effects; and development of new materials tailored to meet the specific needs of fusion reactors.
Fusion reactor control
The plasma kinetic temperature and density changes, each per an injected fuel density rate increment, control the energy supplied by a thermonuclear fusion reactor in a power production cycle. This could include simultaneously coupled control objectives for plasma current, horizontal and vertical position, shape and burn control. The minimum number of measurements required, use of indirect (not plasma parameters) system measurements, and distributed control procedures for burn control are to be verifiable in a time dependent systems code. The International Thermonuclear Experimental Reactor (ITER) has the need to feedback control both the fusion output power and the driven plasma current, while avoiding damage to diverter plates. The system engineering of fusion reactors must be performed to assure their development expeditiously and effectively by considering reliability, availability, maintainability, environmental impact, health and safety, and cost.
Plummer, D.A.
Fusion of Hydrogen to produce energy is one of the technologies under study to meet the mankind raising need in energy and as a substitute to fossil fuels for the future. This technology is under investigation for more than 30 years already, with, for example, the former construction of the experimental reactors Tore Supra, DIII-D and JET. With the construction of ITER to start, the next step to 'fusion for energy' will be done. In these projects, an extensive use of cryogenic systems is requested. Air Liquide has been involved as cryogenic partner in most of former and presently constructed fusion reactors. In the present paper, a review of the cryogenic systems we delivered to Tore Supra, JET, IPR and KSTAR will be presented.
Dauguet, P.; Bonneton, M.; Fauve, E.; Bernhardt, J. M.; Beauvisage, J.; Andrieu, F. [Air Liquide Advanced Technology Division BP15, ZI Les Engenieres, 38360 Sassenage (France); Gistau-Baguer, G. M.; Boissin, J. C. [Consultants, Grenoble (France)
A fusion reactor is provided having a near spherical-shaped plasma with a modest central opening through which straight segments of toroidal field coils extend that carry electrical current for generating a toroidal magnet plasma confinement fields. By retaining only the indispensable components inboard of the plasma torus, principally the cooled toroidal field conductors and in some cases a vacuum containment vessel wall, the fusion reactor features an exceptionally small aspect ratio (typically about 1.5), a naturally elongated plasma cross section without extensive field shaping, requires low strength magnetic containment fields, small size and high beta. These features combine to produce a spherical torus plasma in a unique physics regime which permits compact fusion at low field and modest cost.
Peng, Yueng-Kay M. (Oak Ridge, TN)
Simulation of Fusion Plasmas
The upcoming ITER experiment (www.iter.org) represents the next major milestone in realizing the promise of using nuclear fusion as a commercial energy source, by moving into the ?burning plasma? regime where the dominant heat source is the internal fusion reactions. As part of its support for the ITER mission, the US fusion community is actively developing validated predictive models of the behavior of magnetically confined plasmas. In this talk, I will describe how the plasma community is using the latest high performance computing facilities to develop and refine our models of the nonlinear, multiscale plasma dynamics, and how recent advances in experimental diagnostics are allowing us to directly test and validate these models at an unprecedented level.
Chris Holland
How much laser power can propagate through fusion plasma?
Propagation of intense laser beams is crucial for inertial confinement fusion, which requires precise beam control to achieve the compression and heating necessary to ignite the fusion reaction. The National Ignition Facility (NIF), where fusion will be attempted, is now under construction. Control of intense beam propagation may be ruined by laser beam self-focusing. We have identified the maximum laser beam power that can propagate through fusion plasma without significant self-focusing and have found excellent agreement with recent experimental data, and suggest a way to increase that maximum by appropriate choice of plasma composition with implication for NIF designs. Our theory also leads to the prediction of anti-correlation between beam spray and backscatter and suggests the indirect control of backscatter through manipulation of plasma ionization state or acoustic damping.
Pavel M. Lushnikov; Harvey A. Rose
Fusion technology status and requirements
This paper summarizes the status of fusion technology and discusses the requirements to be met in order to build a demonstration fusion plant. Strategies and programmatic considerations in pursuing engineering feasibility are also outlined.
Thomassen, K.I.
data fusion 15 June 2012
real world data fusion Fred Daum 15 June 2012 data fusion Copyright © 2012 Raytheon Company. All rights reserved. Customer Success Is Our Mission is a trademark of Raytheon Company. 1 #12;PATRIOT
Dobigeon, Nicolas
Fusion Rules in Navier-Stokes Turbulence: First Experimental Tests
We present the first experimental tests of the recently derived fusion rules for Navier-Stokes (N-S) turbulence. The fusion rules address the asymptotic properties of many-point correlation functions as some of the coordinates coalesce, and form an important ingredient of the nonperturbative statistical theory of turbulence. Here we test the fusion rules when the spatial separations lie within the inertial range, and find good agreement between experiment and theory. An unexpected result is a simple linear law for the Laplacian of the velocity fluctuation conditioned on velocity increments across large separations.
Adrienne L. Fairhall; Brindesh Dhruva; Victor S. L'vov; Itamar Procaccia; Katepalli R. Sreenivasan
Stau-catalyzed d-t Nuclear Fusion
The gravitino of mass 10-100 GeV is a well motivated scenario in supergravity. If the stau is the next lightest supersymmetry particle, its life-time becomes order of $10^{6-8}$ sec. If it is the case the stau makes a big impact on the nuclear fusion, since it is a charged particle. In this paper we perform a detailed calculation of a stau-catalyzed d-t fusion. We find that if certain technical conditions are satisfied, it is not hopeless to use the nuclear fusion as a source of energy.
Koichi Hamaguchi; Tetsuo Hatsuda; Masayasu Kamimura; Tsutomu T. Yanagida
Fusion welding process
A process for the fusion welding of nickel alloy steel members wherein a ferrite containing pellet is inserted into a cavity in one member and melted by a welding torch. The resulting weld nugget, a fusion of the nickel containing alloy from the members to be welded and the pellet, has a composition which is sufficiently low in nickel content such that ferrite phases occur within the weld nugget, resulting in improved weld properties. The steel alloys encompassed also include alloys containing carbon and manganese, considered nickel equivalents.
Thomas, Kenneth C. (Export, PA); Jones, Eric D. (Salem, PA); McBride, Marvin A. (Hempfield Township, Westmoreland County, PA)
Princeton -Weekly Bulletin 2/10/03 -Abraham: U.S. participation in international fusion effort builds on success at PPPL
international fusion energy initiative called ITER. Praising the achievements of the fusion energy research into heavier elements such as helium and release enormous amounts of energy. Efforts to control and harnessPrinceton - Weekly Bulletin 2/10/03 - Abraham: U.S. participation in international fusion effort
Assessment of NDE Methods to Detect Lack of Fusion in HDPE Butt Fusion Joints
Studies at the Pacific Northwest National Laboratory (PNNL) in Richland, Washington, were conducted to evaluate nondestructive examinations (NDE) coupled with mechanical testing of butt fusion joints in high-density polyethylene (HDPE) pipe for assessing lack of fusion. The work provided information to the United States Nuclear Regulatory Commission (NRC) on the effectiveness of volumetric inspection techniques of HDPE butt fusion joints in Section III, Division 1, Class 3, buried piping systems in nuclear power plants. This paper describes results from assessments using ultrasonic and microwave nondestructive techniques and mechanical testing with the high-speed tensile impact test and the side-bend test for determining joint integrity. A series of butt joints were fabricated in 3408, 12-inch (30.5-cm) IPS DR-11 HDPE material by varying the fusion parameters to create good joints and joints containing a range of lack-of-fusion conditions. Six of these butt joints were volumetrically examined with time-of-flight diffraction (TOFD), phased-array (PA) ultrasound, and the Evisive microwave system. The outer diameter (OD) weld beads were removed for microwave evaluation and the pipes ultrasonically re-evaluated. In two of the six pipes, both the outer and inner diameter (ID) weld beads were removed and the pipe joints re-evaluated. Some of the pipes were sectioned and the joints destructively evaluated with the high-speed tensile test and the side-bend test. The fusion parameters, nondestructive and destructive evaluation results have been correlated to validate the effectiveness of what each NDE technology detects and what each does not detect. There was no single NDE method that detected all of the lack-of-fusion flaws but a combination of NDE methods did detect most of the flaws.
Crawford, Susan L.; Doctor, Steven R.; Cinson, Anthony D.; Watts, Michael W.; Moran, Traci L.; Anderson, Michael T.
Fusion potentials I
We reconsider the conjecture by Gepner that the fusion ring of a rational conformal field theory is isomorphic to a ring of polynomials in $n$ variables quotiented by an ideal of constraints that derive from a potential. We show that in a variety of cases, this is indeed true with {\\it one-variable} polynomials.
P. Di Francesco; J. -B. Zuber
About sponsorship Fusion power
using the energy released when two light atomic nuclei are brought together to make a heavier one are needed. Unlike existing nuclear reactors, which produce nasty long-lived radioactive waste, the radioactive processes involved with fusion are relatively short- lived and the waste products benign. Unlike
New mechanism of membrane fusion
We have carried out Monte Carlo simulation of the fusion of bilayers of single chain amphiphiles which show phase behavior similar to that of biological lipids. The fusion mechanism we observe is very different from the ``stalk'' hypothesis. Stalks do form on the first stage of fusion, but they do not grow radially to form a hemifused state. Instead, stalk formation destabilizes the membranes and results in hole formation in the vicinity of the stalks. When holes in each bilayer nucleate spontaneously next to the same stalk, an incomplete fusion pore is formed. The fusion process is completed by propagation of the initial connection, the stalk, along the edges of the aligned holes.
M. Mueller; K. Katsov; M. Schick
Stau-catalyzed Nuclear Fusion
We point out that the stau may play a role of a catalyst for nuclear fusions if the stau is a long-lived particle as in the scenario of gravitino dark matter. In this letter, we consider d d fusion under the influence of stau where the fusion is enhanced because of a short distance between the two deuterons. We find that one chain of the d d fusion may release an energy of O(10) GeV per stau. We discuss problems of making the stau-catalyzed nuclear fusion of practical use with the present technology of producing stau.
K. Hamaguchi; T. Hatsuda; T. T. Yanagida
Vector Boson Fusion Higgs Production at the LHC - Mass Variables
There exist substantial backgrounds to the vector boson fusion production of Higgs at the LHC. Mass variables are studied which may alleviate the need to assume a spin zero WW resonance in order to achieve a sufficient signal to noise ratio in the two jet plus two lepton and missing energy final state.
Dan Green
LASER FUSION CHAMBER DESIGN James P. Blanchard1
the energy emitted by the target in such a way that the plant can achieve a commercially viable power approaches required for commercially viable laser fusion power plants, the issues driving those designs define the chamber size by providing flux limits for the various threats. In cases where a dry
Raffray, A. Ren�
anterior cervical fusion: Topics by E-print Network
Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...
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Inspection of Fusion Joints in Plastic Pipe
The standard method of joining plastic pipe in the field is the butt fusion process. As in any pipeline application, joint quality greatly affects overall operational safety of the system. Currently no simple, reliable, cost-effective method exists for assessing the quality of fusion joints in the field. Visual examination and pressure testing are current nondestructive approaches, which do not provide any assurance about the long-term pipeline performance. This project developed, demonstrated, and validated an in-situ nondestructive inspection method for butt fusion joints in gas distribution plastic pipelines. The inspection system includes a laser-based image-recognition system that automatically generates and interprets digital images of pipe joints and assigns them a pass/fail rating, which eliminates operator bias in evaluating joint quality. An EWI-patented process, the Weld Zone Inspection Method (WZIM) was developed in which local heat is applied to the joint region to relax the residual stresses formed by the original joining operation, which reveals the surface condition of the joint. In cases where the joint is not formed under optimal conditions, and the intermolecular forces between contacting surfaces are not strong enough, the relaxation of macromolecules in the surface layer causes the material to pull back, revealing a fusion line. If the joint is sound, the bond line image does not develop. To establish initial feasibility of the approach, welds were performed under standard and nonstandard conditions. These welds were subjected to the WZIM and two destructive forms of testing: short-term tensile testing and long-term creep rupture testing. There appears to be a direct correlation between the WZIM and the destructive testing results. Although WZIM appears to be more sensitive than destructive testing can verify, the approach appears valid.
Connie Reichert
The neutronics studies of fusion fission hybrid power reactor
In this paper, a series of neutronics analysis of hybrid power reactor is proposed. The ideas of loading different fuels in a modular-type fission blanket is analyzed, fitting different level of fusion developments, i.e., the current experimental power output, the level can be obtained in the coming future and the high-power fusion reactor like ITER. The energy multiplication of fission blankets and tritium breeding ratio are evaluated as the criterion of design. The analysis is implemented based on the D-type simplified model, aiming to find a feasible 1000MWe hybrid power reactor for 5 years' lifetime. Three patterns are analyzed: 1) for the low fusion power, the reprocessed fuel is chosen. The fuel with high plutonium content is loaded to achieve large energy multiplication. 2) For the middle fusion power, the spent fuel from PWRs can be used to realize about 30 times energy multiplication. 3) For the high fusion power, the natural uranium can be directly used and about 10 times energy multiplication can be achieved.
Zheng Youqi; Wu Hongchun; Zu Tiejun; Yang Chao; Cao Liangzhi [School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049 (China)
Fusion pumped laser
The apparatus of this invention may comprise a system for generating laser radiation from a high-energy neutron source. The neutron source is a tokamak fusion reactor generating a long pulse of high-energy neutrons and having a temperature and magnetic field effective to generate a neutron flux of at least 10/sup 15/ neutrons/cm/sup 2//center dot/s. Conversion means are provided adjacent the fusion reactor at a location operable for converting the high-energy neutrons to an energy source with an intensity and energy effective to excite a preselected lasing medium. A lasing medium is spaced about and responsive to the energy source to generate a population inversion effective to support laser oscillations for generating output radiation. 2 figs., 2 tabs.
Pappas, D.S.
Still Flying Fusion Edition
please either join the Yahoo Group (http://uk.groups.yahoo.com/group/stillflying) or email the editor (email@example.com - subject heading "Contribution"). Disclaimer This publication is not affiliated with Joss Whedon ; Mutant Enemy, Inc.... This abridged edition is available only at Fusion, Issue Two will be available soon, complete with an Adam Baldwin interview! If you wish to subscribe (for free) please email firstname.lastname@example.com with the subject heading "Subscribe" and you...
Inertial Confinement Fusion R&D and Nuclear Proliferation
In a few months, or a few years, the National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory may achieve fusion gain using 192 powerful lasers to generate x-rays that will compress and heat a small target containing isotopes of hydrogen. This event would mark a major milestone after decades of research on inertial confinement fusion (ICF). It might also mark the beginning of an accelerated global effort to harness fusion energy based on this science and technology. Unlike magnetic confinement fusion (ITER, 2011), in which hot fusion fuel is confined continuously by strong magnetic fields, inertial confinement fusion involves repetitive fusion explosions, taking advantage of some aspects of the science learned from the design and testing of hydrogen bombs. The NIF was built primarily because of the information it would provide on weapons physics, helping the United States to steward its stockpile of nuclear weapons without further underground testing. The U.S. National Academies' National Research Council is now hosting a study to assess the prospects for energy from inertial confinement fusion. While this study has a classified sub-panel on target physics, it has not been charged with examining the potential nuclear proliferation risks associated with ICF R&D. We argue here that this question urgently requires direct and transparent examination, so that means to mitigate risks can be assessed, and the potential residual risks can be balanced against the potential benefits, now being assessed by the NRC. This concern is not new (Holdren, 1978), but its urgency is now higher than ever before.
Robert J. Goldston
Fusion Policy Advisory Committee FINAL REPORT
Fusion Policy Advisory Committee (FPAC) FINAL REPORT September 1990 Report of the Technical Panel on Magnetic Fusion of the Energy Research Advisory Board Washington, D .C. 20585 #12;#12;Fusion Policy of your Fusion Policy Advisory Committee. It presents a fusion policy that the Committee believes
Methodology for Scaling Fusion Power Plant Availability
Normally in the U.S. fusion power plant conceptual design studies, the development of the plant availability and the plant capital and operating costs makes the implicit assumption that the plant is a 10th of a kind fusion power plant. This is in keeping with the DOE guidelines published in the 1970s, the PNL report1, "Fusion Reactor Design Studies - Standard Accounts for Cost Estimates. This assumption specifically defines the level of the industry and technology maturity and eliminates the need to define the necessary research and development efforts and costs to construct a one of a kind or the first of a kind power plant. It also assumes all the "teething" problems have been solved and the plant can operate in the manner intended. The plant availability analysis assumes all maintenance actions have been refined and optimized by the operation of the prior nine or so plants. The actions are defined to be as quick and efficient as possible. This study will present a methodology to enable estimation of the availability of the one of a kind (one OAK) plant or first of a kind (1st OAK) plant. To clarify, one of the OAK facilities might be the pilot plant or the demo plant that is prototypical of the next generation power plant, but it is not a full-scale fusion power plant with all fully validated "mature" subsystems. The first OAK facility is truly the first commercial plant of a common design that represents the next generation plant design. However, its subsystems, maintenance equipment and procedures will continue to be refined to achieve the goals for the 10th OAK power plant.
Lester M. Waganer
Tritium plasma experiment: Parameters and potentials for fusion plasma-wall interaction studies
The tritium plasma experiment (TPE) is a unique facility devoted to experiments on the behavior of deuterium/tritium in toxic (e.g., beryllium) and radioactive materials for fusion plasma-wall interaction studies. A Langmuir probe was added to the system to characterize the plasma conditions in TPE. With this new diagnostic, we found the achievable electron temperature ranged from 5.0 to 10.0 eV, the electron density varied from 5.0 x 10{sup 16} to 2.5 x 10{sup 18} m{sup -3}, and the ion flux density varied between 5.0 x 10{sup 20} to 2.5 x 10{sup 22} m{sup -2} s{sup -1} along the centerline of the plasma. A comparison of these plasma parameters with the conditions expected for the plasma facing components (PFCs) in ITER shows that TPE is capable of achieving most ({approx}800 m{sup 2} of 850 m{sup 2} total PFCs area) of the expected ion flux density and electron density conditions.
Shimada, Masashi; Sharpe, J. Phillip [Fusion Safety Program, Idaho National Laboratory, Idaho Falls, Idaho 83415 (United States); Kolasinski, Robert D.; Causey, Rion A. [Hydrogen and Metallurgical Science Department, Sandia National Laboratories, Livermore, California 94551 (United States)
mechanisms leading to fusion, nuclear structure is affectingknoi,. A [he "nuclear structure" in fusion will consist ofCI i CO I0 + Be fusion I0 ' -cm Nuclear reaction S-factors
Stokstad, R.G.
INL Fusion Safety Program - Past Publications
Significant publications from the INL Fusion Safety Program D. A. Petti and K. A. McCarthy, "Progress in US fusion safety and environmental activities over the last decade," Fusion...
Pathways to Laser Fusion Beyond NIF Fusion Power Associates Meeting
Pathways to Laser Fusion Beyond NIF Fusion Power Associates Meeting Washington DC 10 December 2013 Research supported by the Department of Energy, NNSA #12;How far will NIF go towards ignition? NIF indirect of laser energy on capsule · Ignition and significant yield?? NIF Polar drive · Much more efficient use
Fusion Electricity A roadmap to the realisation of fusion energy
Fusion Electricity A roadmap to the realisation of fusion energy #12;28 European countries signed association EURaToM � University of latvia LATVIA lithuanian Energy Institute LITHUANIA Ministry of Education and Research ROMANIA Ministry of Education, science, culture and sport SLOVENIA centro de Investigaciones
Fusion reactor pumped laser
A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam.
Jassby, Daniel L. (Princeton, NJ)
US ITER - Why Fusion?
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Fusion Nuclear Science | ORNL
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Fusion Science to Prepare
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Fusion Power Associates Awards
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Photons & Fusion Newsletter
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US ITER | Why Fusion?
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Physics Regimes in the Fusion Ignition Research Experiment (FIRE)
Burning plasma science is recognized widely as the next frontier in fusion research. The Fusion Ignition Research Experiment (FIRE) is a design study of a next-step burning plasma experiment with the goal of developing a concept for an experimental facility to explore and understand the strong nonlinear coupling among confinement, magnetohydrodynamic (MHD) self-heating, stability, edge physics, and wave-particle interactions that is fundamental to fusion plasma behavior. This will require plasmas dominated by alpha heating (Q greater than or equal to 5) that are sustained for a duration comparable to characteristic plasma timescales (greater than or equal to 10) tau(subscript ''E''), approximately 4 tau(subscript ''He''), approximately 2 tau(subscript ''skin''). The work reported here has been undertaken with the objective of finding the minimum size (cost) device to achieve these physics goals.
D.M. Meade; S.C.Jardin; C.E. Kessel; M.A. Ulrickson; J.H. Schultz; P.H. Rutherford; J.A. Schmidt; J.C. Wesley; K.M. Young; N.A.Uckan; R.J. Thome; P. Heitzenroeder; B.E. Nelson; and C.C.Baker
Wafer Fusion for Integration of Semiconductor Materials and Devices
We have developed a wafer fusion technology to achieve integration of semiconductor materials and heterostructures with widely disparate lattice parameters, electronic properties, and/or optical properties for novel devices not now possible on any one substrate. Using our simple fusion process which uses low temperature (400-600 C) anneals in inert N{sub 2} gas, we have extended the scope of this technology to examine hybrid integration of dissimilar device technologies. As a specific example, we demonstrate wafer bonding vertical cavity surface emitting lasers (VCSELs) to transparent AlGaAs and GaP substrates to fabricate bottom-emitting short wavelength VCSELs. As a baseline fabrication technology applicable to many semiconductor systems, wafer fusion will revolutionize the way we think about possible semiconductor devices, and enable novel device configurations not possible by epitaxial growth.
Choquette, K.D.; Geib, K.M.; Hou, H.Q.; Allerman, A.A.; Kravitz, S.; Follstaedt, D.M.; Hindi, J.J.
Study of internal magnetic field via polarimetry in fusion plasmas
Motivation Controlled thermonuclear fusion is a promising2007]. Controlled thermonuclear fusion is based on the
Zhang, Jie
VEHICLE NETWORKS: ACHIEVING REGULAR FORMATION MADALENA CHAVES, ROBERT DAY, LUCIA GOMEZ a network of vehicles exchanging information among themselves with the intention of achieving a specified the performance of the vehicle network. A stochastic model for information flow is also considered, allowing
Cellulose binding domain fusion proteins
A cellulose binding domain (CBD) having a high affinity for crystalline cellulose and chitin is disclosed, along with methods for the molecular cloning and recombinant production thereof. Fusion products comprising the CBD and a second protein are likewise described. A wide range of applications are contemplated for both the CBD and the fusion products, including drug delivery, affinity separations, and diagnostic techniques.
Shoseyov, Oded (Karmey Yosef, IL); Shpiegl, Itai (Rehovot, IL); Goldstein, Marc A. (Davis, CA); Doi, Roy H. (Davis, CA)
Quasi-rational fusion products
Fusion is defined for arbitrary lowest weight representations of $W$-algebras, without assuming rationality. Explicit algorithms are given. A category of quasirational representations is defined and shown to be stable under fusion. Conjecturally, it may coincide with the category of representations of finite quantum dimensions.
Werner Nahm
A cellulose binding domain (CBD) having a high affinity for crystalline cellulose and chitin is disclosed, along with methods for the molecular cloning and recombinant production. Fusion products comprising the CBD and a second protein are likewise described. A wide range of applications are contemplated for both the CBD and the fusion products, including drug delivery, affinity separations, and diagnostic techniques. 16 figs.
Shoseyov, O.; Yosef, K.; Shpiegl, I.; Goldstein, M.A.; Doi, R.H.
su(3)k fusion coefficients
A closed and explicit formula for all $\\su{(3)}_k$ fusion coefficients is presented which, in the limit $k \\rightarrow \\infty$, turns into a simple and compact expression for the $su(3)$ tensor product coefficients. The derivation is based on a new diagrammatic method which gives directly both tensor product and fusion coefficients.
L. Begin; P. Mathieu; M. A. Walton
Fusion Policy Advisory Committee (FPAC)
This document is the final report of the Fusion Policy Advisory Committee. The report conveys the Committee's views on the matters specified by the Secretary in his charge and subsequent letters to the Committee, and also satisfies the provisions of Section 7 of the Magnetic Fusion Energy Engineering Act of 1980, Public Law 96-386, which require a triennial review of the conduct of the national Magnetic Fusion Energy program. Three sub-Committee's were established to address the large number of topics associated with fusion research and development. One considered magnetic fusion energy, a second considered inertial fusion energy, and the third considered issues common to both. For many reasons, the promise of nuclear fusion as a safe, environmentally benign, and affordable source of energy is bright. At the present state of knowledge, however, it is uncertain that this promise will become reality. Only a vigorous, well planned and well executed program of research and development will yield the needed information. The Committee recommends that the US commit to a plan that will resolve this critically important issue. It also outlines the first steps in a development process that will lead to a fusion Demonstration Power Plant by 2025. The recommended program is aggressive, but we believe the goal is reasonable and attainable. International collaboration at a significant level is an important element in the plan.
Not Available
Fusion Nuclear Science Facility (FNSF)
Fusion Nuclear Science Facility (FNSF) Motivation, Role, Required Capabilities YK Martin Peng;1 Managed by UT-Battelle for the Department of Energy Example: fusion nuclear-nonnuclear coupling effects-composites; Nano-structure alloy; PFC designs, etc. · Nuclear-nonnuclear coupling in PFC: - Plasma ion flux induces
Frontiers of Fusion Materials Science
migration Radiation damage accumulation kinetics · 1 D vs. 3D diffusion processes · ionization Insulators · Optical Materials *asterisk denotes Fusion Materials Task Group #12;Fusion Materials Sciences R Displacement cascades Quantification of displacement damage source term · Is the concept of a liquid valid
Magnetic Fusion Pilot Plant Studies
FNSF = Fusion Nuclear Science Facility CTF = Component Test Facility · Powerplantlike maintenance. · Targeted ultimate capabilities: Fusion nuclear S&T development, component testing · Steady applicable to power plant · Demonstrate methods for fast replacement of in-vessel components Net
The Fusion Machine (extended abstract)
directly. In the fusion machine, only channels exist at runtime. Channels may be remote, or co to rendezvous at the chan- nel. Execution amounts to the heating of a term (a directed implementation, rendezvous can result in explicit fusions, namely equational concurrent constraints on names. Upon heating
Gardner, Philippa
Clean steels for fusion
Fusion energy production has an inherent advantage over fission: a fuel supply with reduced long term radioactivity. One of the leading candidate materials for structural applications in a fusion reactor is a tungsten stabilized 9% chromium Martensitic steel. This alloy class is being considered because it offers the opportunity to maintain that advantage in the reactor structure as well as provide good high temperature strength and radiation induced swelling and embrittlement resistance. However, calculations indicate that to obtain acceptable radioactivity levels within 500 years after service, clean steel will be required because the niobium impurity levels must be kept below about 2 appm and nickel, molybdenum, nitrogen, copper, and aluminum must be intentionally restricted. International efforts are addressing the problems of clean steel production. Recently, a 5,000 kg heat was vacuum induction melted in Japan using high purity commercial raw materials giving niobium levels less than 0.7 appm. This paper reviews the need for reduced long term radioactivity, defines the advantageous properties of the tungsten stabilized Martensitic steel class, and describes the international efforts to produce acceptable clean steels.
Gelles, D.S.
Fusion - 2050 perspective (in Polish)
The results of strongly exothermic reaction of thermonuclear fusion between nuclei of deuterium and tritium are: helium nuclei and neutrons, plus considerable kinetic energy of neutrons of over 14 MeV. DT nuclides synthesis reaction is probably not the most favorable one for energy production, but is the most advanced technologically. More efficient would be possibly aneutronic fusion. The EU by its EURATOM agenda prepared a Road Map for research and implementation of Fusion as a commercial method of thermonuclear energy generation in the time horizon of 2050.The milestones on this road are tokomak experiments JET, ITER and DEMO, and neutron experiment IFMIF. There is a hope, that by engagement of the national government, and all research and technical fusion communities, part of this Road Map may be realized in Poland. The infrastructure build for fusion experiments may be also used for material engineering research, chemistry, biomedical, associated with environment protection, power engineering, security, ...
Romaniuk, R S
JOURNAL DE PHYSIQUE Colloque C1, supplkment au no2, Tome 40,fkvr~er1979, page C1-73 ATOMIC, IONIC AND MOLECULAR DATA IN THERMO-NUCLEAR FUSION RESEARCH
AND MOLECULAR DATA IN THERMO-NUCLEAR FUSION RESEARCH H.W. Drawin Association EURATOM-CEA DQpartement de Physique section deals with molecular data which are of interest in thermo-nuclear fusion research. 1. INTRODUCTION In order to achieve controlled thermo- nuclear fusion of deuterium and tritium one needs both high
Paris-Sud XI, Université de
Information Technology Systems for Fusion Industry and ITER Project
The industrial developments in the fusion industry will have to overcome numerous technical challenges and will have a strong need for modern information technology (IT) systems.The fusion industry has manifested itself with an unprecedented international collaboration, the International Thermonuclear Experimental Reactor (ITER). Data accumulated in ITER will be the major output of the project and will create the knowledge base for a future fusion power plant. A modern and effective information infrastructure will be critical to the success of the ITER project.To accumulate and maintain the knowledge base at all stages of the project, we propose to build an integrated information system for ITER: ITER Information Plant (IIP). IIP will minimize lost experiment time and accelerate the understanding, interpretation, and planning of fusion experiments. IIP will allow to reap maximum benefits from the project's scientific and technological achievements, make the ITER results accessible to hundreds of researchers worldwide. This will facilitate collaboration, dramatically increasing the pace of scientific and technological discovery and the rate at which practical use is made of these discoveries.As the first of its kind, the ITER Information Plant could be used in the future as a prototype IT system for national and international fusion projects, in which multicountry collaboration, distributed work sites and operations are catalysts for success.
Putvinskaya, N.; Bulasheva, N.; Cole, G.; Dillon, T.; Frieman, E.; Sabado, M.; Schissel, D. (and others)
Recent Accomplishments and Future Directions in US Fusion Safety & Environmental Program
The US fusion program has long recognized that the safety and environmental (S&E) potential of fusion can be attained by prudent materials selection, judicious design choices, and integration of safety requirements into the design of the facility. To achieve this goal, S&E research is focused on understanding the behavior of the largest sources of radioactive and hazardous materials in a fusion facility, understanding how energy sources in a fusion facility could mobilize those materials, developing integrated state of the art S&E computer codes and risk tools for safety assessment, and evaluating S&E issues associated with current fusion designs. In this paper, recent accomplishments are reviewed and future directions outlined.
David A. Petti; Brad J. Merrill; Phillip Sharpe; L. C. Cadwallader; L. El-Guebaly; S. Reyes
Organic materials for fusion-reactor applications
Organic materials requirements for fusion-reactor magnets are described with reference to the temperature, radiation, and electrical and mechanical stress environment expected in these magnets. A review is presented of the response to gamma-ray and neutron irradiation at low temperatures of candidate organic materials; i.e. laminates, thin films, and potting compounds. Lifetime-limiting features of this response as well as needed testing under magnet operating conditions not yet adequately investigated are identified and recomendations for future work are made.
Hurley, G.F.; Coltman, R.R. Jr.
Electron screening effect on stellar thermonuclear fusion
We study the impact of plasma correlation effects on nonresonant thermonuclear reactions for various stellar objects, namely in the liquid envelopes of neutron stars, and the interiors of white dwarfs, low-mass stars, and substellar objects. We examine in particular the effect of electron screening on the enhancement of thermonuclear reactions in dense plasmas within and beyond the linear mixing rule approximation as well as the corrections due to quantum effects at high density. In addition, we examine some recent unconventional (Yukawa-potential and "quantum-tail") theoretical results on stellar thermonuclear fusions and show that these scenarios do not apply to stellar conditions.
Potekhin, A Y
LiWall Fusion - The New Concept of Magnetic Fusion
Utilization of the outstanding abilities of a liquid lithium layer in pumping hydrogen isotopes leads to a new approach to magnetic fusion, called the LiWall Fusion. It relies on innovative plasma regimes with low edge density and high temperature. The approach combines fueling the plasma by neutral injection beams with the best possible elimination of outside neutral gas sources, which cools down the plasma edge. Prevention of cooling the plasma edge suppresses the dominant, temperature gradient related turbulence in the core. Such an approach is much more suitable for controlled fusion than the present practice, relying on high heating power for compensating essentially unlimited turbulent energy losses.
L.E. Zakharov
PPPL-3183 -Preprint: May 1996, UC-420, 424, 426 Fusion Reactivity, Confinement, and Stability of
controllable plasma parameters, the limitation and optimization of fusion power production of the present TFTR with a reversed shear (RS) magnetic configuration [8], and Supershots enhanced by Li pellet conditioning [9, 10
Determination of the deuterium-tritium branching ratio based on inertial confinement fusion implosions
The deuterium-tritium (D-T) ?-to-neutron branching ratio [[superscript 3]H(d,?)[superscript 5]He/[superscript 3]H(d,n)[superscript 4]He] was determined under inertial confinement fusion (ICF) conditions, where the ...
Rosenberg, Michael Jonathan
Fusion option to dispose of spent nuclear fuel and transuranic elements
The fusion option is examined to solve the disposition problems of the spent nuclear fuel and the transuranic elements. The analysis of this report shows that the top rated solution, the elimination of the transuranic elements and the long-lived fission products, can be achieved in a fusion reactor. A 167 MW of fusion power from a D-T plasma for sixty years with an availability factor of 0.75 can transmute all the transuranic elements and the long-lived fission products of the 70,000 tons of the US inventory of spent nuclear fuel generated up to the year 2015. The operating time can be reduced to thirty years with use of 334 MW of fusion power, a system study is needed to define the optimum time. In addition, the fusion solution eliminates the need for a geological repository site, which is a major advantage. Meanwhile, such utilization of the fusion power will provide an excellent opportunity to develop fusion energy for the future. Fusion blankets with a liquid carrier for the transuranic elements can achieve a transmutation rate for the transuranic elements up to 80 kg/MW.y of fusion power with k{sub eff} of 0.98. In addition, the liquid blankets have several advantages relative to the other blanket options. The energy from this transmutation is utilized to produce revenue for the system. Molten salt (Flibe) and lithium-lead eutectic are identified as the most promising liquids for this application, both materials are under development for future fusion blanket concepts. The Flibe molten salt with transuranic elements was developed and used successfully as nuclear fuel for the molten salt breeder reactor in the 1960's.
Gohar, Y.
Poxvirus entry and membrane fusion
The study of poxvirus entry and membrane fusion has been invigorated by new biochemical and microscopic findings that lead to the following conclusions: (1) the surface of the mature virion (MV), whether isolated from an infected cell or by disruption of the membrane wrapper of an extracellular virion, is comprised of a single lipid membrane embedded with non-glycosylated viral proteins; (2) the MV membrane fuses with the cell membrane, allowing the core to enter the cytoplasm and initiate gene expression; (3) fusion is mediated by a newly recognized group of viral protein components of the MV membrane, which are conserved in all members of the poxvirus family; (4) the latter MV entry/fusion proteins are required for cell to cell spread necessitating the disruption of the membrane wrapper of extracellular virions prior to fusion; and furthermore (5) the same group of MV entry/fusion proteins are required for virus-induced cell-cell fusion. Future research priorities include delineation of the roles of individual entry/fusion proteins and identification of cell receptors.
Moss, Bernard [Laboratory of Viral Diseases, National Institute of Allergy and Infectious Diseases, National Institutes of Health, Bethesda, MD 20892-0445 (United States)]. E-mail: email@example.com
Muon catalyzed fusion
This paper presents an overview of the program and results of our experiment performed by a European-American collatoration at the Swiss Institute of Nuclear Research. Systematic investigations of the low temperature region (23K to 300K) reveal a surprisingly rich physics of mesoatomic and mesomolecular processes, unparalleled in other systems of isotopic hydrogen mixtures. A dramatic density dependence of the reaction rates is found. The rich structure in the time spectra of the fusion neutrons observed at low gas density yields first evidence for new effects, most likely strong contributions from reactions of hot muonic atoms. The important question of muon losses due to He sticking is investigated by different methods and over a wide range of tritium concentrations.
Breunlich, W.H.; Cargnelli, M.; Marton, J.; Naegele, N.; Pawlek, P.; Scrinzi, A.; Werner, J.; Zmeskal, J.; Bistirlich, J.; Crowe, K.M.
A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam. 10 figs.
Jassby, D.L.
Fusion pumped light source
Apparatus is provided for generating energy in the form of light radiation. A fusion reactor is provided for generating a long, or continuous, pulse of high-energy neutrons. The neutron flux is coupled directly with the lasing medium. The lasing medium includes a first component selected from Group O of the periodic table of the elements and having a high inelastic scattering cross section. Gamma radiation from the inelastic scattering reactions interacts with the first component to excite the first component, which decays by photon emission at a first output wavelength. The first output wavelength may be shifted to a second output wavelength using a second liquid component responsive to the first output wavelength. The light outputs may be converted to a coherent laser output by incorporating conventional optics adjacent the laser medium.
Pappas, Daniel S. (Los Alamos, NM)
Fusion rules in conformal field theory
Several aspects of fusion rings and fusion rule algebras, and of their manifestations in twodimensional (conformal) field theory, are described: diagonalization and the connection with modular invariance; the presentation in terms of quotients of polynomial rings; fusion graphs; various strategies that allow for a partial classification; and the role of the fusion rules in the conformal bootstrap programme.
J. Fuchs
Temperature & Nuclear Fusion 4 October 2011
Temperature & Nuclear Fusion 4 October 2011 Goals · Review temperature in stars · Practice using the important energy scales for nuclear fusion Temperature 1. For each relation we regularly use in class-Boltzmann equation: L = 4R2 T4 . (d) In fusion energy generation: T . #12;temperature & nuclear fusion 2 Nuclear
Militzer, Burkhard
Temperature & Nuclear Fusion 4 October 2011 Goals · Review temperature in stars · Practice using the important energy scales for nuclear fusion Temperature 1. For each relation we regularly use in class temperature. #12;temperature & nuclear fusion 2 Nuclear Fusion 2. There are a few different energy scales
Magnetic Confinement Fusion at the Crossroads
Matterhorn initiated at Princeton 1950s Classified US Project Sherwood on controlled thermonuclear fusionMagnetic Confinement Fusion at the Crossroads Michael Bell Princeton Plasma Physics Laboratory #12;MGB / UT / 070307 2 The Beginnings of Fusion Energy Research 1928 Concept of fusion reactions
Fusion project decision delayed ITER -NUCLEAR FUSION PROJECT
that are needed," said Hidekazu Tanaka, a senior official of the Japanese Education, Culture, Sports, Science at the level of an electricity- producing power station. Its goal will be to produce 500 megawatts of fusion
Magnetized Target Fusion: Input to the 35-yr Fusion Long-Range Electric Plan
controlled thermonuclear fusion in the laboratory -- Intermediate between MFE and IFE · Presently only fundedMagnetized Target Fusion: Input to the 35-yr Fusion Long-Range Electric Plan G. A. Wurden Fusion Energy Program Office Los Alamos National Laboratory Jan. 14, 2003 #12;Magnetized Target Fusion: Input
Advanced fusion concepts: project summaries
This report contains descriptions of the activities of all the projects supported by the Advanced Fusion Concepts Branch of the Office of Fusion Energy, US Department of Energy. These descriptions are project summaries of each of the individual projects, and contain the following: title, principle investigators, funding levels, purpose, approach, progress, plans, milestones, graduate students, graduates, other professional staff, and recent publications. Information is given for each of the following programs: (1) reverse-field pinch, (2) compact toroid, (3) alternate fuel/multipoles, (4) stellarator/torsatron, (5) linear magnetic fusion, (6) liners, and (7) Tormac. (MOW)
Economic analysis of fusion breeders
This paper presents a study of the economic performance of Fission/Fusion Hybrid devices. This work takes fusion breeder cost estimates and applies methodology and cost factors used in the fission reactor programs to compare fusion breeders with Liquid Metal Fast Breeder Reactors (LMFBR). The results of the analysis indicate that the Hybrid will be in the same competitive range as proposed LMFBRs and have the potential to provide economically competitive power in a future of rising uranium prices. The sensitivity of the results to variations in key parameters is included.
Delene, J.G.
Class II virus membrane fusion proteins
Enveloped animal viruses fuse their membrane with a host cell membrane, thus delivering the virus genetic material into the cytoplasm and initiating infection. This critical membrane fusion reaction is mediated by a virus transmembrane protein known as the fusion protein, which inserts its hydrophobic fusion peptide into the cell membrane and refolds to drive the fusion reaction. This review describes recent advances in our understanding of the structure and function of the class II fusion proteins of the alphaviruses and flaviviruses. Inhibition of the fusion protein refolding reaction confirms its importance in fusion and suggests new antiviral strategies for these medically important viruses.
Kielian, Margaret [Department of Cell Biology, Albert Einstein College of Medicine, 1300 Morris Park Ave., Bronx, NY 10461 (United States)]. E-mail: email@example.com
Fusion Rules for Extended Current Algebras
The initial classification of fusion rules have shown that rational conformal field theory is very limited. In this paper we study the fusion rules of extend ed current algebras. Explicit formulas are given for the S matrix and the fusion rules, based on the full splitting of the fixed point fields. We find that in s ome cases sensible fusion rules are obtained, while in others this procedure lea ds to fractional fusion constants.
Ernest Baver; Doron Gepner
Virasoro Representations on Fusion Graphs
For any non-unitary model with central charge c(2,q) the path spaces associated to a certain fusion graph are isomorphic to the irreducible Virasoro highest weight modules.
J. Kellendonk; A. Recknagel
Maintenance FUSION IGNITION RESEARCH EXPERIMENT
Insulation Enclosure Remote Maintenance Module FUSION IGNITION RESEARCH EXPERIMENT SYSTEM describes the status of the configuration development and the integration of the major subsystem components vessel structural stiffness, this configuration makes use of the cooling jacket as nuclear shielding
Pulsed Power Driven Fusion Energy
Pulsed power is a robust and inexpensive technology for obtaining high powers. Considerable progress has been made on developing light ion beams as a means of transporting this power to inertial fusion capsules. However, further progress is hampered by the lack of an adequate ion source. Alternatively, z-pinches can efficiently convert pulsed power into thermal radiation, which can be used to drive an inertial fusion capsule. However, a z-pinch driven fusion explosion will destroy a portion of the transmission line that delivers the electrical power to the z-pinch. They investigate several options for providing standoff for z-pinch driven fusion. Recyclable Transmission Lines (RTLs) appear to be the most promising approach.
EURATOM/CCFE Fusion Association
- Public Understanding and Education Outreach 7 - Training 7 JET Operations 8 JET Studies 11 MAST 14 - MAST to capture heat from the fusion core to generate electricity in a power station. In this Executive Summary
Preface to Special Topic: Advances in Radio Frequency Physics in Fusion Plasmas
It has long been recognized that auxiliary plasma heating will be required to achieve the high temperature, high density conditions within a magnetically confined plasma in which a fusion �burn� may be sustained by copious fusion reactions. Consequently, the application of radio and microwave frequency electromagnetic waves to magnetically confined plasma, commonly referred to as RF, has been a major part of the program almost since its inception in the 1950s. These RF waves provide heating, current drive, plasma profile control, and Magnetohydrodynamics (MHD) stabilization. Fusion experiments employ electromagnetic radiation in a wide range of frequencies, from tens of MHz to hundreds of GHz. The fusion devices containing the plasma are typically tori, axisymmetric or non, in which the equilibrium magnetic fields are composed of a strong toroidal magnetic field generated by external coils, and a poloidal field created, at least in the symmetric configurations, by currents flowing in the plasma. The waves are excited in the peripheral regions of the plasma, by specially designed launching structures, and subsequently propagate into the core regions, where resonant wave-plasma interactions produce localized heating or other modification of the local equilibrium profiles. Experimental studies coupled with the development of theoretical models and advanced simulation codes over the past 40+ years have led to an unprecedented understanding of the physics of RF heating and current drive in the core of magnetic fusion devices. Nevertheless, there are serious gaps in our knowledge base that continue to have a negative impact on the success of ongoing experiments and that must be resolved as the program progresses to the next generation devices and ultimately to �demo� and �fusion power plant.� A serious gap, at least in the ion cyclotron (IC) range of frequencies and partially in the lower hybrid frequency ranges, is the difficulty in coupling large amount of power to the plasma while minimizing the interaction between the plasma and launching structures. These potentially harmful interactions between the plasma and the vessel and launching structures are challenging: (i) significant and variable loss of power in the edge regions of confined plasmas and surrounding vessel structures adversely affect the core plasma performance and lifetime of a device; (ii) the launcher design is partly �trial and error,� with the consequence that launchers may have to be reconfigured after initial tests in a given device, at an additional cost. Over the broader frequency range, another serious gap is a quantitative lack of understanding of the combined effects of nonlinear wave-plasma processes, energetic particle interactions and non-axisymmetric equilibrium effects on determining the overall efficiency of plasma equilibrium and stability profile control techniques using RF waves. This is complicated by a corresponding lack of predictive understanding of the time evolution of transport and stability processes in fusion plasmas.
Tuccillo, Angelo A.; Ceccuzzi, Silvio [Unit� Tecnica Fusione ENEA, C. R. Frascati, 00044 RM (Italy); Phillips, Cynthia K. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States)
Japanese magnetic confinement fusion research
Six U.S. scientists surveyed and assessed Japanese research and development in magnetic fusion. The technical accomplishments from the early 1980s through June 1989 are reviewed, and the Japanese capabilities and outlook for future contributions are assessed. Detailed evaluations are provided in the areas of basic and applied plasma physics, tokamak confinement, alternate confinement approaches, plasma technology, and fusion nuclear technology and materials.
Davidson, R.C.; Abdou, M.A.; Berry, L.A.; Horton, C.W.; Lyon, J.F.; Rutherford, P.H.
Prospects for improved fusion reactors
Ideally, a new energy source must be capable of displacing old energy sources while providing both economic opportunities and enhanced environmental benefits. The attraction of an essentially unlimited fuel supply has generated a strong impetus to develop advanced fission breeders and, even more strongly, the exploitation of nuclear fusion. Both fission and fusion systems trade a reduced fuel charge for a more capital-intensive plant needed to utilize a cheaper and more abundant fuel. Results from early conceptual designs of fusion power plants, however, indicated a capital intensiveness that could override cost savings promised by an inexpensive fuel cycle. Early warnings of these problems appeared, and generalized routes to more economically attractive systems have been suggested; specific examples have also recently been given. Although a direct reduction in the cost (and mass) of the fusion power core (FPC, i.e., plasma chamber, first wall, blanket, shield, coils, and primary structure) most directly reduces the overall cost of fusion power, with the mass power density (MPD, ratio of net electric power to FPC mass, kWe/tonne) being suggested as a figure-of-merit in this respect, other technical, safety/environmental, and institutional issues also enter into the definition of and direction for improved fusion concepts. These latter issues and related tradeoffs are discussed.
Krakowski, R.A.; Miller, R.L.; Hagenson, R.L.
The US Department of Energy (DOE) has clearly defined requirements for nuclear material control and accountability (MC&A) of tritium whereas the International Atomic Energy Agency (IAEA) does not since tritium is not a fissile material. MC&A requirements are expected for tritium fusion machines and will be dictated by the host country or regulatory body where the machine is operated. Material Balance Areas (MBAs) are defined to aid in the tracking and reporting of nuclear material movements and inventories. Material subaccounts (MSAs) are established along with key measurement points (KMPs) to further subdivide a MBA to localize and minimize uncertainties in the inventory difference (ID) calculations for tritium accountancy. Fusion systems try to minimize tritium inventory which may require continuous movement of material through the MSAs. The ability of making meaningful measurements of these material transfers is described in terms of establishing the MSA structure to perform and reconcile ID calculations. For fusion machines, changes to the traditional ID equation will be discussed which includes breading, burn-up, and retention of tritium in the fusion device. The concept of �net� tritium quantities consumed or lost in fusion devices is described in terms of inventory taking strategies and how it is used to track the accumulation of tritium in components or fusion machines.
Klein, J. E.; Farmer, D. A.; Moore, M. L.; Tovo, L. L.; Poore, A. S.; Clark, E. A.; Harvel, C. D.
Ignition and Inertial Confinement Fusion at The National Ignition Facility
The National Ignition Facility (NIF), the world's largest and most powerful laser system for inertial confinement fusion (ICF) and for studying high-energy-density (HED) science, is now operational at Lawrence Livermore National Laboratory (LLNL). The NIF is now conducting experiments to commission the laser drive, the hohlraum and the capsule and to develop the infrastructure needed to begin the first ignition experiments in FY 2010. Demonstration of ignition and thermonuclear burn in the laboratory is a major NIF goal. NIF will achieve this by concentrating the energy from the 192 beams into a mm{sup 3}-sized target and igniting a deuterium-tritium mix, liberating more energy than is required to initiate the fusion reaction. NIF's ignition program is a national effort managed via the National Ignition Campaign (NIC). The NIC has two major goals: execution of DT ignition experiments starting in FY2010 with the goal of demonstrating ignition and a reliable, repeatable ignition platform by the conclusion of the NIC at the end of FY2012. The NIC will also develop the infrastructure and the processes required to operate NIF as a national user facility. The achievement of ignition at NIF will demonstrate the scientific feasibility of ICF and focus worldwide attention on laser fusion as a viable energy option. A laser fusion-based energy concept that builds on NIF, known as LIFE (Laser Inertial Fusion Energy), is currently under development. LIFE is inherently safe and can provide a global carbon-free energy generation solution in the 21st century. This paper describes recent progress on NIF, NIC, and the LIFE concept.
Industrial Scale Demonstration of Smart Manufacturing Achieving...
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Neutron imaging with bubble chambers for inertial confinement fusion.
??One of the main methods to obtain energy from controlled thermonuclear fusion is inertial confinement fusion (ICF), a process where nuclear fusion reactions are initiated� (more)
Ghilea, Marian Constantin (1973 - ); Meyerhofer, David D.
ash fusion temperature: Topics by E-print Network
and Fusion Performance Plasma Physics and Fusion Websites Summary: Inst. for Plasma Research 3 Univ. of Texas Inst for Fusion Studies (October 6, 1999) The physics in a...
Deuterium Uptake in Magnetic Fusion Devices with Lithium Conditioned Carbon
AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to UserProduct: CrudeOffice ofINLNuclear262AboutDesignerFileDetectingWalls
Conformal nets III: fusion of defects
Conformal nets provides a mathematical model for conformal field theory. We define a notion of defect between conformal nets, formalizing the idea of an interaction between two conformal field theories. We introduce an operation of fusion of defects, and prove that the fusion of two defects is again a defect, provided the fusion occurs over a conformal net of finite index. There is a notion of sector (or bimodule) between two defects, and operations of horizontal and vertical fusion of such sectors. Our most difficult technical result is that the horizontal fusion of the vacuum sectors of two defects is isomorphic to the vacuum sector of the fused defect. Equipped with this isomorphism, we construct the basic interchange isomorphism between the horizontal fusion of two vertical fusions and the vertical fusion of two horizontal fusions of sectors.
Arthur Bartels; Christopher L. Douglas; Andr� Henriques
Kinetic advantage of controlled intermediate nuclear fusion
The dominated process of controlled fusion is to let nuclei gain enough kinetic energy to overcome Coulomb barrier. As a result, a fusion scheme can consider two factors in its design: to increase kinetic energy of nuclei and to alter the Coulomb barrier. Cold Fusion and Hot fusion are all one-factor schemes while Intermediate Fusion is a twofactors scheme. This made CINF kinetically superior. Cold Fusion reduces deuteron-deuteron distance, addressing Coulomb barrier, and Hot Fusion heat up plasma into extreme high temperature, addressing kinetic energy. Without enough kinetic energy made Cold Fusion skeptical. Extreme high temperature made Hot Fusion very difficult to engineer. Because CIFN addresses both factors, CIFN is a more promising technique to be industrialized.
Guo Xiaoming [Physics and Computer Science Department, Wilfrid Laurier University, Waterloo, Ontario, N2L 3C5 (Canada)
Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System
of Con- trolled Nuclear Fusion, CONF-760975-P3, pages 1061�more effective solution, nuclear fusion. Fission Energy Thethe development of nuclear fusion weapons, humankind has
Kramer, Kevin James
Fusion Plasma Theory project summaries
This Project Summary book is a published compilation consisting of short descriptions of each project supported by the Fusion Plasma Theory and Computing Group of the Advanced Physics and Technology Division of the Department of Energy, Office of Fusion Energy. The summaries contained in this volume were written by the individual contractors with minimal editing by the Office of Fusion Energy. Previous summaries were published in February of 1982 and December of 1987. The Plasma Theory program is responsible for the development of concepts and models that describe and predict the behavior of a magnetically confined plasma. Emphasis is given to the modelling and understanding of the processes controlling transport of energy and particles in a toroidal plasma and supporting the design of the International Thermonuclear Experimental Reactor (ITER). A tokamak transport initiative was begun in 1989 to improve understanding of how energy and particles are lost from the plasma by mechanisms that transport them across field lines. The Plasma Theory program has actively-participated in this initiative. Recently, increased attention has been given to issues of importance to the proposed Tokamak Physics Experiment (TPX). Particular attention has been paid to containment and thermalization of fast alpha particles produced in a burning fusion plasma as well as control of sawteeth, current drive, impurity control, and design of improved auxiliary heating. In addition, general models of plasma behavior are developed from physics features common to different confinement geometries. This work uses both analytical and numerical techniques. The Fusion Theory program supports research projects at US government laboratories, universities and industrial contractors. Its support of theoretical work at universities contributes to the office of Fusion Energy mission of training scientific manpower for the US Fusion Energy Program.
Rep-Rated Target Injection for Inertial Fusion Energy
Inertial Fusion Energy (IFE) with laser drivers is a pulsed power generation system that relies on repetitive, high-speed injection of targets into a fusion reactor. To produce an economically viable IFE power plant the targets must be injected into the reactor at a rate between 5 and 10 Hz.To survive the injection process, direct drive (laser fusion) targets (spherical capsules) are placed into protective sabots. The sabots separate from the target and are stripped off before entering the reactor chamber. Indirect drive (heavy ion fusion) utilizes a hohlraum surrounding the spherical capsule and enters the chamber as one piece.In our target injection demonstration system, the sabots or hohlraums are injected into a vacuum system with a light gas gun using helium as a propellant. To achieve pulsed operation a rep-rated injection system has been developed. For a viable power plant we must be able to fire continuously at 6 Hz. This demonstration system is currently set up to allow bursts of up to 12 targets at 6 Hz. Using the current system, tests have been successfully run with direct drive targets to show sabot separation under vacuum and at barrel exit velocities of {approx}400 m/s.The existing revolver system along with operational data will be presented.
Frey, D.T.; Goodin, D.T.; Stemke, R.W.; Petzoldt, R.W.; Drake, T.J.; Egli, W.; Vermillion, B.A.; Klasen, R.; Cleary, M.M
The Path to Magnetic Fusion Energy
When the possibility of fusion as an energy source for electricity generation was realized in the 1950s, understanding of the plasma state was primitive. The fusion goal has been paced by, and has stimulated, the development of plasma physics. Our understanding of complex, nonlinear processes in plasmas is now mature. We can routinely produce and manipulate 100 million degree plasmas with remarkable finesse, and we can identify a path to commercial fusion power. The international experiment, ITER, will create a burning (self-sustained) plasma and produce 500 MW of thermal fusion power. This talk will summarize the progress in fusion research to date, and the remaining steps to fusion power.
Prager, Stewart (PPPL) [PPPL
FIRE, A Next Step Option for Magnetic Fusion
The next major frontier in magnetic fusion physics is to explore and understand the strong nonlinear coupling among confinement, MHD stability, self-heating, edge physics, and wave-particle interactions that is fundamental to fusion plasma behavior. The Fusion Ignition Research Experiment (FIRE) Design Study has been undertaken to define the lowest cost facility to attain, explore, understand, and optimize magnetically confined fusion-dominated plasmas. The FIRE is envisioned as an extension of the existing Advanced Tokamak Program that could lead to an attractive magnetic fusion reactor. The FIRE activities have focused on the physics and engineering assessment of a compact, high-field tokamak with the capability of achieving Q approximately equal to 10 in the ELMy H-mode for a duration of about 1.5 plasma current redistribution times (skin times) during an initial burning-plasma science phase, and the flexibility to add Advanced Tokamak hardware (e.g., lower-hybrid current drive) later. The configuration chosen for FIRE is similar to that of ARIES-RS, the U.S. Fusion Power Plant study utilizing an Advanced Tokamak reactor. The key ''Advanced Tokamak'' features are: strong plasma shaping, double-null pumping divertors, low toroidal field ripple (<0.3%), internal control coils, and space for wall stabilization capabilities. The reference design point is R subscript ''o'' = 2.14 m, a = 0.595 m, B subscript ''t''(R subscript ''o'') = 10 T, I subscript ''p'' = 7.7 MA with a flattop time of 20 s for 150 MW of fusion power. The baseline magnetic fields and pulse lengths can be provided by wedged BeCu/OFHC toroidal-field (TF) coils and OFHC poloidal-field (PF) coils that are pre-cooled to 80 K prior to the pulse and allowed to warm up to 373 K at the end of the pulse. A longer-term goal of FIRE is to explore Advanced Tokamak regimes sustained by noninductive current drive (e.g., lower-hybrid current drive) at high fusion gain (Q > 5) for a duration of 1 to 3 current redistribution times.
Meade, D.M.
An Assessment of the Economics of Future Electric Power Generation Options and the Implications for Fusion
This study examines the potential range of electric power costs for some major alternatives to fusion electric power generation when it is ultimately deployed in the middle of the 21st century and, thus, offers a perspective on the cost levels that fusion must achieve to be competitive. The alternative technologies include coal burning, coal gasification, natural gas, nuclear fission, and renewable energy. The cost of electricity (COE) from the alternatives to fusion should remain in the 30-50 mils/kWh (1999 dollars) range of today in carbon sequestration is not needed, 30-60 mils/kWh if sequestration is required, or as high as 75 mils/kWh for the worst-case scenario for cost uncertainty. The reference COE range for fusion was estimated at 70-100 nmils/kWh for 1- to 1.3-GW(e) scale power plants. Fusion costs will have to be reduced and/or alternative concepts derived before fusion will be competitive with the alternatives for the future production of electricity. Fortunately, there are routes to achieve this goal.
Delene, J.G.; Hadley, S.; Reid, R.L.; Sheffield, J.; Williams, K.A.
Application of reliability analysis method to fusion component testing
The term reliability here implies that a component satisfies a set of performance criteria while under specified conditions of use over a specified period of time. For fusion nuclear technology, the reliability goal to be pursued is the development of a mean time between failures (MTBF) for a component which is longer than its lifetime goal. While the component lifetime is mainly determined by the fluence limitation (i.e., damage level) which leads to performance degradation or failure, the MTBF represents an arithmetic average life of all units in a population. One method of assessing the reliability goal involves determining component availability needs to meet the goal plant availability, defining a test-analyze-fix development program to improve component reliability, and quantifying both test times and the number of test articles that would be required to ensure that a specified target MTBF is met. Statistically, constant failure rates and exponential life distributions are assumed for analyses and blanket component development is used as an example. However, as data are collected the probability distribution of the parameter of interest can be updated in a Bayesian fashion. The nuclear component testing program will be structured such that reliability requirements for DEMO can be achieved. The program shall not exclude the practice of a good design (such as reducing the complexity of the system to the minimum essential for the required operation), the execution of high quality manufacturing and inspection processes, and the implication of quality assurance and control for component development. In fact, the assurance of a high quality testing/development program is essential so that there is no question left for reliability.
Ying, A.Y.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States)
Image fusion for a nighttime driving display
An investigation into image fusion for a nighttime driving display application was performed. Most of the image fusion techniques being investigated in this application were developed for other purposes. When comparing the ...
Herrington, William Frederick
Fusion Energy Sciences Advisory Committee Strategic Planning
with excellent safety features and modest environmental impact that is available to all nations. The quest of the fusion fuel from within the reactor. Throughout its history, the quest for fusion has been a global
Role of atomic collisions in fusion
Atomic physics issues have played a large role in controlled fusion research. A general discussion of the present role of atomic processes in both magnetic and inertial controlled fusion work is presented.
Post, D.E.
Idaho National Laboratory Fusion Safety Program
Contact Information: Brad Merrill 208-526-0395 Email Contact Fusion Safety Program Thermonuclear fusion powers the Sun and the stars and is the most powerful energy source known....
EURATOM/CCFE Fusion Association Annual Report
European and UK fusion research Public understanding and education outreach Training JET operations Tokamak for clean electricity generation here on earth. Fusion power stations would emit no greenhouse gases
Establishment of an Institute for Fusion Studies. Technical progress report, November 1, 1994--October 31, 1995
The Institute for Fusion Studies is a national center for theoretical fusion plasma physics research. Its purposes are to (1) conduct research on theoretical questions concerning the achievement of controlled fusion energy by means of magnetic confinement--including both fundamental problems of long-range significance, as well as shorter-term issues; (2) serve as a national and international center for information exchange by hosting exchange visits, conferences, and workshops; and (3) train students and postdoctoral research personnel for the fusion energy program and plasma physics research areas. During FY 1995, a number of significant scientific advances were achieved at the IFS, both in long-range fundamental problems as well as in near-term strategic issues, consistent with the Institute`s mandate. Examples of these achievements include, for example, tokamak edge physics, analytical and computational studies of ion-temperature-gradient-driven turbulent transport, alpha-particle-excited toroidal Alfven eigenmode nonlinear behavior, sophisticated simulations for the Numerical Tokamak Project, and a variety of non-tokamak and non-fusion basic plasma physics applications. Many of these projects were done in collaboration with scientists from other institutions. Research discoveries are briefly described in this report.
Fusion rules and singular vectors of the osp(1|2) current algebra
The fusion of Verma modules of the osp(1|2) current algebra is studied. In the framework of an isotopic formalism, the singular vector decoupling conditions are analyzed. The fusion rules corresponding to the admissible representations of the osp(1|2) algebra are determined. A relation between the characters of these last representations and those corresponding to the minimal superconformal models is found. A series of equations that relate the descendants of the highest weight vectors resulting from a fusion of Verma modules are obtained. Solving these equations the singular vectors of the theory can be determined.
I. P. Ennes; A. V. Ramallo
Dispersion relation approach to sub-barrier heavy-ion fusion reactions
We discuss the conditions under which the dispersion relation technique, extensively employed in the context of elastic scattering, can be used in the analysis of heavy-ion fusion reactions. General unitarity defect arguments are used for this purpose. With the aid of an inverse dispersion relation, which gives the imaginary part of the fusion inclusive polarization potential in terms of the principal part integral involving the real part of the inclusive polarization potential, the sub-barrier fusion of heavy ions is discussed. The system /sup 16/O+/sup A/Sm is taken as an example.
Franzin, V.L.M.; Hussein, M.S.
Fusion Nuclear Science and Technology (FNST)Fusion Nuclear Science and Technology (FNST) Challenges and Facilities
Fusion Nuclear Science and Technology (FNST)Fusion Nuclear Science and Technology (FNST) Challenges these issues. 2 #12;FNST is the science, engineering, technology and materials Fusion Nuclear Science & Technology (FNST) FNST is the science, engineering, technology and materials for the fusion nuclear
Fusion Nuclear Science and Technology (FNST)Fusion Nuclear Science and Technology (FNST) Challenges on MFE Roadmapping in the ITER Era Princeton, NJ 7-10 September 2011 1 #12;Fusion Nuclear Science never done any experiments on FNST in a real fusion nuclear environment we must be realistic on what
Science/Fusion Energy Sciences FY 2007 Congressional Budget Fusion Energy Sciences
Science/Fusion Energy Sciences FY 2007 Congressional Budget Fusion Energy Sciences Funding Profile Adjustments FY 2006 Current Appropriation FY 2007 Request Fusion Energy Sciences Science,182 Total, Fusion Energy Sciences........... 266,947b 290,550 -2,906 287,644 318,950 Public Law
Science/Fusion Energy Sciences FY 2011 Congressional Budget Fusion Energy Sciences
Science/Fusion Energy Sciences FY 2011 Congressional Budget Fusion Energy Sciences Funding Profile FY 2010 Current Appropriation FY 2011 Request Fusion Energy Sciences Science 163,479 +57,399 182, Fusion Energy Sciences 394,518b +91,023 426,000 380,000 Public Law Authorizations: Public Law 95
Inside ITER seminar on History of Fusion Page 1 History of Fusion
Union thermonuclear explosion 400kT #12;Inside ITER seminar on History of Fusion Page 4 Big IvanInside ITER seminar on History of Fusion Page 1 History of Fusion Personal view V. Chuyanov 9 July 2009 Special thanks to ITER Communication Division. #12;Inside ITER seminar on History of Fusion Page 2
JJ, IAP Cambridge January 20101 Fusion Energy & ITER:Fusion Energy & ITER
JJ, IAP Cambridge January 20101 Fusion Energy & ITER:Fusion Energy & ITER: Challenges Billions ITERITER startsstarts DEMODEMO decisiondecision:: Fusion impact? Energy without greenEnergy Fusion fuel: deuterium et tritium Deuterium: plenty in the ocean Tritium: made in situ from Lithium
Pionic Fusion of Heavy Ions
We report the first experimental observation of the pionic fusion of two heavy ions. The 12C(12C,24Mg)pi0 and 12C(12C,24Na)pi+ cross sections have been measured to be 208 +/- 38 and 182 +/- 84 picobarns, respectively, at E_cm = 137 MeV. This cross section for heavy-ion pion production, at an energy just 6 MeV above the absolute energy-conservation limit, constrains possible production mechanisms to incorporate the kinetic energy of the entire projectile-target system as well as the binding energy gained in fusion.
D. Horn; G. C. Ball; D. R. Bowman; W. G. Davies; D. Fox; A. Galindo-Uribarri; A. C. Hayes; G. Savard; L. Beaulieu; Y. Larochelle; C. St-Pierre
Method for vacuum fusion bonding
An improved vacuum fusion bonding structure and process for aligned bonding of large area glass plates, patterned with microchannels and access holes and slots, for elevated glass fusion temperatures. Vacuum pumpout of all components is through the bottom platform which yields an untouched, defect free top surface which greatly improves optical access through this smooth surface. Also, a completely non-adherent interlayer, such as graphite, with alignment and location features is located between the main steel platform and the glass plate pair, which makes large improvements in quality, yield, and ease of use, and enables aligned bonding of very large glass structures.
Ackler, Harold D. (Sunnyvale, CA); Swierkowski, Stefan P. (Livermore, CA); Tarte, Lisa A. (Livermore, CA); Hicks, Randall K. (Stockton, CA)
Fusion bonding and alignment fixture
An improved vacuum fusion bonding structure and process for aligned bonding of large area glass plates, patterned with microchannels and access holes and slots, for elevated glass fusion temperatures. Vacuum pumpout of all the components is through the bottom platform which yields an untouched, defect free top surface which greatly improves optical access through this smooth surface. Also, a completely non-adherent interlayer, such as graphite, with alignment and location features is located between the main steel platform and the glass plate pair, which makes large improvements in quality, yield, and ease of use, and enables aligned bonding of very large glass structures.
Quantum Tunneling in Nuclear Fusion
Recent theoretical advances in the study of heavy ion fusion reactions below the Coulomb barrier are reviewed. Particular emphasis is given to new ways of analyzing data, such as studying barrier distributions; new approaches to channel coupling, such as the path integral and Green function formalisms; and alternative methods to describe nuclear structure effects, such as those using the Interacting Boson Model. The roles of nucleon transfer, asymmetry effects, higher-order couplings, and shape-phase transitions are elucidated. The current status of the fusion of unstable nuclei and very massive systems are briefly discussed.
Balantekin, A B
A. B. Balantekin; N. Takigawa
The automorphisms of affine fusion rings
The fusion rings associated to affine Kac-Moody algebras appear in several different contexts in math and mathematical physics. In this paper we find all automorphisms of all affine fusion rings, or equivalently the symmetries of the corresponding fusion coefficients. Most of these are directly related to symmetries of the corresponding Coxeter-Dynkin diagram. We also find all pairs of isomorphic affine fusion rings.
T. Gannon
Breakthrough: Neutron Science for the Fusion Mission
How Oak Ridge National Laboratory is helping to solve the world's energy problems through fusion energy research.
McGreevy, Robert
Fusion Energy: Visions of the Future
worldwide · X-ray/neutron applications · US teams at KSU, NSTec 2009: LPP Focus Fusion-1 lab begins
Z-Pinch Fusion for Energy Applications
Z pinches, the oldest fusion concept, have recently been revisited in light of significant advances in the fields of plasma physics and pulsed power engineering. The possibility exists for z-pinch fusion to play a role in commercial energy applications. We report on work to develop z-pinch fusion concepts, the result of an extensive literature search, and the output for a congressionally-mandated workshop on fusion energy held in Snowmass, Co July 11-23,1999.
Investigation into Fusion Feasibility of a Magnetized Target Fusion Reactor
illustrate how various material properties influence the efficiency of the design in our model setting by an imploding shell of lead-lithium. With sufficient compression, the plasma will heat to igni- tion in producing fusion is forcing the lighter particles to interact enough with each other so that they can fuse
Wetton, Brian
Culham Centre for Fusion Energy Fusion -A clean future
, scientists and engineers are working to make fusion a real option for our electricity supply.At the forefront consumption is expected to grow dramatically over the next fifty years as the world's population expands; Governments are divided over whether to include nuclear fission in their energy portfolios; and renewable
05/22/2006 12:33 PMnews @ nature.com -Chaos could keep fusion under control -A leaky magnetic bottle may prove key to making a reactor. Page 1 of 3http://www.nature.com/news/2006/060522/full/060522-2.html
) achieve its goal of generating net energy from fusion. Fusion occurs when two light elements, usually hydrogen, collide to form a new element, usually helium, releasing an enormous amount of energy and produces less long-lived radioactive waste. Scientists have worked for decades to build a fusion reactor
Nuclear Fusion: Bringing a star down to Earth
Nuclear fusion offers the potential for being a near limitless energy source by fusing together deuterium and tritium nuclei to form helium inside a plasma burning at 100 million kelvin. However, scientific and engineering challenges remain. This paper describes how such a plasma can be confined on Earth and discusses the similarities and differences with fusion in stars. It focusses on the magnetic confinement technique and, in particular, the method used in a tokamak. The confinement achieved in the equilibrium state is reviewed and it is shown how the confinement can be too good, leading to explosive instabilities at the plasma edge called Edge Localised modes (ELMs). It is shown how the impact of ELMs can be minimised by the application of magnetic perturbations and discusses the physics behind the penetration of these perturbations into what is ideally a perfect conducting plasma.
Kirk, A
Mirror-based fusion: some possible new directions
This paper examines some possible areas for the study of new approaches to fusion research, ones that employ magnetic confinement systems based on open-ended field topology and employing the magnetic mirror principle. In the spirit of encouraging a wider look at possibilities, some unconventional approaches are suggested. These approaches, involving long linear systems having ion injectors and direct converters at their ends, attempt to exploit some inherent advantages of open-ended systems for fusion. The results of analysis, calculations and preliminary cost estimates for long linear systems of this type that utilize the magnetic mirror effect to achieve their operating regimes will be presented. The approaches suggested, when examined in greater depth, may not stand the test of time, but they might encourage thinking in new areas.
Post, R F., LLNL
Fusion Rules for Affine sl(2|1;C) at Fractional Level k=-1/2
We calculate fusion rules for the admissible representations of the affine superalgebra sl(2|1;C) at fractional level k=-1/2 in the Ramond sector. By representing 3-point correlation functions involving a singular vector as the action of differential operators on the sl(2|1;C) invariant 3-point function, we obtain conditions on permitted quantum numbers involved. We find that in this case the primary fields close under fusion.
Gavin Johnstone
Fusion rules for N=2 superconformal modules
In this note we calculate the fusion coefficients for minimal series representations of the N=2 superconformal algebra by using a modified Verlinde's formula, and obtain associative and commutative fusion algebras with non-negative integral fusion coefficients at each level. Some references are added.
Minoru Wakimoto
Introduction to Fusion Energy Jerry Hughes
;Terrestrial energy sources have their origin in the nuclear fusion reactions of stars Supernova produces Earth #12;Terrestrial energy sources have their origin in the nuclear fusion reactions of stars energy sources have their origin in the nuclear fusion reactions of stars Geothermal Nuclear fission
potential as an energy source. We are looking forward to JET advancing the records for fusion power for the year 2013. The objective of fusion research is to develop power stations that harness the process that powers the sun for clean electricity generation here on earth. Fusion power stations would emit
.1. Introduction; NUCLEAR FUSION, Vol.26, No.10 (1986) 1377 #12;CONFERENCES AND SYMPOSIA 5.2. Progress. Alternative fusion concepts (AFCs); 6.1. Introduction and status; 6.2. Summary of concepts; 6.3. Conclusions; 7. Fusion nuclear technology and materials; 7.1. Progress since 1981; 7.2. Issues and R and D needs
Improved Image Fusion Using Balanced Multiwavelets
Improved Image Fusion Using Balanced Multiwavelets Lahouari Ghouti, Ahmed Bouridane and Mohammad K. Ibrahim Abstract-- This paper presents the use of balanced multi- wavelets for image fusion. The proposed image fusion scheme incorporates the use of balanced multiwavelets transform, which uses multiple
Ghouti, Lahouari
Fusion Lecture Summary Eugene S. Evans
March 31, 2010 2 / 15 #12;National Ignition Facility (NIF) location: Lawrence Livermore National. Evans (2010) Fusion Lecture Summary March 31, 2010 1 / 15 #12;Outline 1 Overview of NIF Specifications Timeline Goals 2 Inertial Confinement Fusion (ICF) 3 Science at NIF 4 Fusion and the Future Laser Inertial
Budker, Dmitry
FUSION POWER PLANTS � GOALS AND TECHNOLOGICAL CHALLENGES Farrokh Najmabadi Dept. of Electrical for fusion power plants is given and their economic, safety, and environmental features are explored. Concep- tual design studies predict that fusion power plants will be capital intensive and will be used
Najmabadi, Farrokh
Plasma Physics and Fusion Energy Miklos Porkolab
Plasma Physics and Fusion Energy Miklos Porkolab MIT Plasma Science and Fusion Center Presented at the Fusion Power Associates Annual Meeting Washington, D.C. December 2-3, 2009 Porkolab_FPA_2009 #12;Proposed is sufficient physics to make ITER a success but much more to learn for DEMO grade plasmas See review talk
Laser Fusion Energy The High Average Power
Laser Fusion Energy and The High Average Power Program John Sethian Naval Research Laboratory Dec for Inertial Fusion Energy with lasers, direct drive targets and solid wall chambers Lasers DPPSL (LLNL) Kr posters Snead Payne #12;Laser(s) Goals 1. Develop technologies that can meet the fusion energy
White Paper on Magnetic Fusion Program Strategies
of the international fusion program, the International Thermonuclear Experimental Reactor (ITER), is now halfwayWhite Paper on Magnetic Fusion Program Strategies Prepared for The President's Committee of Advisors on Science and Technology Prepared by David E. Baldwin Senior Vice President for Fusion General
Introduction to Magnetic Thermonuclear Fusion and
Introduction to Magnetic Thermonuclear Fusion and Related Research Projects Ghassan Antar Fusion 2. Research on Turbulence (Theory and Experiment) 3. Research on Disruptions 4. Research on Plasma Facing Components #12;Ghassan Y. ANTAR 3 Fusion Occurs when Two Nuclei Unite to Form One The Energy
Shihadeh, Alan
*****I* ****f?* Fusion Programme Evaluation Board
of the Community's programme in the field of Controlled Thermonuclear Fusion; to appraise the environmental, safety*****I* ****f?* Report of the Fusion Programme Evaluation Board prepared for the Commission . . . . . . . . . . . . 11 CHAPTER ONE: NUCLEAR FUSION AND ITS POTENTIAL CONTRIBUTION TO THE WORLD'S ENERGY NEEDS 1
A1.5 Fusion Performance
Analysis and radiation hydrodynamics simulations for expected high-gain fusion target performance on a demonstration 1-GWe Laser Inertial Fusion Energy (LIFE) power plant in the mid-2030s timeframe are presented. The required laser energy driver is 2.2 MJ at a 0.351-{micro}m wavelength, and a fusion target gain greater than 60 at a repetition rate of 16 Hz is the design goal for economic and commercial attractiveness. A scaling-law analysis is developed to benchmark the design parameter space for hohlraum-driven central hot-spot ignition. A suite of integrated hohlraum simulations is presented to test the modeling assumptions and provide a basis for a near-term experimental resolution of the key physics uncertainties on the National Ignition Facility (NIF). The NIF is poised to demonstrate ignition by 2012 based on the central hot spot (CHS) mode of ignition and propagating thermonuclear burn [1]. This immediate prospect underscores the imperative and timeliness of advancing inertial fusion as a carbon-free, virtually limitless source of energy by the mid-21st century to substantially offset fossil fuel technologies. To this end, an intensive effort is underway to leverage success at the NIF and to provide the foundations for a prototype 'LIFE.1' engineering test facility by {approx}2025, followed by a commercially viable 'LIFE.2' demonstration power plant operating at 1 GWe by {approx}2035. The current design goal for LIFE.2 is to accommodate {approx}2.2 MJ of laser energy (entering the high-Z radiation enclosure or 'hohlraum') at a 0.351-{micro}m wavelength operating at a repetition rate of 16 Hz and to provide a fusion target yield of 132 MJ. To achieve this design goal first requires a '0-d' analytic gain model that allows convenient exploration of parameter space and target optimization. This step is then followed by 2- and 3-dimensional radiation-hydrodynamics simulations that incorporate laser beam transport, x-ray radiation transport, atomic physics, and thermonuclear burn [2]. These simulations form the basis for assessing the susceptibility to hydrodynamic instability growth, target performance margins, laser backscatter induced by plasma density fluctuations within the hohlraum, and the threat spectrum emerging from the igniting capsule, e.g., spectra, fluences and anisotropy of the x rays and ions, for input into the chamber survivability calculations. The simulations follow the guidelines of a 'point design' methodology, which formally designates a well-defined milestone in concept development that meets established criteria for experimental testing. In Section 2, the 0-d analytic gain model to survey gain versus laser energy parameter space is discussed. Section 3 looks at the status of integrated hohlraum simulations and the needed improvements in laser-hohlraum coupling efficiency to meet the LIFE.2 threshold (net) target gain of {approx}60. Section 4 considers advanced hohlraum designs to well exceed the LIFE.2 design goal for satisfactory performance margins. We summarize in Sec. 5.
Amendt, P
Progress in the pulsed power Inertial Confinement Fusion program
Pulsed power accelerators are being used in Inertial Confinement Fusion (ICF) research. In order to achieve our goal of a fusion yield in the range of 200 - 1000 MJ from radiation-driven fusion capsules, it is generally believed that {approx}10 MJ of driver energy must be deposited within the ICF target in order to deposit {approx}1 MJ of radiation energy in the fusion capsule. Pulsed power represents an efficient technology for producing both these energies and these radiation environments in the required short pulses (few tens of ns). Two possible approaches are being developed to utilize pulsed power accelerators in this effort: intense beams of light ions and z- pinches. This paper describes recent progress in both approaches. Over the past several years, experiments have successfully answered many questions critical to ion target design. Increasing the ion beam power and intensity are our next objectives. Last year, the Particle Beam Fusion Accelerator H (PBFA II) was modified to generate ion beams in a geometry that will be required for high yield applications. This 2048 modification has resulted in the production of the highest power ion beam to be accelerated from an extraction ion diode. We are also evaluating fast magnetically-driven implosions (z-pinches) as platforms for ICF ablator physics and EOS experiments. Z-pinch implosions driven by the 20 TW Saturn accelerator have efficiently produced high x- ray power (> 75 TW) and energy (> 400 kJ). Containing these x-ray sources within a hohlraum produces a unique large volume (> 6000 mm{sup 3}), long lived (>20 ns) radiation environment. In addition to studying fundamental ICF capsule physics, there are several concepts for driving ICF capsules with these x-ray sources. Progress in increasing the x-ray power on the Saturn accelerator and promise of further increases on the higher power PBFA II accelerator will be described.
Quintenz, J.P.; Matzen, M.K.; Mehlhorn, T.A. [and others
Inertial Fusion Program. Progress report, July 1-December 31, 1979
Progress in the development of high-energy short-pulse CO/sub 2/ laser systems for fusion research is reported. Improvements in the Los Alamos National Laboratory eight-beam Helios system are described. These improvements increased the reliability of the laser and permitted the firing of 290 shots, most of which delivered energies of approximately 8 kJ to the target. Modifications to Gemini are outlined, including the installation of a new target-insertion mechanism. The redirection of the Antares program is discussed in detail, which will achieve a total energy of approximatey 40 kJ with two beams. This redirection will bring Antares on-line almost two years earlier than was possible with the full six-beam system, although at a lower energy. Experiments with isentropically imploded Sirius-B targets are discussed, and x-ray radiation-loss data from gold microballoons are presented, which show that these results are essentially identical with those obtained at glass-laser wavelengths. Significant progress in characterizing laser fusion targets is reported. New processes for fabricating glass miroballoon x-ray diagnostic targets, the application of high-quality metallic coatings, and the deposition of thick plastic coatings are described. Results in the development of x-ray diagnostics are reported, and research in the Los Alamos heavy-ion fusion program is summarized. Results of investigations of phase-conjugation research of gaseous saturable absorbers and of the use of alkali-halide crystals in a new class of saturable absorbers are summarized. New containment-vessel concepts for Inertial Confinement Fusion reactors are discussed, and results of a scoping study of four fusion-fission hybrid concepts are presented.
Skoberne, F. (comp.) [comp.
Journal of Fusion Energy, Vol. 13, Nos. 2/3, 1994 Fusion Energy Advisory Committee (FEAC): Panel 7 Report
.2. A Brief History of Heavy Ion Fusion The heavy ion fusion approach to inertial fusion energy (IFEJournal of Fusion Energy, Vol. 13, Nos. 2/3, 1994 Fusion Energy Advisory Committee (FEAC): Panel 7 Report on Inertial Fusion Energy 1 Ronald Davidson,2 Barrett Ripin, Mohamed Abdou, David E. Baldwin
Reviewers Comments on the 5th Symposium and the Status of Fusion Research 2003
Better to understand the status of fusion research in the year 2003 we will first put the research in its historical context. Fusion power research, now beginning its sixth decade of continuous effort, is unique in the field of scientific research. Unique in its mixture of pure and applied research, unique in its long-term goal and its promise for the future, and unique in the degree that it has been guided and constrained by national and international governmental policy. Though fusion research's goal has from the start been precisely defined, namely, to obtain a net release of energy from controlled nuclear fusion reactions between light isotopes (in particular those of hydrogen and helium) the difficulty of the problem has spawned in the past a very wide variety of approaches to the problem. Some of these approaches have had massive international support for decades, some have been pursued only at a ''shoestring'' level by dedicated groups in small research laboratories or universities. In discussing the historical and present status of fusion research the implications of there being two distinctly different approaches to achieving net fusion power should be pointed out. The first, and oldest, approach is the use of strong magnetic fields to confine the heated fuel, in the form of a plasma and at a density typically four or five orders of magnitude smaller than the density of the atmosphere. In steady state this fusion fuel density is still sufficient to release fusion energy at the rate of many megawatts per cubic meter. The plasma confinement times required for net energy release in this regime are long--typically a second or more, representing an extremely difficult scientific challenge --witness the five decades of research in magnetic fusion, still without having reaching that goal. The second, more recently initiated approach, is of course the ''inertial'' approach. As its name implies, the ''confinement'' problem is solved ''inertially,'' that is by compressing and heating a tiny pellet of frozen fusion fuel in nanoseconds, such that before disassembly the pellet fuses and releases its energy as a micro-explosion. The first, and most thoroughly investigated means to create this compression and heating is to use multiple laser beams, with total energies of megajoules, focused down to impinge uniformly on the pellet target. To illustrate the extreme difference between the usual magnetic confinement regime at that of inertial fusion, there are twenty orders of magnitude in fusion power density (ten orders of magnitude in plasma density) between the two regimes. In principle fusion power systems could operate at any density between these extremes, if means were to be found to exploit this possibility.
Post, R F
Particle beam fusion progress report for 1989
This report summarizes the progress on the pulsed power approach to inertial confinement fusion. In 1989, the authors achieved a proton focal intensity of 5 TW/cm{sup 2} on PBFA-II in a 15-cm-radius applied magnetic-field (applied-B) ion diode. This is an improvement by a factor of 4 compared to previous PBFA-II experiments. They completed development of the three-dimensional (3-D), electromagnetic, particle-in-cell code QUICKSILVER and obtained the first 3-D simulations of an applied-B ion diode. The simulations, together with analytic theory, suggest that control of electromagnetic instabilities could reduce ion divergence. In experiments using a lithium fluoride source, they delivered 26 kJ of lithium energy to the diode axis. Rutherford-scattered ion diagnostics have been developed and tested using a conical foil located inside the diode. They can now obtain energy density profiles by using range filters and recording ion images on nuclear track recording film. Timing uncertainties in power flow experiments on PBFA-II have been reduced by a factor of 5. They are investigating three plasma opening switches that use magnetic fields to control and confine the injected plasma. These new switches provide better power flow than the standard plasma erosion switch. Advanced pulsed-power fusion drivers will require extraction-geometry applied-B ion diodes. During this reporting period, progress was made in evaluating the generation, transport, and focus of multiple ion beams in an extraction geometry and in assessing the probable damage to a target chamber first wall.
Sweeney, M.A. [ed.] [Sandia National Labs., Albuquerque, NM (United States). Pulsed Power Sciences Center
Towards the detection of magnetohydrodynamics instabilities in a fusion reactor
Various active control strategies of the Neoclassical tearing modes are being studied in present tokamaks using established detection techniques which exploit the measurements of the fluctuations of the magnetic field and of the electron temperature. The extrapolation of such techniques to the fusion reactor scale is made problematic by the neutron fluence and by the physics conditions related to the high plasma temperature and density which degrade the spatial resolution of such measurements.
Sozzi, Carlo, E-mail: firstname.lastname@example.com; Alessi, E., E-mail: firstname.lastname@example.com; Figini, L., E-mail: email@example.com; Galperti, G., E-mail: firstname.lastname@example.com; Lazzaro, E., E-mail: email@example.com; Marchetto, C., E-mail: email@example.com; Nowak, S. [Istituto di Fisica del Plasma, CNR, EURATOM-ENEA Association, Milano (Italy); Mosconi, M. [Dipartimento di Energia, Politecnico di Milano, Milano (Italy)
Systematic quantum corrections to screening in thermonuclear fusion
We develop a series expansion of the plasma screening length away from the classical limit in powers of $\\hbar^{2}$. It is shown that the leading order quantum correction increases the screening length in solar conditions by approximately 2% while it decreases the fusion rate by approximately $ 0.34%$. We also calculate the next higher order quantum correction which turns out to be approximately 0.05%.
Shirish M. Chitanvis
Chitanvis, S M
Fusion Test Facilities John Sheffield
Fusion Test Facilities John Sheffield ISSE - University of Tennessee FPA meeting Livermore December Stambaugh, and their colleagues #12;Destructive Testing · It is common practice to test engineered components to destruction prior to deployment of a system e.g., - Automobile crash tests - Airplane wing
Fusion Ignition Research Experiment Highlights
objectives for FIRE are to address the critical burning plasma issues of an attractive magnetic fusion power plant as envisioned by the Advanced Reactor Innovation Evaluation Studies (ARIES). The FIRE Design study. institutions, and is managed through the Virtual Laboratory for Technology. The technical work on FIRE has been
Third Edition, Gene Fusion System
. Small-Scale Isolation of pGEX DNA .... 9 6. Large-Scale Isolation of pGEX DNA .... 9 Notes on Sequencing ....................................................... 2 pGEX Vectors ............................................. 2 Purification Modules. Screening pGEX Vectors with PCR ..... 10 Purification of GST Fusion Proteins.. 11 8. Preparation
Lai, Zhi-Chun
Fusion Engineering and Design 4950 (2000) 689695 ARIES-ST breeding blanket design and analysis
. The power core uses an advanced `dual-cooled' breeding blanket with flowing PbLi breeder and He efficiency in the power conversion system can not be achieved with solid breeder blankets irrespectiveFusion Engineering and Design 49�50 (2000) 689�695 ARIES-ST breeding blanket design and analysis
Pulsifer, John
OPTIONS FOR A STEADY-STATE COMPACT FUSION NEUTRON SOURCE M.P. Gryaznevich1
) Nuclear Power production: the emerging shortage of fissile fuel, disposal and storage of nuclear waste. This can be achieved in several ways: by recycling high level nuclear waste from conventional nuclear of nuclear waste and fuel and removing Pu from the spent fuel. This combination of "fission + fusion
Fusion Rules for the q-deformed Vertex Operators of U_q(sl(2)^)
We analyze the properties of the q-vertex operators of U_q(sl(2)^) introduced by Frenkel and Reshetikhin. As the condition for the null vector decoupling, we derive the existence condition of the q-vertex operators ( the fusion rules ).
H. Awata; Y. Yamada
The National Ignition Facility: The Path to Ignition, High Energy Density Science and Inertial Fusion Energy
The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory (LLNL) in Livermore, CA, is a Nd:Glass laser facility capable of producing 1.8 MJ and 500 TW of ultraviolet light. This world's most energetic laser system is now operational with the goals of achieving thermonuclear burn in the laboratory and exploring the behavior of matter at extreme temperatures and energy densities. By concentrating the energy from its 192 extremely energetic laser beams into a mm{sup 3}-sized target, NIF can produce temperatures above 100 million K, densities of 1,000 g/cm{sup 3}, and pressures 100 billion times atmospheric pressure - conditions that have never been created in a laboratory and emulate those in the interiors of planetary and stellar environments. On September 29, 2010, NIF performed the first integrated ignition experiment which demonstrated the successful coordination of the laser, the cryogenic target system, the array of diagnostics and the infrastructure required for ignition. Many more experiments have been completed since. In light of this strong progress, the U.S. and the international communities are examining the implication of achieving ignition on NIF for inertial fusion energy (IFE). A laser-based IFE power plant will require a repetition rate of 10-20 Hz and a 10% electrical-optical efficiency laser, as well as further advances in large-scale target fabrication, target injection and tracking, and other supporting technologies. These capabilities could lead to a prototype IFE demonstration plant in 10- to 15-years. LLNL, in partnership with other institutions, is developing a Laser Inertial Fusion Energy (LIFE) baseline design and examining various technology choices for LIFE power plant This paper will describe the unprecedented experimental capabilities of the NIF, the results achieved so far on the path toward ignition, the start of fundamental science experiments and plans to transition NIF to an international user facility providing access to researchers around the world. The paper will conclude with a discussion of LIFE, its development path and potential to enable a carbon-free clean energy future.
Security on the US Fusion Grid
The National Fusion Collaboratory project is developing and deploying new distributed computing and remote collaboration technologies with the goal of advancing magnetic fusion energy research. This work has led to the development of the US Fusion Grid (FusionGrid), a computational grid composed of collaborative, compute, and data resources from the three large US fusion research facilities and with users both in the US and in Europe. Critical to the development of FusionGrid was the creation and deployment of technologies to ensure security in a heterogeneous environment. These solutions to the problems of authentication, authorization, data transfer, and secure data storage, as well as the lessons learned during the development of these solutions, may be applied outside of FusionGrid and scale to future computing infrastructures such as those for next-generation devices like ITER.
Burruss, Justin R.; Fredian, Tom W.; Thompson, Mary R.
Data security on the national fusion grid
Burruss, Justine R.; Fredian, Tom W.; Thompson, Mary R.
aml1-eto fusion protein: Topics by E-print Network
antibody-photosensitizer fusion protein: Topics by E-print Network
antibody-gdnf fusion protein: Topics by E-print Network
akar2-akap12 fusion protein: Topics by E-print Network
E-Print Network 3.0 - advanced fusion material Sample Search...
Physics and Fusion 5 Fusion Energy Program Presentation to Summary: International Thermonuclear Experimental Reactor Plasma Technologies Fusion Technologies Advanced Materials......
E-Print Network 3.0 - advanced deuterium fusion Sample Search...
Physics and Fusion 2 Fusion Energy Program Presentation to Summary: International Thermonuclear Experimental Reactor Plasma Technologies Fusion Technologies Advanced Materials......
Magneto-Inertial Fusion (Magnetized Target Fusion)( g g )
National Security, LLC for the DOE/NNSA Slide 1 LA-UR-11-01898 #12;Some Observations An economic for the DOE/NNSA 2 #12;Magneto-inertial fusion: Part of a plan B · May allow more efficient drivers, lower Operated by the Los Alamos National Security, LLC for the DOE/NNSA Slide 3 #12;A Wide Range of Driver
Lithium As Plasma Facing Component for Magnetic Fusion Research
The use of lithium in magnetic fusion confinement experiments started in the 1990's in order to improve tokamak plasma performance as a low-recycling plasma-facing component (PFC). Lithium is the lightest alkali metal and it is highly chemically reactive with relevant ion species in fusion plasmas including hydrogen, deuterium, tritium, carbon, and oxygen. Because of the reactive properties, lithium can provide strong pumping for those ions. It was indeed a spectacular success in TFTR where a very small amount (~ 0.02 gram) of lithium coating of the PFCs resulted in the fusion power output to improve by nearly a factor of two. The plasma confinement also improved by a factor of two. This success was attributed to the reduced recycling of cold gas surrounding the fusion plasma due to highly reactive lithium on the wall. The plasma confinement and performance improvements have since been confirmed in a large number of fusion devices with various magnetic configurations including CDX-U/LTX (US), CPD (Japan), HT-7 (China), EAST (China), FTU (Italy), NSTX (US), T-10, T-11M (Russia), TJ-II (Spain), and RFX (Italy). Additionally, lithium was shown to broaden the plasma pressure profile in NSTX, which is advantageous in achieving high performance H-mode operation for tokamak reactors. It is also noted that even with significant applications (up to 1,000 grams in NSTX) of lithium on PFCs, very little contamination (< 0.1%) of lithium fraction in main fusion plasma core was observed even during high confinement modes. The lithium therefore appears to be a highly desirable material to be used as a plasma PFC material from the magnetic fusion plasma performance and operational point of view. An exciting development in recent years is the growing realization of lithium as a potential solution to solve the exceptionally challenging need to handle the fusion reactor divertor heat flux, which could reach 60 MW/m2 . By placing the liquid lithium (LL) surface in the path of the main divertor heat flux (divertor strike point), the lithium is evaporated from the surface. The evaporated lithium is quickly ionized by the plasma and the ionized lithium ions can provide a strongly radiative layer of plasma ("radiative mantle"), thus could significantly reduce the heat flux to the divertor strike point surfaces, thus protecting the divertor surface. The protective effects of LL have been observed in many experiments and test stands. As a possible reactor divertor candidate, a closed LL divertor system is described. Finally, it is noted that the lithium applications as a PFC can be quite flexible and broad. The lithium application should be quite compatible with various divertor configurations, and it can be also applied to protecting the presently envisioned tungsten based solid PFC surfaces such as the ones for ITER. Lithium based PFCs therefore have the exciting prospect of providing a cost effective flexible means to improve the fusion reactor performance, while providing a practical solution to the highly challenging divertor heat handling issue confronting the steadystate magnetic fusion reactors.
Masayuki Ono
Laser fusion neutron source employing compression with short pulse lasers
A method and system for achieving fusion is provided. The method includes providing laser source that generates a laser beam and a target that includes a capsule embedded in the target and filled with DT gas. The laser beam is directed at the target. The laser beam helps create an electron beam within the target. The electron beam heats the capsule, the DT gas, and the area surrounding the capsule. At a certain point equilibrium is reached. At the equilibrium point, the capsule implodes and generates enough pressure on the DT gas to ignite the DT gas and fuse the DT gas nuclei.
Sefcik, Joseph A; Wilks, Scott C
Chamber technology concepts for inertial fusion energy: Three recent examples
The most serious challenges in the design of chambers for inertial fusion energy (IFE) are 1) protecting the first wall from fusion energy pulses on the order of several hundred megajoules released in the form of x rays, target debris, and high energy neutrons, and 2) operating the chamber at a pulse repetition rate of 5-10 Hz (i.e., re-establishing, the wall protection and chamber conditions needed for beam propagation to the target between pulses). In meeting these challenges, designers have capitalized on the ability to separate the fusion burn physics from the geometry and environment of the fusion chamber. Most recent conceptual designs use gases or flowing liquids inside the chamber. Thin liquid layers of molten salt or metal and low pressure, high-Z gases can protect the first wall from x rays and target debris, while thick liquid layers have the added benefit of protecting structures from fusion neutrons thereby significantly reducing the radiation damage and activation. The use of thick liquid walls is predicted to 1) reduce the cost of electricity by avoiding the cost and down time of changing damaged structures, and 2) reduce the cost of development by avoiding the cost of developing a new, low-activation material. Various schemes have been proposed to assure chamber clearing and renewal of the protective features at the required pulse rate. Representative chamber concepts are described, and key technical feasibility issues are identified for each class of chamber. Experimental activities (past, current, and proposed) to address these issues and technology research and development needs are discussed.
Meier, W.R.; Moir, R.W. [Lawrence Livermore National Lab., CA (United States); Abdou, M.A. [California Univ., Los Angeles, CA (United States)
Fusion of \\ade Lattice Models
Fusion hierarchies of \\ade face models are constructed. The fused critical $D$, $E$ and elliptic $D$ models yield new solutions of the Yang-Baxter equations with bond variables on the edges of faces in addition to the spin variables on the corners. It is shown directly that the row transfer matrices of the fused models satisfy special functional equations. Intertwiners between the fused \\ade models are constructed by fusing the cells that intertwine the elementary face weights. As an example, we calculate explicitly the fused $2\\times 2$ face weights of the 3-state Potts model associated with the $D_4$ diagram as well as the fused intertwiner cells for the $A_5$--$D_4$ intertwiner. Remarkably, this $2\\times 2$ fusion yields the face weights of both the Ising model and 3-state CSOS models.
Yu-kui Zhou; Paul A. Pearce
Fusion rules of chiral algebras
Recently (hep-th/9307183) we showed that for the case of the WZW- and the minimal models fusion can be understood as a certain ring-like tensor product of the symmetry algebra. In this paper we generalize this analysis to arbitrary chiral algebras. We define the tensor product of conformal field theory in the general case and prove that it is associative and symmetric up to equivalence. We also determine explicitly the action of the chiral algebra on this tensor product. In the second part of the paper we demonstrate that this framework provides a powerful tool for calculating restrictions for the fusion rules of chiral algebras. We exhibit this for the case of the $W_{3}$-algebra and the $N=1$ and $N=2$ NS superconformal algebras.
M. Gaberdiel
Uranium resources and their implications for fission breeder and fusion hybrid development
Present estimates of uranium resources and reserves in the US and the non-Communist world are reviewed. The resulting implications are considered for two proposed breeder technologies: the liquid metal fast breeder reactor (LMFBR) and the fusion hybrid reactor. Using both simple arguments and detailed scenarios from the published literature, conditions are explored under which the LMFBR and fusion hybrid could respectively have the most impact, considering both fuel-supply and economic factors. The conclusions emphasize strong potential advantages of the fusion hybrid, due to its inherently large breeding rate. A discussion is presented of proposed US development strategies for the fusion hybrid, which at present is far behind the LMFBR in its practical application and maturity.
Max, C.E.
Paramyxovirus fusion: Real-time measurement of parainfluenza virus 5 virus-cell fusion
Although cell-cell fusion assays are useful surrogate methods for studying virus fusion, differences between cell-cell and virus-cell fusion exist. To examine paramyxovirus fusion in real time, we labeled viruses with fluorescent lipid probes and monitored virus-cell fusion by fluorimetry. Two parainfluenza virus 5 (PIV5) isolates (W3A and SER) and PIV5 containing mutations within the fusion protein (F) were studied. Fusion was specific and temperature-dependent. Compared to many low pH-dependent viruses, the kinetics of PIV5 fusion was slow, approaching completion within several minutes. As predicted from cell-cell fusion assays, virus containing an F protein with an extended cytoplasmic tail (rSV5 F551) had reduced fusion compared to wild-type virus (W3A). In contrast, virus-cell fusion for SER occurred at near wild-type levels, despite the fact that this isolate exhibits a severely reduced cell-cell fusion phenotype. These results support the notion that virus-cell and cell-cell fusion have significant differences.
Connolly, Sarah A. [Howard Hughes Medical Institute, Northwestern University, Evanston, IL 60208-3500 (United States); Lamb, Robert A. [Howard Hughes Medical Institute, Northwestern University, Evanston, IL 60208-3500 (United States) and Department of Biochemistry, Molecular Biology, and Cell Biology, Northwestern University, Evanston, IL 60208-3500 (United States)]. E-mail: email@example.com
Progress with developing a target for magnetized target fusion
Magnetized Target Fusion (MTF) is an approach to fusion where a preheated and magnetized plasma is adiabatically compressed to fusion conditions. Successful MTF requires a suitable initial target plasma with an embedded magnetic field of at least 5 T in a closed-field-line topology, a density of roughly 10{sup 18} cm{sup {minus}3}, a temperature of at least 50 eV, and must be free of impurities which would raise radiation losses. Target plasma generation experiments are underway at Los Alamos National Laboratory using the Colt facility; a 0.25 MJ, 2--3 {micro}s rise-time capacitor bank. The goal of these experiments is to demonstrate plasma conditions meeting the minimum requirements for a MTF initial target plasma. In the first experiments, a Z-pinch is produced in a 2 cm radius by 2 cm high conducting wall using a static gas-fill of hydrogen or deuterium gas in the range of 0.5 to 2 torr. Thus far, the diagnostics include an array of 12 B-dot probes, framing camera, gated OMA visible spectrometer, time-resolved monochrometer, filtered silicon photodiodes, neutron yield, and plasma-density interferometer. These diagnostics show that a plasma is produced in the containment region that lasts roughly 10 to 20 {micro}s with a maximum plasma density exceeding 10{sup 18} cm{sup {minus}3}. The experimental design and data are presented.
Wysocki, F.J.; Chrien, R.E.; Idzorek, G.; Oona, H.; Whiteson, D.O.; Kirkpatrick, R.C.; Lindemuth, I.R.; Sheehey, P.T.
Studies at the Pacific Northwest National Laboratory in Richland, Washington, are being conducted to evaluate nondestructive examination approaches for inspecting butt fusion joints in high density polyethylene (HDPE) pipe for lack of fusion (LOF). The work provides information to the United States Nuclear Regulatory Commission on the effectiveness and need for volumetric inspection techniques of HDPE butt fusion joints in Section III, Division 1, Class 3, buried piping systems in nuclear power plants. This paper describes results from preliminary assessments using ultrasonic nondestructive techniques and high-speed tensile impact testing for determining joint integrity. A series of butt joints were fabricated in 3408, 12-inch IPS DR-11 material by varying the fusion parameters in attempts to provide good joints and joints containing LOF. These butt joints were visually examined and volumetrically examined with time-of-flight diffraction (TOFD) and phased-array (PA) ultrasound. A limited subset of pipe joint material was destructively analyzed by either slicing through the joint and visually examining the surface or by employing a standard high-speed tensile impact test. Initial correlation of the fusion parameters, nondestructive, and destructive evaluations have shown that areas with gross LOF were detected with both TOFD and PA ultrasound and that the tensile impact test showed a brittle failure at the joint. There is still some ambiguity in results from the less obvious LOF conditions. Current work is targeted on assessing the sensitivity of the ultrasonic volumetric examinations and validating the results with a destructive analysis. It is expected that on-going and future work will lead to quantifying the ultrasonic responses in terms of joint integrity.
Crawford, Susan L.; Doctor, Steven R.; Cinson, Anthony D.; Cumblidge, Stephen E.; Anderson, Michael T.
Inertial fusion energy: A clearer view of the environmental and safety perspectives
If fusion energy is to achieve its full potential for safety and environmental (S&E) advantages, the S&E characteristics of fusion power plant designs must be quantified and understood, and the resulting insights must be embodied in the ongoing process of development of fusion energy. As part of this task, the present work compares S&E characteristics of five inertial and two magnetic fusion power plant designs. For each design, a set of radiological hazard indices has been calculated with a system of computer codes and data libraries assembled for this purpose. These indices quantify the radiological hazards associated with the operation of fusion power plants with respect to three classes of hazard: accidents, occupational exposure, and waste disposal. The three classes of hazard have been qualitatively integrated to rank the best and worst fusion power plant designs with respect to S&E characteristics. From these rankings, the specific designs, and other S&E trends, design features that result in S&E advantages have been identified. Additionally, key areas for future fusion research have been identified. Specific experiments needed include the investigation of elemental release rates (expanded to include many more materials) and the verification of sequential charged-particle reactions. Improvements to the calculational methodology are recommended to enable future comparative analyses to represent more accurately the radiological hazards presented by fusion power plants. Finally, future work must consider economic effects. Trade-offs among design features will be decided not by S&E characteristics alone, but also by cost-benefit analyses. 118 refs., 35 figs., 35 tabs.
Latkowski, J.F.
M. Abdou April 2013 Fusion Nuclear Science and Technology
M. Abdou April 2013 Fusion Nuclear Science and Technology Challenges and Required R&D Mohamed Fusion Nuclear Science and Technology Challenges and Required R&D Presentation Outline Introduction to the Fusion Nuclear Environment and Fusion Nuclear Components FNST R&D Challenges Need for Fusion Nuclear
Course: FUSION SCIENCE AND ENGINEERING Universit degli Studi di Padova
the subject of controlled thermonuclear fusion in magnetically confined plasmas. Both fusion science of Controlled Thermonuclear Fusion, b) Engineering of a Magnetically Confined Fusion Reactor, c) ExperimentalCourse: FUSION SCIENCE AND ENGINEERING Università degli Studi di Padova in agreement
Cesare, Bernardo
Diamond neutral particle spectrometer for fusion reactor ITER
A compact diamond neutral particle spectrometer with digital signal processing has been developed for fast charge-exchange atoms and neutrons measurements at ITER fusion reactor conditions. This spectrometer will play supplementary role for Neutral Particle Analyzer providing 10 ms time and 30 keV energy resolutions for fast particle spectra in non-tritium ITER phase. These data will also be implemented for independent studies of fast ions distribution function evolution in various plasma scenarios with the formation of a single fraction of high-energy ions. In tritium ITER phase the DNPS will measure 14 MeV neutrons spectra. The spectrometer with digital signal processing can operate at peak counting rates reaching a value of 10{sup 6} cps. Diamond neutral particle spectrometer is applicable to future fusion reactors due to its high radiation hardness, fast response and high energy resolution.
Krasilnikov, V.; Amosov, V.; Kaschuck, Yu.; Skopintsev, D. [Institution PROJECT CENTER ITER, 1, Akademik Kurchatov Sq., Moscow (Russian Federation)
Fusion Nuclear Science Pathways Assessment
With the strong commitment of the US to the success of the ITER burning plasma mission, and the project overall, it is prudent to consider how to take the most advantage of this investment. The production of energy from fusion has been a long sought goal, and the subject of several programmatic investigations and time line proposals [1]. The nuclear aspects of fusion research have largely been avoided experimentally for practical reasons, resulting in a strong emphasis on plasma science. Meanwhile, ITER has brought into focus how the interface between the plasma and engineering/technology, presents the most challenging problems for design. In fact, this situation is becoming the rule and no longer the exception. ITER will demonstrate the deposition of 0.5 GW of neutron heating to the blanket, deliver a heat load of 10-20 MW/m2 or more on the divertor, inject 50-100 MW of heating power to the plasma, all at the expected size scale of a power plant. However, in spite of this, and a number of other technologies relevant power plant, ITER will provide a low neutron exposure compared to the levels expected to a fusion power plant, and will purchase its tritium entirely from world reserves accumulated from decades of CANDU reactor operations. Such a decision for ITER is technically well founded, allowing the use of conventional materials and water coolant, avoiding the thick tritium breeding blankets required for tritium self-sufficiency, and allowing the concentration on burning plasma and plasma-engineering interface issues. The neutron fluence experienced in ITER over its entire lifetime will be ~ 0.3 MW-yr/m2, while a fusion power plant is expected to experience 120-180 MW-yr/m2 over its lifetime. ITER utilizes shielding blanket modules, with no tritium breeding, except in test blanket modules (TBM) located in 3 ports on the midplane [2], which will provide early tests of the fusion nuclear environment with very low tritium production (a few g per year).
C.E. Kessel, et. al.
Is Fusion Inhibited for Weakly Bound Nuclei?
Complete fusion of light radioactive nuclei is predicted to be hindered at near-barrier energies. This feature is investigated in the case of the least bound stable nuclei. Evaporation residues resulting from the {sup 6,7}Li+{sup 9}Be and {sup 6,7}Li+{sup 12}C fusion reactions have been measured in order to study common features in reactions involving light weakly bound nuclei. The experimental excitation functions revealed that the fusion cross section is significantly smaller than the total reaction cross section and also smaller than the fusion cross section expected from the available systematics. A clear correlation between the fusion probability and nucleon (cluster) separation energy has been established.The results suggest that the breakup process has a strong influence on the hindrance of the fusion cross section. {copyright} {ital 1996} {ital The American Physical Society}
Takahashi, J.; Munhoz, M.; Szanto, E.M.; Carlin, N.; Added, N.; Suaide, A.A.; de Moura, M.M.; Liguori Neto, R.; Szanto de Toledo, A. [Universidade de Sao Paulo, Institute de Fisica, Departamento de Fisica Nuclear, Caixa Postal 66318, 05389-970 Sao Paulo, Sao Paulo, (Brasil)] [Universidade de Sao Paulo, Institute de Fisica, Departamento de Fisica Nuclear, Caixa Postal 66318, 05389-970 Sao Paulo, Sao Paulo, (Brasil); Canto, L.F. [Instituto de Fisica, Universidade Federal do Rio de Janeiro, Caixa Postal 68528, 21945-970 Rio de Janeiro, RJ, (Brasil)] [Instituto de Fisica, Universidade Federal do Rio de Janeiro, Caixa Postal 68528, 21945-970 Rio de Janeiro, RJ, (Brasil)
Fusion: an energy source for synthetic fuels
The decreasing availability of fossil fuels emphasizes the need to develop systems which will produce synthetic fuel to substitute for and supplement the natural supply. An important first step in the synthesis of liquid and gaseous fuels is the production of hydrogen. Thermonuclear fusion offers an inexhaustible source of energy for the production of hydrogen from water. Depending on design, electric generation efficiencies of approx. 40 to 60% and hydrogen production efficiencies by high temperature electrolysis of approx. 50 to 70% are projected for fusion reactors using high temperature blankets. Fusion/coal symbiotic systems appear economically promising for the first generation of commercial fusion synfuels plants. Coal production requirements and the environmental effects of large-scale coal usage would be greatly reduced by a fusion/coal system. In the long term, there could be a gradual transition to an inexhaustible energy system based solely on fusion.
Fillo, J A; Powell, J; Steinberg, M
Perspectives on a Constrained Fusion Ten-Year Fusion Program (Comments on FESAC charge #2)
roadmap to a demonstration power plant. It is imperative that the US program, stellarators, next-step planning activities, spherical tokamaks, and fusion simulation), and harnessing fusion power (surviving neutron fluxes, producing tritium and heat
Fusion reactor blanket-main design aspects
The main function of the fusion reactor blanket is ensuring tritium breeding and radiation shield. The blanket version depends on the reactor type (experimental, DEMO, commercial) and its parameters. Blanket operation conditions are defined with the heat flux, neutron load/fluence, cyclic operation, dynamic heating/force loading, MHD effects etc. DEMO/commercial blanket design is distinguished e.g. by rather high heat load and neutron fluence - up to 100 W/cm{sup 2} and 7 MWa/m{sup 2} accordingly. This conditions impose specific requirements for the materials, structure, maintenance of the blanket and its most loaded components - FW and limiter. The liquid Li-Pb eutectic is one of the possible breeder for different kinds of blanket in view of its advantages one of which is the blanket convertibility that allow to have shielding blanket (borated water) or breeding one (Li-Pb eutectic). Using Li-Pb eutectic for both ITER and DEMO blankets have been considered. In the conceptual ITER design the solid eutectic blanket was carried out. The liquid eutectic breeder/coolant is suggested also for the advanced (high parameter) blanket.
Strebkov, Yu.; Sidorov, A.; Danilov, I. [Research and Development Inst. of Power Engineering, Moscow (Russian Federation)
Achieving Airtight Ducts in Manufactured Housing
correlated with achieving CFM25OUT=3% in mastic sealed systems, but less reliably with taped systems. Cost for achieving duct tightness goals range from $4 to $8 including duct testing on the assembly line...
McIlvaine, J.; Beal, D.; Moyer, N.; Chasar, D.; Chandra, S.
| International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 54 (2014) 033008 (8pp) doi:10.1088/0029-5515/54/3/033008
localized modes (ELMs) or plasma disruptions [1, 2], the high thermal energy can be deposited on localized areas of plasma- facing components (PFC) in fusion devices [3, 4]. Among high-Z materials, pure tungsten (W) demonstrates the highest resistance against thermal loads under plasma disruption conditions
Harilal, S. S.
Achieving and Demonstrating Vehicle Technologies Engine Fuel...
Broader source: Energy.gov (indexed) [DOE]
Engine Fuel Efficiency Milestones Achieving and Demonstrating Vehicle Technologies Engine Fuel Efficiency Milestones 2009 DOE Hydrogen Program and Vehicle Technologies...
Scale Demonstration of Smart Manufacturing Achieving Transformational Energy Productivity Gains Development of an Open Architecture, Widely Applicable Smart Manufacturing...
Some Calculations for Cold Fusion Superheavy Elements
The Q value and optimal exciting energy of the hypothetical superheavy nuclei in cold fusion reaction are calculated with relativistic mean field model and semiemperical shell model mass equation(SSME) and the validity of the two models is tested. The fusion barriers are also calculated with two different models and reasonable results are obtained. The calculations can give useful references for the experiments in the superheavy nuclei synthesized in cold fusion reactions.
Zhong, X H; Ning, P Z
X. H. Zhong; L. Li; P. Z. Ning
Cold nuclear fusion and muon-catalyzed fusion. (Latest citations from the INSPEC database). Published Search
The bibliography contains citations concerning a nuclear fusion process which occurs at lower temperatures and pressures than conventional fusion reactions. The references describe theoretical and experimental results for a proposed muon-catalyzed fusion reactor, and for studies on muon sticking and reactivation. The temperature dependence of fusion rates, and resolution of some engineering challenges are also discussed. (Contains 250 citations and includes a subject term index and title list.)
Nuclear Fusion: A Solution to the GlobalNuclear Fusion: A Solution to the Global Energy CrisisEnergy Crisis
Nuclear Fusion: A Solution to the GlobalNuclear Fusion: A Solution to the Global Energy email@example.com Introduction and Motivation What is Nuclear Fusion? Laser Plasma Interactions The world, and particularly is harnessing the power of nuclear fusion. It is however, extremely difficult to sustain a fusion reaction
Strathclyde, University of
Journal of Fusion Energy, Vol. 18, No. 4, 1999 Report of the FEAC Inertial Fusion Energy Review Panel
participation in the of the Fusion Energy Sciences Program of the Office of International Thermonuclear ReactorJournal of Fusion Energy, Vol. 18, No. 4, 1999 Report of the FEAC Inertial Fusion Energy Review. S. Department of Energy Fusion Energy Advisory Committee (FEAC) review of its Inertial Fusion Energy
On the classification of fusion rings
The fusion rules and modular matrix of a rational conformal field theory obey a list of properties. We use these properties to classify rational conformal field theories with not more than six primary fields and small values of the fusion coefficients. We give a catalogue of fusion rings which can arise for these field theories. It is shown that all such fusion rules can be realized by current algebras. Our results support the conjecture that all rational conformal field theories are related to current algebras.
D. Gepner; A. Kapustin
Fusion Rings Related to Affine Weyl Groups
The construction of the fusion ring of a quasi-rational CFT based on $\\hat{sl}(3)_k$ at generic level $k\
P. Furlan; V. B. Petkova
Method of controlling fusion reaction rates
This invention relates to a method of controlling the reaction rates in a nuclear fusion reactor; and more particularly, to the use of polarized nuclear fuel.
Kulsrud, R.M.; Furth, H.P.; Valeo, E.J.; Goldhaber, M.
Cavitation-Induced Fusion: Proof of Concept
Cavitation-induced fusion (also known as bubble fusion or sonofusion) has been a topic of much debate and controversy and is generally (albeit incorrectly) perceived as unworkable. In this paper we present the theoretical foundations of cavitation-induced fusion and summarize the experimental results of the research conducted in the past 20 years. Based on the systematic study of all available data we conclude that the cavitation-induced fusion is feasible, doable, and can be used for commercial power generation. We present the results of our own research and disclose a commercial reactor prototype.
Max I. Fomitchev-Zamilov
PPPL Races Ahead with Fusion Research
Princeton Plasma Physics Laboratory. A Collaborative National Center for Fusion & Plasma Research. All rights reserved. NONDISCRIMINATION STATEMENT In compliance with Title IX of...
Science/Fusion Energy Sciences FY 2008 Congressional Budget Fusion Energy Sciences
. Benefits Total world energy consumption has increased by more than 50% during the past 25 years, and given,182 31,317 Total, Fusion Energy Sciences 280,683a 318,950 427,850 Public Law Authorizations: Public LawScience/Fusion Energy Sciences FY 2008 Congressional Budget Fusion Energy Sciences Funding Profile
The Heavy Ion Fusion Virtual National Laboratory The Heavy Ion Path to Fusion Energy
-consistent power plant design for a multi- beam induction linac, final focus and chamber propagationThe Heavy Ion Fusion Virtual National Laboratory The Heavy Ion Path to Fusion Energy Grant Logan Director Heavy-Ion Fusion Virtual National Laboratory Presented to FESAC Workshop on Development Paths
Strengthening and AcceleratingStrengthening and Accelerating the Development of Fusion Powerthe Development of Fusion Power
Development of Fusion Power Chris Llewellyn Smith Director, UKAEA Culham Chairman Consultative Committee) people of the importance of developing fusion as (potentially) an environmentally responsible source (used to fuel a fusion power station) 200,000 KW-hrs = (total US electricity production for 15 years
Fusion Power Associates Annual Meeting and Symposium Fusion Energy: Preparing for the NIF and ITER Era
Fusion Power Associates Annual Meeting and Symposium Fusion Energy: Preparing for the NIF and ITER of Directors 8:20 Presentation of Awards S. Dean, President, FPA 8:30 Fusion at the Department of Energy Technology Program Stan Milora, ORNL 1:40 Issues and Opportunities from ITER Review R. Hawryluk, PPPL 2
A Strategic Program Plan for Fusion Energy Sciences Fusion Energy Sciences
, while creating manageable waste and little risk to public safety and health. Making fusion energy a part light atoms such as those of hydrogen, holds great promise for clean and abundant energy produc- tionA Strategic Program Plan for Fusion Energy Sciences 1 Fusion Energy Sciences #12;2 Bringing
Measurement of limiter heating due to fusion product losses during high fusion power deuterium-tritium operation of TFTR
Preliminary analysis has been completed on measurements of limiter heating during high fusion power deuterium-tritium (D-T) operation of TFTR, in an attempt to identify heating from alpha particle losses. Recent operation of TFTR with a 50-50 mix of D-T has resulted in fusion power output ({approx} 6.2 MW) orders of magnitude above what was previously achieved on TFTR. A significantly larger absolute number of particles and energy from fusion products compared to D-D operation is expected to be lost to the limiters. Measurements were made in the vicinity of the midplane ({plus_minus} 30{degree}) with thermocouples mounted on the tiles of an outboard limiter. Comparisons were made -between discharges which were similar except for the mix of deuterium and tritium beam sources. Power and energy estimates of predicted alpha losses were as high as 0.13 MW and 64 kJ. Depending on what portion of the limiters absorbed this energy, temperature rises of up to 42 {degrees}C could be expected, corresponding to a heat load of 0.69 MJ/m{sup 2} over a 0.5 sec period, or a power load of 1.4 MW/m{sup 2}. There was a measurable increase in the limiter tile temperature as the fusion power yield increased with a more reactive mixture of D and T at constant beam power during high power D-T operation. Analysis of the data is being conducted to see if the alpha heating component can be extracted. Measured temperature increases were no greater than 1 {degree}C, indicating that there was probably neither an unexpectedly large fraction of lost particles nor unexpected localization of the losses. Limits on the stochastic ripple loss contribution from alphas can be deduced.
Janos, A.; Owens, D.K.; Darrow, D.; Redi, M.; Zarnstorff, M.; Zweben, S.
Overview of Recent Japanese Activities in Fusion Technology
After the ITER/EDA study, Japanese activities in fusion technology have been mainly devoted to DEMO reactors. The paper intends to overview these activities.With respect to the test blanket modules, solid breeder blankets with ferritic steel structure cooled by helium and water are being developed by JAERI in cooperation with universities and NIFS. Advanced blankets are being developed by universities and NIFS. In the area of tritium processing technology, R and D has been focused on the blanket tritium recovery technology. In terms of the superconducting magnet, JAERI has performed basic research for the Fusion Power Demonstration Plant, aiming at realization of toroidal filed higher than 13 T using innovative superconductors, such as Nb{sub 3}Al and High Temperature Superconductors (HTS). In the R and D of negative ion based NBI technologies, a H{sup -} beam of 110 mA has been stably accelerated up to 0.9 MeV, which corresponds to the current density of 80 A/m{sup 2}. A beam power of 13.1 MW at 180 keV has been injected from three injectors in the LHD N-NBI. With respect to the radio-frequency heating technology, development of 170GHz ITER gyrotron has been progressed to achieve a 500kW for 100 sec operation in JAERI. Long pulse injection for 766 sec with 72 kW at 84 GHz was achieved in a LHD ECH experiment.
Seki, Masahiro [Japan Atomic Energy Research Institute (Japan); Yamamoto, I. [Nagoya University (Japan); Sagara, A. [NIFS (Japan)
Differential Regulation of Granule-to-Granule and Granule-to-Plasma Membrane Fusion during Secretion from Rat Pituitary Lactotrophs
Abstract. We used fluorescence imaging of individual exocytic events together with electron microscopy to study the regulation of dense core granule-to-plasma membrane fusion and granule-to-granule fusion events that occur during secretion from rat pituitary lactotrophs. Stimulating secretion with elevated extracellular potassium, with the calcium ionophore ionomycin, or with thyrotropin releasing hormone or vasoactive intestinal polypeptide resulted in abundant exocytic structures. Approximately 67 % of these structures consisted of multiple granules fused together sharing a single exocytic opening with the plasma membrane, i.e., compound exocytosis. For all of these stimulation conditions there appeared to be a finite number of plasma membrane fusion sites, ?11 sites around each cellular equator. However, a granule could fuse directly with another granule that had already fused with the plasma membrane even before all plasma membrane sites were occupied. Granule-to-plasma membrane and granuleto-granule fusion events were subject to different regulations. Forskolin, which can elevate cAMP, increased the number of granule-to-granule fusion events without altering the number of granule-to-plasma membrane fusion events. In contrast, the phorbol ester PMA, which activates protein kinase C increased both granule-to-granule and granule-to-plasma membrane fusion events. These results provide a cellular mechanism that can account for the previously demonstrated potentiation of secretion from lactotrophs by cAMP- and PKCdependent pathways. Key words: FM1-43 � fluorescence � homotypic fusion � compound exocytosis � phorbol ester
A J. Cochilla; Joseph K. Angleson; William J. Betz
fusion | National Nuclear Security Administration
National Nuclear Security Administration (NNSA)
AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration goSecuritycdns ||fors | Nationalfrmac |fusion |
Fusion Nuclear Science and Technology ProgramFusion Nuclear Science and Technology Program Issues and Strategy for Fusion Nuclear Science Facility (FNSF)
Need for Fusion Nuclear Science and Technology ProgramFusion Nuclear Science and Technology Program Issues and Strategy for Fusion Nuclear Science Facility (FNSF) Key R&D Areas to begin NOW (modeling 12, 2010 #12;Fusion Nuclear Science and Technology (FNST) FNST is the science engineering technology
Summary of the report of the Senior Committee on Environmental, Safety, and Economic Aspects of Magnetic Fusion Energy
The Senior Committee on Environmental, Safety, and Economic Aspects of Magnetic Fusion Energy (ESECOM) has assessed magnetic fusion energy's prospects for providing energy with economic, environmental, and safety characteristics that would be attractive compared with other energy sources (mainly fission) available in the year 2015 and beyond. ESECOM gives particular attention to the interaction of environmental, safety, and economic characteristics of a variety of magnetic fusion reactors, and compares them with a variety of fission cases. Eight fusion cases, two fusion-fission hybrid cases, and four fission cases are examined, using consistent economic and safety models. These models permit exploration of the environmental, safety, and economic potential of fusion concepts using a wide range of possible materials choices, power densities, power conversion schemes, and fuel cycles. The ESECOM analysis indicates that magnetic fusion energy systems have the potential to achieve costs-of-electricity comparable to those of present and future fission systems, coupled with significant safety and environmental advantages. 75 refs., 2 figs., 24 tabs.
Holdren, J.P.; Berwald, D.H.; Budnitz, R.J.; Crocker, J.G.; Delene, J.G.; Endicott, R.D.; Kazimi, M.S.; Krakowski, R.A.; Logan, B.G.; Schultz, K.R.
aspects of a hybrid fusion-fission energy system called theof a Hybrid Fusion-Fission Nuclear Energy System by Kevinof a Hybrid Fusion-Fission Nuclear Energy System by Kevin
Inertial confinement fusion research and development studies. Final report, October 1979-August 1980
These Inertial Confinement Fusion (ICF) research and development studies were selected for structural, thermal, and vacuum pumping analyses in support of the High Yield Lithium Injection Fusion Energy (HYLIFE) concept development. An additional task provided an outlined program plan for an ICF Engineering Test Facility, using the HYLIFE concept as a model, although the plan is generally applicable to other ICF concepts. The HYLIFE is one promising type of ICF concept which features a falling array of liquid lithium jets. These jets surround the fusion reaction to protect the first structural wall (FSW) of the vacuum chamber by absorbing the fusion energy, and to act as the tritium breeder. The fusion energy source is a deuterium-tritium pellet injected into the chamber every second and driven by laser or heavy ion beams. The studies performed by Grumman have considered the capabilities of specific HYLIFE features to meet life requirements and the requirement to recover to preshot conditions prior to each subsequent shot. The components under investigation were the FSW which restrains the outward motion of the liquid lithium, the nozzle plate which forms the falling jet array, the graphite shield which is in direct top view of the fusion pellet, and the vacuum pumping system. The FSW studies included structural analysis, and definition of an experimental program to validate computer codes describing lithium motion and the resulting impact on the wall.
Bullis, R.; Finkelman, M.; Leng, J.; Luzzi, T.; Ojalvo, I.; Powell, E.; Sedgley, D.
ORNL's Peng wins Fusion Power Associates Leadership Award | ornl...
tax-exempt research and educational foundation that provides information on the status of fusion development and other applications of plasma science and fusion research....
Exploring Plasma Science Advances from Fusion Findings to Astrophysica...
confinement fusion experiments at the National Ignition Facility (NIF) at the DOE's Lawrence Livermore National Laboratory. Speakers noted that producing fusion by heating a...
accelerator fusion research: Topics by E-print Network
on the Fusion Ignition Research Experiment (FIRE), a tokamak designed for burning plasma research. Engineering 17 Research Needs Workshop for Magnetic Fusion Energy Plasma Physics...
association fusion research: Topics by E-print Network
on the Fusion Ignition Research Experiment (FIRE), a tokamak designed for burning plasma research. Engineering 18 Research Needs Workshop for Magnetic Fusion Energy Plasma Physics...
This report summarizes the work of the University of Utah, which was a member of the National Fusion Collaboratory (NFC) Project funded by the United States Department of Energy (DOE) under the Scientific Discovery through Advanced Computing Program (SciDAC) to develop a persistent infrastructure to enable scientific collaboration for magnetic fusion research. A five year project that was initiated in 2001, it the NFC built on the past collaborative work performed within the U.S. fusion community and added the component of computer science research done with the USDOE Office of Science, Office of Advanced Scientific Computer Research. The project was itself a collaboration, itself uniting fusion scientists from General Atomics, MIT, and PPPL and computer scientists from ANL, LBNL, and Princeton University, and the University of Utah to form a coordinated team. The group leveraged existing computer science technology where possible and extended or created new capabilities where required. The complete finial report is attached as an addendum. The In the collaboration, the primary technical responsibility of the University of Utah in the collaboration was to develop and deploy an advanced scientific visualization service. To achieve this goal, the SCIRun Problem Solving Environment (PSE) is used on FusionGrid for an advanced scientific visualization service. SCIRun is open source software that gives the user the ability to create complex 3D visualizations and 2D graphics. This capability allows for the exploration of complex simulation results and the comparison of simulation and experimental data. SCIRun on FusionGrid gives the scientist a no-license-cost visualization capability that rivals present day commercial visualization packages. To accelerate the usage of SCIRun within the fusion community, a stand-alone application built on top of SCIRun was developed and deployed. This application, FusionViewer, allows users who are unfamiliar with SCIRun to quickly create visualizations and perform analysis of their simulation data from either the MDSplus data storage environment or from locally stored HDF5 files. More advanced tools for visualization and analysis also were created in collaboration with the SciDAC Center for Extended MHD Modeling. Versions of SCIRun with the FusionViewer have been made available to fusion scientists on the Mac OS X, Linux, and other Unix based platforms and have been downloaded 1163 times. SCIRun has been used with NIMROD, M3D, BOUT fusion simulation data as well as simulation data from other SciDAC application areas (e.g., Astrophysics). The subsequent visualization results - including animations - have been incorporated into invited talks at multiple APS/DPP meetings as well as peer reviewed journal articles. As an example, SCIRun was used for the visualization and analysis of a NIMROD simulation of a disruption that occurred in a DIII-D experiment. The resulting animations and stills were presented as part of invited talks at APS/DPP meetings and the SC04 conference in addition to being highlighted in the NIH/NSF Visualization Research Challenges Report. By achieving its technical goals, the University of Utah played a key role in the successful development of a persistent infrastructure to enable scientific collaboration for magnetic fusion research. Many of the visualization tools developed as part of the NFC continue to be used by Fusion and other SciDAC application scientists and are currently being supported and expanded through follow-on up on SciDAC projects (Visualization and Analytics Center for Enabling Technology, and the Visualization and Analysis in Support of Fusion SAP).
Allen R. Sanderson; Christopher R. Johnson
Assessment of NDE Methods on Inspection of HDPE Butt Fusion Piping Joints for Lack of Fusion with Validation from Mechanical Testing
Studies at the Pacific Northwest National Laboratory (PNNL) in Richland, Washington, are being conducted to evaluate nondestructive examinations (NDE) coupled with mechanical testing of butt fusion joints in high-density polyethylene (HDPE) pipe for assessing lack of fusion. The work provides information to the U.S. Nuclear Regulatory Commission (NRC) on the effectiveness of volumetric inspection techniques of HDPE butt fusion joints in Section III, Division 1, Class 3, buried piping systems in nuclear power plants. This paper describes results from preliminary assessments using ultrasonic and microwave nondestructive techniques and mechanical testing with the high-speed tensile impact test and the side-bend test for determining joint integrity. A series of butt joints were fabricated in 3408, 12-in. IPS DR-11 HDPE material by varying the fusion parameters to create good joints and joints containing a range of lack-of-fusion conditions. Six of these butt joints were volumetrically examined with time-of-flight diffraction (TOFD), phased-array (PA) ultrasound, and the Evisive microwave system. The outer-diameter weld beads were removed for the microwave inspection. In two of the four pipes, both the outer and inner weld beads were removed and the pipe joints re-evaluated. The pipes were sectioned and the joints destructively evaluated with the side-bend test by cutting portions of the fusion joint into slices that were planed and bent. The last step in this limited study will be to correlate the fusion parameters, nondestructive, and destructive evaluation results to validate the effectiveness of what each NDE technology detects and what each does not detect. The results of the correlation will be used in identifying any future work that is needed.
Anderson, Michael T.; Cinson, Anthony D.; Crawford, Susan L.; Doctor, Steven R.; Moran, Traci L.; Watts, Michael W.
Applications of Skyrme energy-density functional to fusion reactions spanning the fusion barriers
The Skyrme energy density functional has been applied to the study of heavy-ion fusion reactions. The barriers for fusion reactions are calculated by the Skyrme energy density functional with proton and neutron density distributions determined by using restricted density variational (RDV) method within the same energy density functional together with semi-classical approach known as the extended semi-classical Thomas-Fermi method. Based on the fusion barrier obtained, we propose a parametrization of the empirical barrier distribution to take into account the multi-dimensional character of real barrier and then apply it to calculate the fusion excitation functions in terms of barrier penetration concept. A large number of measured fusion excitation functions spanning the fusion barriers can be reproduced well. The competition between suppression and enhancement effects on sub-barrier fusion caused by neutron-shell-closure and excess neutron effects is studied.
Min Liu; Ning Wang; Zhuxia Li; Xizhen Wu; Enguang Zhao
Fusion Ignition Research Experiment Engineering Status Report
of the world. The FIRE web site has been chosen as a selection for the Scout Report for Science and EngineeringFusion Ignition Research Experiment -FIRE- Engineering Status Report For Fiscal Year 2000 Issued on the Fusion Ignition Research Experiment (FIRE), a tokamak designed for burning plasma research. Engineering
The Case for Magnetized Target Fusion (MTF)
of conventional unmagnetized targets by orders of magnitude; (b) makes fusion "easier" for any driver; (c) makes) drivers feasible; (d) allows experimentation at much higher energy (e.g., 20 MJ implosion kinetic energy can reduce the required radial convergence to drivers can lead to a new fusion
Plasmas are Hot and Fusion is Cool
Plasmas are Hot and Fusion is Cold. The DOE Princeton Plasma Physics Laboratory (PPPL) collaborates to develop fusion as a safe, clean and abundant energy source for the future. This video discusses PPPL's research and development on plasma, the fourth state of matter.
Fusion Power Associates Meeting 3 December 2009
of laser-accelerated planar targets Visible, XUV & x-ray Detectors & Spectrometers Distance Distance SIDEFusion Power Associates Meeting 3 December 2009 Overview of the NRL laser fusion program: Progress in the Science and Technology of Direct Drive Laser fusion with the KrF laser Presented by: Steve Obenschain
A method of controlling the reaction rates of the fuel atoms in a fusion reactor comprises the step of polarizing the nuclei of the fuel atoms in a particular direction relative to the plasma confining magnetic field. Fusion reaction rates can be increased or decreased, and the direction of emission of the reaction products can be controlled, depending on the choice of polarization direction.
Kulsrud, Russell M. (Princeton, NJ); Furth, Harold P. (Princeton, NJ); Valeo, Ernest J. (Princeton Junction, NJ); Goldhaber, Maurice (Bayport, NY)
EPRI Fusion Energy Assessment July 19, 2011
EPRI Fusion Energy Assessment July 19, 2011 Palo Alto, CA Roadmapping an MFE Strategy R.J. Fonck research program RJF EPRI 2011 #12;ACCELERATE MFE VIA FUSION NUCLEAR S&T PROGRAM IN ITER TIMEFRAME #12;THE development · Similar efforts, and results, pursued by international partners RJF EPRI 2011 #12;THE SEQUENCE
Unlocking Fusion Power: Materials are the Key
ComponentsHigh Heat Flux Components DEMODEMO #12;5 Radiation damage in Materials Bombardment of 2-10 MW / m2 fusion "ash") gets embedded forms nano-sized bubbles n #12;6 Radiation damage in Materials Bombardment" for steels "useful" for steels SAFE for a fusion reactor Materials #12;12 Surface gamma dose rate (Sv
Sean Finnegan & Ann Satsangi Fusion Energy Sciences
Energy (IFE) science. #12;HEDLP definition "High-energy-density laboratory plasma (HEDLP) physicsSean Finnegan & Ann Satsangi Fusion Energy Sciences Program Management Team for HEDLP Fusion Power Associates15 December 2011 Comments on the DOE-SC Program in High Energy Density Laboratory Plasma Science
ERDA-76/110/l FUSION POWER
ERDA-76/110/l UC-20 FUSION POWER BY MAGNETIC CONFINEMENT PROGRAMPLAN VOLUME I SUMMARY JULY 1976 electric plants. These include direct production of hydrogen gas and/or synthetic fuels; direct energy production for chemical processing; fissile fuel production; fission product waste disposal; and fusion
Neutron Catalysis of Resonance Fusion in Stellar Matter
Within the framework of resonance fusion study in stellar matter the features of system consisted of two alpha particles and one neutron have been investigated at astrophysical energies. Consideration of three body scattering has been carried out on base of well-known Faddeev's equations. It is found that under certain conditions the series of resonance states appear in this system at very low energies. The lifetimes of these three body resonances are close to the lifetime of unstable nucleus 8Be. The simple forms of two body repulsive potentials are taken into account to describe the parameters of the alpha, alpha resonance and to satisfy n, alpha scattering data at very low energies. The explanation of resonance phenomena in n, alpha, alpha system is offered on base of physical model. The effect results from resonance quantum phenomena in few body dynamics. In turn, the resonance fusion can give influence on many astrophysical phenomena. The possibility of catalyzing this new mode of fusion by free neutrons in alpha particle matter is considered too.
Nurgali Takibayev
A Virtualized Computing Platform For Fusion Control Systems
The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory is a stadium-sized facility that contains a 192-beam, 1.8-Megajoule, 500-Terawatt, ultraviolet laser system together with a 10-meter diameter target chamber with room for multiple experimental diagnostics. NIF is the world's largest and most energetic laser experimental system, providing a scientific center to study inertial confinement fusion (ICF) and matter at extreme energy densities and pressures. NIF's laser beams are designed to compress fusion targets to conditions required for thermonuclear burn, liberating more energy than required to initiate the fusion reactions. 2,500 servers, 400 network devices and 700 terabytes of networked attached storage provide the foundation for NIF's Integrated Computer Control System (ICCS) and Experimental Data Archive. This talk discusses the rationale & benefits for server virtualization in the context of an operational experimental facility, the requirements discovery process used by the NIF teams to establish evaluation criteria for virtualization alternatives, the processes and procedures defined to enable virtualization of servers in a timeframe that did not delay the execution of experimental campaigns and the lessons the NIF teams learned along the way. The virtualization architecture ultimately selected for ICCS is based on the Open Source Xen computing platform and 802.1Q open networking standards. The specific server and network configurations needed to ensure performance and high availability of the control system infrastructure will be discussed.
Frazier, T; Adams, P; Fisher, J; Talbot, A
AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review of theOFFICE OF8/%2A en Responding to Emergencies7/%2A
NNSA Sees Significant Achievements, Important Improvements in...
Sees Significant ... NNSA Sees Significant Achievements, Important Improvements in 2012 Posted: December 17, 2012 - 5:03pm As 2012 draws to a close, the National Nuclear Security...
achievement: Topics by E-print Network
POLICIES FOR ACHIEVING ENERGY JUSTICE IN SOCIETY: BEST PRACTICES FOR APPLYING SOLAR ENERGY) Project Center for Energy and Environmental Policy University of Delaware First...
Evaluation of Project Achievements in VOMARE -project.
??The purpose of the thesis is to study the achievements of VOMARE �project from the Finnish Lifeboat Institutions perspective. The organisation is a roof organisation� (more)
Kokkarinen, Eeva
Vehicle Technologies Engine Fuel Efficiency Milestones Achieving and Demonstrating Vehicle Technologies Engine Fuel Efficiency Milestones 2010 DOE Vehicle Technologies and Hydrogen...
NERSC Announces Third Annual HPC Achievement Awards
Computing Center (NERSC) announced the winners of its third annual High Performance Computing (HPC) Achievement Awards on Feb. 24, 2015, during the annual NERSC User...
Chamber and target technology development for inertial fusion energy
Fusion chambers and high pulse-rate target systems for inertial fusion energy (IFE) must: regenerate chamber conditions suitable for target injection, laser propagation, and ignition at rates of 5 to 10 Hz; extract fusion energy at temperatures high enough for efficient conversion to electricity; breed tritium and fuel targets with minimum tritium inventory; manufacture targets at low cost; inject those targets with sufficient accuracy for high energy gain; assure adequate lifetime of the chamber and beam interface (final optics); minimize radioactive waste levels and annual volumes; and minimize radiation releases under normal operating and accident conditions. The primary goal of the US IFE program over the next four years (Phase I) is to develop the basis for a Proof-of-Performance-level driver and target chamber called the Integrated Research Experiment (IRE). The IRE will explore beam transport and focusing through prototypical chamber environment and will intercept surrogate targets at high pulse rep-rate. The IRE will not have enough driver energy to ignite targets, and it will be a non-nuclear facility. IRE options are being developed for both heavy ion and laser driven IFE. Fig. 1 shows that Phase I is prerequisite to an IRE, and the IRE plus NIF (Phase II) is prerequisite to a high-pulse rate. Engineering Test Facility and DEMO for IFE, leading to an attractive fusion power plant. This report deals with the Phase-I R&D needs for the chamber, driver/chamber interface (i.e., magnets for accelerators and optics for lasers), target fabrication, and target injection; it is meant to be part of a more comprehensive IFE development plan which will include driver technology and target design R&D. Because of limited R&D funds, especially in Phase I, it is not possible to address the critical issues for all possible chamber and target technology options for heavy ion or laser fusion. On the other hand, there is risk in addressing only one approach to each technology option. Therefore, in the following description of these specific feasibility issues, we try to strike a balance between narrowing the range of recommended R&D options to minimize cost, and keeping enough R&D options to minimize risk.
Abdou, M; Besenbruch, G; Duke, J; Forman, L; Goodin, D; Gulec, K; Hoffer, J; Khater, H; Kulcinsky, G; Latkowski, J F; Logan, B G; Margevicious, B; Meier, W R; Moir, R W; Morley, N; Nobile, A; Payne, S; Peterson, P F; Peterson, R; Petzoldt, R; Schultz, K; Steckle, W; Sviatoslavsky, L; Tillack, M; Ying, A
Upside-Down Solar Cell Achieves Record Efficiencies (Fact Sheet)
The inverted metamorphic multijunction (IMM) solar cell is an exercise in efficient innovation - literally, as the technology boasted the highest demonstrated efficiency for converting sunlight into electrical energy at its debut in 2005. Scientists at the National Renewable Energy Laboratory (NREL) inverted the conventional photovoltaic (PV) structure to revolutionary effect, achieving solar conversion efficiencies of 33.8% and 40.8% under one-sun and concentrated conditions, respectively.
Security Conditions
Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]
This Notice ensures that DOE uniformly meets the requirements of the Homeland Security Advisory System outlined in Homeland Security Presidential Directive-3, Threat Conditions and Associated Protective Measures, dated 3-11-02, and provides responses specified in Presidential Decision Directive 39, U.S. Policy on Counterterrorism (U), dated 6-21-95. It cancels DOE N 473.8, Security Conditions, dated 8-7-02. Extended until 7-7-06 by DOE N 251.64, dated 7-7-05 Cancels DOE N 473.8
Technical Letter Report - Preliminary Assessment of NDE Methods on Inspection of HDPE Butt Fusion Piping Joints for Lack of Fusion
The U.S. Nuclear Regulatory Commission (NRC) has a multi-year program at the Pacific Northwest National Laboratory (PNNL) to provide engineering studies and assessments of issues related to the use of nondestructive evaluation (NDE) methods for the reliable inspection of nuclear power plant components. As part of this program, there is a subtask 2D that was set up to address an assessment of issues related to the NDE of high density polyethylene (HDPE) butt fusion joints. This work is being driven by the nuclear industry wanting to employ HDPE materials in nuclear power plant systems. This being a new material for use in nuclear applications, there are a number of issues related to its use and potential problems that may evolve. The industry is pursuing ASME Code Case N-755 entitled �Use of Polyethylene (PE) Plastic Pipe for Section III, Division 1, Construction and Section XI Repair/Replacement Activities� that contains the requirements for nuclear power plant applications of HDPE. This Code Case requires that inspections be performed after the fusion joint is made by visually examining the bead that is formed and conducting a pressure test of the joint. These tests are only effective in general if gross through-wall flaws exist in the fusion joint. The NRC wants to know whether a volumetric inspection can be conducted on the fusion joint that will reliably detect lack-of-fusion conditions that may be produced during joint fusing. The NRC has requested that the work that PNNL is conducting be provided to assist them in resolving this inspection issue of whether effective volumetric NDE can be conducted to detect lack of fusion (LOF) in the butt HDPE joints. PNNL had 24 HDPE pipe specimens manufactured of 3408 material to contain LOF conditions that could be used to assess the effectiveness of NDE in detecting the LOF. Basic ultrasonic material properties were measured and used to guide the use of phased arrays and time-of-flight diffraction (TOFD) work that was conducted. Millimeter (mm) waves were also used to inspect these assemblies. Fluor and NDE Innovations, Inc. conducted TOFD inspections using their commercially available equipment on all 24 specimens. These NDE inspection results were reviewed and several of the specimens were selected for destructive evaluation using a microtome to slice small blocks of blank and fusion joint material. This interim report provides a status/summary of the work that has been conducted to date. In the areas selected for destructive testing where there were strong acoustic responses, LOF was verified. In areas where there were no NDE responses, no LOF was found. It needs to be noted that only a small amount of material has been destructively characterized at this point and further work is planned to determine if these trends hold up. Some of the material from three of the assemblies was sent off for mechanical testing but the results were not available to be included in this status report. The initial work shows that at least some of the LOF is providing NDE responses that have been verified through destructive testing. Thus, there is promise that a volumetric examination can be conducted on HDPE butt fusion joints. The future work will lead to quantifying what various NDE methods can detect, what they miss, and what they incorrectly characterize as defective.
Crawford, Susan L.; Cumblidge, Stephen E.; Doctor, Steven R.; Hall, Thomas E.; Anderson, Michael T.
Fusion Potentials for G_k and Handle Squashing
Using Chern-Simons gauge theory, we show that the fusion ring of the conformal field theory G_k is isomorphic to P(u)/(\\del V), where V is a polynomial in u and (\\del V) is the ideal generated by the conditions \\del V=0. We also derive a residue-like formula for the correlation functions in the Chern-Simons theory thus providing a RCFT version of the residue formula for the TLG models. An operator that acts like the measure in the residue formula has the ionterpretation of a handle squashing operator and an explicit formula for this operator is given.
Michael Crescimanno
Thermonuclear Fusion with the Sheared Flow Stabilized Z-Pinch
Two basic approaches to producing thermonuclear fusion with a sheared flow stabilized z-pinch are considered. One consists of heating the entire length of the z-pinch column to the required temperatures. The other basic approach considered here involves the concept of fast ignition. A localized "hot-spot" is produced under the proper conditions to ignite a thermonuclear burn wave in the z-pinch plasma. Here we demonstrate that sheared flow stabilization is more efficient in the fast-ignition method with isentropic compression then in a z-pinch where the entire plasma column is heated.
Winterberg, F
How far is a Fusion Power Reactor from an Experimental Reactor?
be able to move directly and safely to a "first of a kind" reactor. The main conditions to be satisfied / experimental evidence. To assess the reactor relevance of ITER, rather than a comparison between ITER and one1 How far is a Fusion Power Reactor from an Experimental Reactor? R. Toschi(1) , P. Barabaschi(2
Development and characterization of a Rift Valley fever virus cell-cell fusion assay using alphavirus replicon vectors
Rift Valley fever virus (RVFV), a member of the Phlebovirus genus in the Bunyaviridae family, is transmitted by mosquitoes and infects both humans and domestic animals, particularly cattle and sheep. Since primary RVFV strains must be handled in BSL-3+ or BSL-4 facilities, a RVFV cell-cell fusion assay will facilitate the investigation of RVFV glycoprotein function under BSL-2 conditions. As for other members of the Bunyaviridae family, RVFV glycoproteins are targeted to the Golgi, where the virus buds, and are not efficiently delivered to the cell surface. However, overexpression of RVFV glycoproteins using an alphavirus replicon vector resulted in the expression of the glycoproteins on the surface of multiple cell types. Brief treatment of RVFV glycoprotein expressing cells with mildly acidic media (pH 6.2 and below) resulted in rapid and efficient syncytia formation, which we quantified by {beta}-galactosidase {alpha}-complementation. Fusion was observed with several cell types, suggesting that the receptor(s) for RVFV is widely expressed or that this acid-dependent virus does not require a specific receptor to mediate cell-cell fusion. Fusion occurred over a broad temperature range, as expected for a virus with both mosquito and mammalian hosts. In contrast to cell fusion mediated by the VSV-G glycoprotein, RVFV glycoprotein-dependent cell fusion could be prevented by treating target cells with trypsin, indicating that one or more proteins (or protein-associated carbohydrate) on the host cell surface are needed to support membrane fusion. The cell-cell fusion assay reported here will make it possible to study the membrane fusion activity of RVFV glycoproteins in a high-throughput format and to screen small molecule inhibitors for the ability to block virus-specific membrane fusion.
Filone, Claire Marie [Department of Microbiology, University of Pennsylvania, 301 Johnson Pavilion, 3610 Hamilton Walk, Philadelphia, PA 19104 (United States); Heise, Mark [Departments of Genetics and Microbiology and Immunology, The Carolina Vaccine Institute, University of North Carolina, Chapel Hill, NC 27599 (United States); Doms, Robert W. [Department of Microbiology, University of Pennsylvania, 301 Johnson Pavilion, 3610 Hamilton Walk, Philadelphia, PA 19104 (United States)]. E-mail: email@example.com; Bertolotti-Ciarlet, Andrea [Department of Microbiology, University of Pennsylvania, 301 Johnson Pavilion, 3610 Hamilton Walk, Philadelphia, PA 19104 (United States)]. E-mail: email@example.com
The Gasdynamic Mirror Fusion Propulsion System -- Revisited
Many of the previous studies assessing the capability of the gasdynamic mirror (GDM) fusion propulsion system employed analyses that ignored the 'ambipolar' potential. This electrostatic potential arises as a result of the rapid escape of the electrons due to their small mass. As they escape, they leave behind an excess positive charge which manifests itself in an electric field that slows down the electrons while speeding up the ions until their respective axial diffusions are equalized. The indirect effect on the ions is that their confinement time is reduced relative to that of zero potential, and hence the plasma length must be increased to accommodate that change. But as they emerge from the thruster mirror - which serves as a magnetic nozzle - the ions acquire an added energy equal to that of the potential energy, and that in turn manifests itself in increased specific impulse and thrust. We assess the propulsive performance of the GDM thruster, based on the more rigorous theory, by applying it to a round trip Mars mission employing a continuous burn acceleration/deceleration type of trajectory. We find that the length of the device and travel time decrease with increasing plasma density, while the total vehicle mass reaches a minimum at a plasma density of 3 x 1016 cm-3. At such a density, and an initial DT ion temperature of 10 keV, a travel time of 60 days is found to be achievable at GDM propulsion parameters of about 200,000 seconds of specific impulse and approximately 47 kN of thrust.
Kammash, Terry [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Blvd, Ann Arbor, MI 48109 (United States); Tang, Ricky [Department of Aerospace Engineering, University Michigan, 1320 Beal Ave, Ann Arbor, MI 48109 (United States)
Contribution to Fusion Materials Semiannual Report
The objectives of this work are the following: (1) The application of micro and mesoscale modeling techniques to study dislocation properties in ferritic and W-based materials; and (2) The development of computational models and tools to study damage accumulation in >1 dpa (fusion-like) conditions, both for Fe and W-based alloys. The high-temperature strength of structural ferritic alloys (ferritic/martensitic steels, ODS steels, bcc refractory alloys) hinges on the thermal stability of second phase particles and their interactions with dislocations. Irradiation damage can modify the structure and stability of both the particles and dislocations, particularly by the introduction of gas atoms, point defects and point defect clusters. The three aspects of materials strength that we are studying are: (a) Computation of dislocation mobility functions (stress-velocity relations) as a function of temperature and dislocation character. This will be done via molecular dynamics (MD) simulations of single dislocation motion under applied shear stress. This is a fundamental input to dislocation dynamics (DD) simulations and also provides fundamental insights into the high-temperature plastic behavior of ferritic materials. (b) Simulations of dislocation-obstacle interactions using MD and DD. This subtask includes simulating the effect on dislocation glide of precipitates (e.g., {alpha}' Cr precipitates), ODS particles, and irradiation induced defect clusters (e.g. voids, dislocation loops, etc.). (c) Implementation of this information (dislocation mobilities and dislocation-defect interaction rules) into DD codes that will allow us to study plasticity of single crystals Fe alloys under relevant irradiation conditions.
Marian, J; Meier, W
A program toward a fusion reactor* P.-H. Rebut,+ M. L. Watkins, D. J. Gambier, and D. Boucher
between the model and JET data. The main predictions are also consistent with statistical scaling laws without a significant increase in world funding. I. INTRODUCTION Present fusion research programs out the main results achieved in JET. Furthermore, a clearer picture of energy and particle transport
Parameterizing loop fusion for automated empirical tuning
Traditional compilers are limited in their ability to optimize applications for different architectures because statically modeling the effect of specific optimizations on different hardware implementations is difficult. Recent research has been addressing this issue through the use of empirical tuning, which uses trial executions to determine the optimization parameters that are most effective on a particular hardware platform. In this paper, we investigate empirical tuning of loop fusion, an important transformation for optimizing a significant class of real-world applications. In spite of its usefulness, fusion has attracted little attention from previous empirical tuning research, partially because it is much harder to configure than transformations like loop blocking and unrolling. This paper presents novel compiler techniques that extend conventional fusion algorithms to parameterize their output when optimizing a computation, thus allowing the compiler to formulate the entire configuration space for loop fusion using a sequence of integer parameters. The compiler can then employ an external empirical search engine to find the optimal operating point within the space of legal fusion configurations and generate the final optimized code using a simple code transformation system. We have implemented our approach within our compiler infrastructure and conducted preliminary experiments using a simple empirical search strategy. Our results convey new insights on the interaction of loop fusion with limited hardware resources, such as available registers, while confirming conventional wisdom about the effectiveness of loop fusion in improving application performance.
Zhao, Y; Yi, Q; Kennedy, K; Quinlan, D; Vuduc, R
Ion Rings for Magnetic Fusion
This Final Technical Report presents the results of the program, Ion Rings for Magnetic Fusion, which was carried out under Department of Energy funding during the period August, 1993 to January, 2005. The central objective of the program was to study the properties of field-reversed configurations formed by ion rings. In order to reach this objective, our experimental program, called the Field-reversed Ion Ring Experiment, FIREX, undertook to develop an efficient, economical technology for the production of field-reversed ion rings. A field-reversed configuration (FRC) in which the azimuthal (field-reversing) current is carried by ions with gyro-radius comparable to the magnetic separatrix radius is called a field-reversed ion ring. A background plasma is required for charge neutralization of the ring, and this plasma will be confined within the ring's closed magnetic flux. Ion rings have long been of interest as the basis of compact magnetic fusion reactors, as the basis for a high-power accelerator for an inertial fusion driver, and for other applications of high power ion beams or plasmas of high energy density. Specifically, the FIREX program was intended to address the longstanding question of the contribution of large-orbit ions to the observed stability of experimental FRCs to the MHD tilt mode. Typical experimental FRCs with s {approx} 2-4, where s is the ratio of separatrix radius to ion gyro-radius, have been stable to tilting, but desired values for a fusion reactor, s > 20, should be unstable. The FIREX ring would consist of a plasma with large s for the background ions, but with s {approx} 1 for the ring ions. By varying the proportions of these two populations, the minimum proportion of large-orbit ions necessary for stability could be determined. The incorporation of large-orbit ions, perhaps by neutral-beam injection, into an FRC has been advanced for the purpose of stabilizing, heating, controlling angular momentum, and aiding the formation of a reactor-scale FRC, and the FIREX program was intended to test the ideas behind this approach. We will describe in this report the technological development path and advances in physics understanding that allowed FIREX to reach a regime in which ion rings were reproducibly created with up to about half the current necessary to produce field reversal. Unfortunately, the experiments were limited to this level by a fundamental, unanticipated aspect of the physics of strong ion rings in plasma. The FIREX ring is a strongly anisotropic, current-carrying population of ions moving faster than the Alfven speed in the background plasma. The rapidly changing ring current excites very large-amplitude Alfven waves in the plasma, and these waves strongly affect the ring, causing rapid energy loss in a way that is not compatible with the success of the ring trapping scenario around which FIREX was designed. The result was that FIREX rings were always very short-lived. We will discuss the implication of these results for possible future use of large-orbit ions in FRCs. In short, it appears that a certain range of the parameters characterizing the ring Alfven mach number and distribution function must be avoided to allow the existence of a long-lived energetic ion component in an FRC. This report will explain why FIREX experimental results cannot be directly scaled to quantitatively predict this range for a particular FRC configuration. This will require accurate, three-dimensional simulations. FIREX results do constitute a very good dataset for validating such a code, and simulations already carried out during this program provide a guide to the important physics involved.
Greenly, John, B.
Fusion materials science and technology research opportunities now and during the ITER era
Several high-priority near-term potential research activities to address fusion nuclear science challenges are summarized. General recommendations include: (1) Research should be preferentially focused on the most technologically advanced options (i.e., options that have been developed at least through the singleeffects concept exploration stage, technology readiness levels >3), (2) Significant near-term progress can be achieved by modifying existing facilities and/or moderate investment in new medium-scale facilities, and (3) Computational modeling for fusion nuclear sciences is generally not yet sufficiently robust to enable truly predictive results to be obtained, but large reductions in risk, cost and schedule can be achieved by careful integration of experiment and modeling.
S.J. Zinkle; J.P. Planchard; R.W. Callis; C.E. Kessel; P.J. Lee; K.A. McCarty; Various Others
Fusion Materials Science and Technology Research Opportunities now and during the ITER Era
Several high-priority near-term potential research activities to address fusion nuclear science challenges are summarized. General recommendations include: 1) Research should be preferentially focused on the most technologically advanced options (i.e., options that have been developed at least through the single-effects concept exploration stage, Technology Readiness Levels >3), 2) Significant near-term progress can be achieved by modifying existing facilities and/or moderate investment in new medium-scale facilities, and 3) Computational modeling for fusion nuclear sciences is generally not yet sufficiently robust to enable truly predictive results to be obtained, but large reductions in risk, cost and schedule can be achieved by careful integration of experiment and modeling.
Zinkle, Steven J.; Blanchard, James; Callis, Richard W.; Kessel, Charles E.; Kurtz, Richard J.; Lee, Peter J.; Mccarthy, Kathryn; Morley, Neil; Najmabadi, Farrokh; Nygren, Richard; Tynan, George R.; Whyte, Dennis G.; Willms, Scott; Wirth, Brian D.
Potential of Mirror Systems as Future Fusion Power Reactors
Mirror based fusion reactors - as other fusion reactor concepts - have considerable environmental and safety advantages. They could make available energy resources for many 1000 years. Mirror type fusion reactors have additional technical advantages over other fusion reactor concepts. These are: simple design topology, steady state power generation, decoupling of end plugs from central power producing regions, small power units as demonstration facilities.
Kessler, Guenter; Kulcinski, Gerald L. [University of Madison (United States)
Status of Research on Fusion Energy and Plasma Turbulence
Status of Research on Fusion Energy and Plasma Turbulence Candy, Waltz (General Atomics) Greg Project · A DOE, Office of Fusion Energy Sciences, SciDAC (Scientific Discovery Through Advanced Computing_annual.html #12;#12;#12;Progress in Fusion Energy Outpaced Computers J.B. Lister #12;Progress in Fusion
Department of Advanced Energy Nuclear Fusion Research Education Program
24 Department of Advanced Energy Nuclear Fusion Research Education Program 23 8 23 to Nuclear Fusion Research Education Program 277-8561 5-1-5 1 04-7136-4092 http://www.k.u-tokyo.ac.jp/fusion: firstname.lastname@example.com tel: 046-856-2121 12 http://www. k.u-tokyo.ac.jp/fusion-pro/ #12
Yamamoto, Hirosuke
359-06/RDS/ Fusion Nuclear Science Facility and Program
359-06/RDS/ rs Fusion Nuclear Science Facility and Program by R.D. Stambaugh Fusion Power, DC #12;359-06/RDS/ rs Mission of a Fusion Nuclear Science Facility (FNSF) Two Candidates: FNSF That Must Be Filled Between ITER and a DEMO * A Fusion Nuclear Science Program and Facility Fills Nearly All
Taming turbulence in magnetized plasmas: from fusion energy to
occurs (fusion of particle beams will not work...) Thermonuclear fusion in a confined plasma (T~10 keTaming turbulence in magnetized plasmas: from fusion energy to black hole accretion disks Troy?: In fusion plasmas turbulent leakage of heat and particles is a key issue. Sheared flow can suppress
MSc in Plasma Physics & Applications Laser Fusion Energy
. Thermonuclear fusion provides unlimited energy for all the world which is clean from long lived radioactiveMSc in Plasma Physics & Applications Laser Fusion Energy Why laser fusionDescription of the course fusion for energy production. This unique training scheme involves eight leading European centres
Paxton, Anthony T.
Thermonuclear Experimental Reactor), now being constructed in Caderache, France [5]. In contrast, inertial fusion
Sharp, W. M.
Fusion utility in the Knudsen layer
In inertial confinement fusion, the loss of fast ions from the edge of the fusing hot-spot region reduces the reactivity below its Maxwellian value. The loss of fast ions may be pronounced because of the long mean free paths of fast ions, compared with those of thermal ions. We introduce a fusion utility function to demonstrate essential features of this Knudsen layer effect, in both magnetized and unmagnetized cases. The fusion utility concept is also used to evaluate the restoring reactivity in the Knudsen layer by manipulating fast ions in phase space using waves.
Davidovits, Seth; Fisch, Nathaniel J. [Princeton Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08544 (United States)
Fusion Induced by Radioactive Ion Beams
The use of radioactive beams opens a new frontier for fusion studies. The coupling to the continuum can be explored with very loosely bound nuclei. Experiments were performed with beams of nuclei at or near the proton and neutron drip-lines to measure fusion and associated reactions in the vicinity of the Coulomb barrier. In addition, the fusion yield is predicted to be enhanced in reactions involving very neutron-rich unstable nuclei. Experimental measurements were carried out to investigate if it is feasible to use such beams to produce new heavy elements. The current status of these experimental activities is given in this review.
J. F. Liang; C. Signorini
IPFR: Integrated Pool Fusion Reactor concept
The IPFR (Integrated Pool Fusion Reactor) concept is to place a fusion reactor into a pool of molten Flibe. The Flibe will serve the multiple functions of breeding, cooling, shielding, and moderating. Therefore, the only structural material between the superconducting magnets and the plasma is the first wall. The first wall is a stand-alone structure with no coolant connection and is cooled by Flibe at the atmospheric pressure. There is also no need of the primary coolant loop. The design is expected to improve the safety, reliability, and maintainability aspects of the fusion system.
Sze, D.K.
Basics of Fusion-Fissison Research Facility (FFRF) as a Fusion Neutron Source
FFRF, standing for the Fusion-Fission Research Facility represents an option for the next step project of ASIPP (Hefei, China) aiming to a first fusion-fission multifunctional device [1]. FFRF strongly relies on new, Lithium Wall Fusion plasma regimes, the development of which has already started in the US and China. With R/a=4/1m/m, Ipl=5 MA, Btor=4-6 T, PDT=50- 100 MW, Pfission=80-4000MW, 1 m thick blanket, FFRF has a unique fusion mission of a stationary fusion neutron source. Its pioneering mission of merging fusion and fission consists in accumulation of design, experimental, and operational data for future hybrid applications.
Leonid E. Zakharov
The heat transport system and plant design for the HYLIFE-2 fusion reactor
HYLIFE is the name given to a family of self-healing liquid-wall reactor concepts for inertial confinement fusion. This HYLIFE-II concept employs the molten salt, Flibe, for the liquid jets instead of liquid lithium used in the original HYLIFE-I study. A preliminary conceptual design study of the heat transport system and the balance of plant of the HYLIFE-II fusion power plant is described in this paper with special emphasis on a scoping study to determine the best intermediate heat exchanger geometry and flow conditions for minimum cost of electricity. 11 refs., 8 figs.
Hoffman, M.A.
Fusion Engineering and Design 54 (2001) 181247 On the exploration of innovative concepts for fusion
for fusion chamber technology M.A. Abdou a, *, The APEX TEAM, A. Ying a , N. Morley a , K. Gulec a , S-310-8252599. E-mail address: firstname.lastname@example.com (M.A. Abdou). 0920-3796/01/$ - see front matter © 2001 Elsevier Science B.V. All rights reserved. PII: S0920-3796(00)00433-6 #12;M.A. Abdou et al. / Fusion
Journal of Fusion Energy, Vol. 19, No. 1, March 2000 ( 2001) Review of the Fusion Materials Research Program
, Livermore, CA 94551. 6 University of Wisconsin, Madison, WI 53706. 7 Columbia University, New York, NY 10027Journal of Fusion Energy, Vol. 19, No. 1, March 2000 ( 2001) Review of the Fusion Materials.S. Department of Energy (DOE) Fusion Energy Sciences Advisory Committee Panel on the Review of the Fusion
Fusion Technologies for Tritium-Suppressed D-D Fusion White Paper prepared for FESAC Materials Science Subcommittee
1 Fusion Technologies for Tritium-Suppressed D-D Fusion White Paper prepared for FESAC Materials for tritium-suppressed D-D fusion and the understanding of the turbulent pinch in magnetically confined plasma pathway. Tritium- suppressed D-D fusion eliminates the need to breed fuel from lithium, reduces the damage
Journal of Fusion Energy, Vol. 15, Nos. 3/4, 1996 Report of the FESAC Inertial Fusion Energy Review Panel
Journal of Fusion Energy, Vol. 15, Nos. 3/4, 1996 Report of the FESAC Inertial Fusion Energy Review on a specific recommendation made by your Committee in its report, "A Restructured Fusion Energy Sciences Pro Committee report of 1990, we had taken as our highest priority in inertial fusion energy the development
The ITERThe ITER eraera : the 10: the 10 yearyear roadmaproadmap for the French fusion programmefor the French fusion programme
-2035 : The Fusion Energy Era of magnetic fusion research ITER thermonuclear plasmasITER thermonuclear plasmasThe ITERThe ITER eraera : the 10: the 10 yearyear roadmaproadmap for the French fusion programmefor the French fusion programme E. Tsitrone1 on behalf of IRFM and Tore Supra team 1 : CEA, IRFM, F-13108 Saint
Rho GTPase activity modulates paramyxovirus fusion protein-mediated cell-cell fusion
The paramyxovirus fusion protein (F) promotes fusion of the viral envelope with the plasma membrane of target cells as well as cell-cell fusion. The plasma membrane is closely associated with the actin cytoskeleton, but the role of actin dynamics in paramyxovirus F-mediated membrane fusion is unclear. We examined cell-cell fusion promoted by two different paramyxovirus F proteins in three cell types in the presence of constitutively active Rho family GTPases, major cellular coordinators of actin dynamics. Reporter gene and syncytia assays demonstrated that expression of either Rac1{sup V12} or Cdc42{sup V12} could increase cell-cell fusion promoted by the Hendra or SV5 glycoproteins, though the effect was dependent on the cell type expressing the viral glycoproteins. In contrast, RhoA{sup L63} decreased cell-cell fusion promoted by Hendra glycoproteins but had little affect on SV5 F-mediated fusion. Also, data suggested that GTPase activation in the viral glycoprotein-containing cell was primarily responsible for changes in fusion. Additionally, we found that activated Cdc42 promoted nuclear rearrangement in syncytia.
Schowalter, Rachel M. [Department of Molecular and Cellular Biochemistry, University of Kentucky, 741 South Limestone, Lexington, KY 40536-0509 (United States); Wurth, Mark A. [Department of Molecular and Cellular Biochemistry, University of Kentucky, 741 South Limestone, Lexington, KY 40536-0509 (United States); Aguilar, Hector C. [Department of Microbiology, Immunology and Molecular Genetics, UCLA, Los Angeles, CA 90095 (United States); Lee, Benhur [Department of Microbiology, Immunology and Molecular Genetics, UCLA, Los Angeles, CA 90095 (United States); Moncman, Carole L. [Department of Molecular and Cellular Biochemistry, University of Kentucky, 741 South Limestone, Lexington, KY 40536-0509 (United States); McCann, Richard O. [Department of Molecular and Cellular Biochemistry, University of Kentucky, 741 South Limestone, Lexington, KY 40536-0509 (United States); Dutch, Rebecca Ellis [Department of Molecular and Cellular Biochemistry, University of Kentucky, 741 South Limestone, Lexington, KY 40536-0509 (United States)]. E-mail: firstname.lastname@example.com
Achieving Energy Efficiency in Exis0ng Buildings How achieve significant commercial building energy efficiency?
· Led BU Energy Audit over past 3 years · University Sustainability CommiAchieving Energy Efficiency in Exis0ng Buildings ·How achieve significant commercial building energy efficiency? Focus on HVAC. ·Our solu0on
Hutyra, Lucy R.
Current Activities Assessing Butt Fusion Joint Integrity in High Density Polyethylene Piping
The Pacific Northwest National Laboratory (PNNL) in Richland, Washington, conducted initial studies to evaluate the effectiveness of nondestructive examinations (NDE) coupled with mechanical testing for assessing butt fusion joint integrity in high density polyethylene (HDPE) pipe. The work provided insightful information to the United States Nuclear Regulatory Commission (NRC) on the effectiveness of volumetric inspection techniques for detecting lack of fusion (LOF) conditions in the fusion joints. HDPE has been installed on a limited basis in American Society of Mechanical Engineers (ASME) Class 3, buried piping systems at several operating U.S. nuclear power plants and has been proposed for use in new construction. A comparison was made between the results from ultrasonic and microwave nondestructive examinations and the results from mechanical destructive evaluations, specifically the high-speed tensile test and the side-bend test, for determining joint integrity. The data comparison revealed that none of the NDE techniques detected all of the lack-of-fusion conditions that were revealed by the destructive tests. Follow-on work has recently been initiated at PNNL to accurately characterize the NDE responses from machined flaws of varying size and location in PE 4710 materials as well as the LOF condition. This effort is directed at quantifying the ability of volumetric NDE techniques to detect flaws in relation to the critical flaw size associated with joint integrity. A status of these latest investigations is presented.
Crawford, Susan L.; Cinson, Anthony D.; Doctor, Steven R.; Denslow, Kayte M.
Potential inversion with subbarrier fusion data revisited
We invert experimental data for heavy-ion fusion reactions at energies well below the Coulomb barrier in order to directly determine the internucleus potential between the colliding nuclei. In contrast to the previous applications of the inversion formula, we explicitly take into account the effect of channel couplings on fusion reactions, by assuming that fusion cross sections at deep subbarrier energies are governed by the lowest barrier in the barrier distribution. We apply this procedure to the $^{16}$O +$^{144}$Sm and $^{16}$O +$^{208}$Pb reactions, and find that the inverted internucleus potential are much thicker than phenomenological potentials. A relation to the steep fall-off phenomenon of fusion cross sections recently found at deep subbarrier energies is also discussed.
K. Hagino; Y. Watanabe
Fusion in the W_3 algebra
We develop the notions of fusion for representations of the W_3 algebra along the lines of Feigin and Fuchs. We present some explicit calculations for a W_3 minimal model.
G. M. T. Watts
Renew Workshop on Fusion-Fission Hybrids
of Final Report #12;4 The Workshop Sponsored by OFES, NE, NNSA About 100 attendees From fusion (DOE) DOE NNSA perspective Kirk Levedahl (DOE) Nuclear industry perspective Adrian Heymer (NEI
Fusion materials modeling: Challenges and opportunities
The plasma facing components, first wall, and blanket systems of future tokamak-based fusion power plants arguably represent the single greatest materials engineering challenge of all time. Indeed, the United States National ...
Wirth, B. D.
Not So Permafrost Viewport for Nuclear Fusion
Not So Permafrost Under Fire Viewport for Nuclear Fusion Hassle-Free Uranium 1663 LOS ALAMOS role in deterring aggression during the tenuous Cold War years. Following the Cold War, the nation
Fusion Development Path Panel Preliminary Report
Laboratory · Grant Logan, Lawrence Berkeley National Laboratory · Kathryn McCarthy, Idaho National. #12;Principles: Portfolio Management (a) The plan recognizes that difficult scientific opportunities for moving forward with fusion energy and they face largely independent scientific
Alloy Design for a Fusion Power Plant
Fusion power is generated when hot deuterium and tritium nuclei react, producing alpha particles and 14 MeV neutrons. These neutrons escape the reaction plasma and are absorbed by the surrounding material structure of the plant, transferring...
Kemp, Richard
Data Fusion for Improved Respiration Rate Estimation
We present an application of a modified Kalman-Filter (KF) framework for data fusion to the estimation of respiratory rate from multiple physiological sources which is robust to background noise. A novel index of the ...
Nemati, Shamim
Heavy-Ion Fusion Accelerator Research, 1991
This report discusses the following topics: research with multiple- beam experiment MBE-4; induction linac systems experiments; and long- range research and development of heavy-ion fusion accelerators.
From Earth to Saturn: Los Alamos Achievements
A compilation of some of the remarkable achievements of Los Alamos National Laboratory staff over the past 12 months. Originally aired in the June 26, 2008 Director's all-employee meeting.
McMillan, Charlie; Wilson, Cathy; Nekimkem, Howard; Martinez, Johnnie; Martz, Joe; Albright, Brian
Studies at the Pacific Northwest National Laboratory (PNNL) in Richland, Washington, are being conducted to evaluate nondestructive examinations (NDE) coupled with mechanical testing of butt fusion joints in high density polyethylene (HDPE) pipe for assessing lack of fusion. The work provides information to the United States Nuclear Regulatory Commission (NRC) on the effectiveness of volumetric inspection techniques of HDPE butt fusion joints in Section III, Division 1, Class 3, buried piping systems in nuclear power plants. This paper describes results from preliminary assessments using ultrasonic and microwave nondestructive techniques and mechanical testing with the high speed tensile impact test and the bend test for determining joint integrity. A series of butt joints were fabricated in 3408, 12 inch (30.5 cm) IPS DR-11 HDPE material by varying the fusion parameters to create good joints and joints containing a range of lack of fusion conditions. Six of these butt joints were volumetrically examined with time of flight diffraction (TOFD), phased array (PA) ultrasound, and the Evisive microwave system. The outer diameter (OD) weld beads were removed for microwave evaluation and the pipes ultrasonically re-evaluated. In two of the six pipes both the outer and inner diameter (ID) weld beads were removed and the pipe joints re-evaluated. Several of the pipes were sectioned and the joints destructively evaluated with the following techniques: high speed tensile test, bend test, and focused immersion ultrasound on a joint section removed from the pipe coupled with slicing through the joint and examining the revealed surfaces. The fusion parameters, nondestructive, and destructive evaluation results will be correlated to validate the effectiveness of what each NDE technology detects and what each does not detect. This is an initial limited study which will aid in identifying key future work.
Low Voltage White Phosphorescent OLED Achievements
Universal Display Corporation (UDC) and its research partners at Princeton University and the University of Southern California have succeeded in developing a white phosphorescent OLED (PHOLED�) that achieved a record efficiency of 20 lumens per watt. This achievement is the result of the team's collaborative efforts to increase the efficiency of PHOLED lighting by focusing on two critical factors: lowering the drive voltages and increasing the amount of light extracted.
Implications of Theoretical Ideas Regarding Cold Fusion
A lot of theoretical ideas have been floated to explain the so called cold fusion phenomenon. I look at a large subset of these and study further physical implications of the concepts involved. I suggest that these can be tested by other independent physical means. Because of the significance of these the experimentalists are urged to look for these signatures. The results in turn will be important for a better understanding and hence control of the cold fusion phenomenon.
Afsar Abbas
Nuclear fusion as a probe for octupole deformation in $^{224}$Ra
$\\textit{Background}$: Nuclear fusion has been shown to be a perfect probe to study the different nuclear shapes. However, the possibility of testing octupole deformation of a nucleus with this tool has not been fully explored yet. The presence of a stactic octupole deformation in nuclei will enhanced a possible permanent electric dipole moment, leading to a possible demonstration of parity violation. $\\textit{Purpose}$: To check whether static octupole deformation or octupole vibration in fusion give qualitatively different results so that both situations can be experimentally disentangled. $\\textit{Method}$: Fusion cross sections are computed in the Coupled-Channels formalism making use of the Ingoing-Wave Boundary Conditions (IWBC) for the systems $^{16}$O+$^{144}$Ba and $^{16}$O+$^{224}$Ra. $\\textit{Results}$: Barrier distributions of the two considered schemes show different patterns. For the $^{224}$Ra case, the octupole deformation parameter is large enough to create a sizeable difference. $\\textit{Con...
Kumar, Raj; Vitturi, A
Femtosecond spectroscopy probes the folding quality of antibody fragments expressed as GFP fusions in the cytoplasm
Time-resolved femtosecond spectroscopy can improve the application of green fluorescent proteins (GFPs) as protein-folding reporters. The study of ultrafast excited-state dynamics (ESD) of GFP fused to single chain variable fragment (scFv) antibody fragments, allowed us to define and measure an empirical parameter that only depends on the folding quality (FQ) of the fusion. This method has been applied to the analysis of genetic fusions expressed in the bacterial cytoplasm and allowed us to distinguish folded and thus functional antibody fragments (high FQ) with respect to misfolded antibody fragments. Moreover, these findings were strongly correlated to the behavior of the same scFvs expressed in animal cells. This method is based on the sensitivity of the ESD to the modifications in the tertiary structure of the GFP induced by the aggregation state of the fusion partner. This approach may be applicable to the study of the FQ of polypeptides over-expressed under reducing conditions.
Didier, P. [Faculte de Pharmacie, UMR 7175, 74, route du Rhin, 67412 Illkirch (France); Weiss, E.; Sibler, A.-P. [Ecole Superieure de Biotechnologie de Strasbourg, UMR 7175, Boulevard Sebastien Brant, F-67412 Illkirch (France); Philibert, P.; Martineau, P. [Centre de recherche en cancerologie de Montpellier, UMR 5160, Val d'Aurelle-Paul Lamarque, 34298 Montpellier cedex 5 (France); Bigot, J.-Y. [Institut de Physique et Chimie des Materiaux de Strasbourg, UMR 7504, 23, rue du Loess, F-67037 Strasbourg (France); Guidoni, L. [Institut de Physique et Chimie des Materiaux de Strasbourg, UMR 7504, 23, rue du Loess, F-67037 Strasbourg (France); Laboratoire Materiaux et Phenomenes Quantiques, UMR 7162, Batiment Condorcet, 10 rue Alice Domon et Leonie Duquet, 75205 Paris cedex 13 (France)], E-mail: email@example.com
The Fast Track to Fusion Power
World energy use is predicted to double in the next 40 years. Today, 80% is provided by burning fossil fuels, but this is not sustainable indefinitely because (i) it is driving climate change, and (ii) fossil fuels will eventually be exhausted (starting with oil). The resulting potential energy crisis requires increased investment in energy research and development (which is currently very small on the scale of the $3 trillion p.a. energy market, and falling). The wide portfolio of energy work that should be supported must include fusion, which is one of very few options that are capable in principle of supplying a large fraction of need in an environmentally responsible manner. The case for fusion has been strengthened by recent advances in plasma physics and fusion technology and by studies of fusion power plants that address safety and cost issues. The big questions are, 'How can we deliver fusion power as fast as possible?' and 'How long is it likely to take?' I will review progress in fusion, and argue for a focused fast-track program that could deliver a working prototype power station in less than 30 years.
Smith, Chris Llewellyn (UKAEA, Culham) [UKAEA, Culham
Safety of magnetic fusion facilities: Guidance
This document provides guidance for the implementation of the requirements identified in DOE-STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While the requirements in DOE-STD-6002-96 are generally applicable to a wide range of fusion facilities, this Standard, DOE-STD-6003-96, is concerned mainly with the implementation of those requirements in large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This Standard is oriented toward regulation in the Department of Energy (DOE) environment as opposed to regulation by other regulatory agencies. As the need for guidance involving other types of fusion facilities or other regulatory environments emerges, additional guidance volumes should be prepared. The concepts, processes, and recommendations set forth here are for guidance only. They will contribute to safety at magnetic fusion facilities.
1-1 ROLE OF FUSION ENERGY IN A SUSTAINABLE GLOBAL ENERGY STRATEGY R�LE DE L'�NERGIE DE FUSION DANS. 1. Introduction 1. Introduction 1.1. Fusion energy 1.1. Energie de fusion Fusion energy is one of only a few truly long-term energy options. Since its inception in the 1950s, the vision of the fusion
1-1 ROLE OF FUSION ENERGY IN A SUSTAINABLE GLOBAL ENERGY STRATEGY R� LE DE L'�NERGIE DE FUSION DANS. 1. Introduction 1. Introduction 1.1. Fusion energy 1.1. Energie de fusion Fusion energy is one of only a few truly long-term energy options. Since its inception in the 1950s, the vision of the fusion
Laser Fusion: The First Ten Years 1962-1972
This account of the beginning of the program on laser fusion at Livermore in 1962, and its subsequent development during the decade ending in 1972, was originally prepared as a contribution to the January 1991 symposium 'Achievements in Physics' honoring Professor Keith Brueckner upon his retirement from the University of San Diego at La Jolla. It is a personal recollection of work at Livermore from my vantage point as its scientific leader, and of events elsewhere that I thought significant. This period was one of rapid growth in which the technology of high-power short-pulse lasers needed to drive the implosion of thermonuclear fuel to the temperature and density needed for ignition was developed, and in which the physics of the interaction of intense light with plasmas was explored both theoretically and experimentally.
Kidder, R E
The 2013 International Workshop on Cloud Enhanced Information Fusion (CloudFusion'2013) http://bingweb.binghamton.edu/~ychen/CloudFusion2013.htm
and design, experimental studies, and social impacts of advanced cloud enhanced information fusion, open problems, new application challenges, visionary ideas, and preliminary studies. The topics include data computations, retrieval, and storage. Information fusion filters and combines useful data
Chen, Yu
Environmental Challenges of Climate-Nuclear Fusion: A Case Study of India
Challenges of Climate- Nuclear Fusion: A Case Study of Indiatext. CHALLENGES OF CLIMATE-NUCLEAR FUSION waste management,CHALLENGES OF CLIMATE-NUCLEAR FUSION granting construction
Badrinarayan, Deepa
Influence of projectile neutron number on cross section in cold fusion reactions
ON CROSS SECTION IN COLD FUSION REACTIONS I. Dragojevi? ,type of reaction has been referred to as �cold fusion. �The study of cold fusion reactions is an indispensable
Dragojevic, I.
E-Print Network 3.0 - anisotropic d-d fusion Sample Search Results
F. Leipold1 Summary: and Fusion Center, Cambridge, MA 02139, USA Introduction Plasmas for thermonuclear fusion contain a highly... in the deuterium-tritium fusion reaction which is...
Fusion reactor breeder material safety compatibility studies
Tritium breeder material selection for fusion reactors is strongly influenced by the desire to minimize safety and environmental concerns. Breeder material safety compatibility studies are being conducted to identify and characterize breeder-coolant-material interactions under postulated reactor accident conditions. Recently completed scoping compatibility tests indicate the following. 1. Ternary oxides (LiAlO/sub 2/, Li/sub 2/ZrO/sub 3/, Li/sub 2/SiO/sub 3/, Li/sub 4/SiO/sub 4/, and LiTiO/sub 3/) at postulated blanket operating temperatures are chemically compatible with water coolant, while liquid lithium and Li/sub 7/Pb/sub 2/ reactions with water generate heat, aerosol, and hydrogen. 2. Lithium oxide and 17Li-83Pb alloy react mildly with water requiring special precautions to control hydrogen release. 3. Liquid lithium reacts substantially, while 17Li83Pb alloy reacts mildly with concrete to produce hydrogen. 4. Liquid lithium-air reactions may present some major safety concerns. Additional scoping tests are needed, but the ternary oxides, lithium oxide, and 17Li-83Pb have definite safety advantages over liquid lithium and Li/sub 7/Pb/sub 2/. The ternary oxides present minimal safetyrelated problems when used with water as coolant, air or concrete; but they do require neutron multipliers, which may have safety compatibility concerns with surrounding materials. The combined favorable neutronics and minor safety compatibility concerns of lithium oxide and 17Li-83Pb make them prime candidates as breeder materials. Current safety efforts are directed toward assessing the compatibility of lithium oxide and the lithium-lead alloy with coolants and other materials.
Jeppson, D.W.; Cohen, S.; Muhlestein, L.D.
Fusion transmutation of waste and the role of the In-Zinerator in the nuclear fuel cycle.
The Z-Pinch fusion experiment at Sandia National Laboratories has been making significant progress in developing a high-energy fusion neutron source. This source has the potential to be used for the transmutation of nuclear waste. The goal of this research was to do a scoping-level design of a fusion-based transmuter to determine potential transmutation rates along with the fusion yield requirements. Two ''In-Zinerator'' designs have been developed to transmute the long-lived actinides that dominate the heat production in spent fuel. The first design burns up all transuranics (TRU) in spent fuel (Np, Pu, Am, Cm), and the second is focused only on burning up Am and Cm. The TRU In-Zinerator is designed for a fuel cycle requiring burners to get rid of all the TRU with no light water reactor (LWR) recycle. The Am/Cm In-Zinerator is designed for a fuel cycle with Np/Pu recycling in LWRs. Both types of In-Zinerators operate with a moderate fusion source driving a sub-critical actinide blanket. The neutron multiplication is 30, so a great deal of energy is produced in the blanket. With the design goal of generating 3,000 MW{sub th}, about 1,200 kg/yr of actinides can be destroyed in each In-Zinerator. Each TRU In-Zinerator will require a 20 MW fusion source, and it will take a total of 20 units (each producing 3,000 MWth) to burn up the TRU as fast as the current LWR fleet can produce it. Each Am/Cm In-Zinerator will require a 24 MW fusion source, and it will take a total of 2 units to burn up the Am/Cm as fast as the current LWR fleet can produce it. The necessary fusion yield could be achieved using a 200-240 MJ target fired once every 10 seconds.
Cipiti, Benjamin B.
Science/Fusion Energy Sciences FY 2006 Congressional Budget Fusion Energy Sciences
radioactive waste. A science-based approach to fusion offers the most deliberate path to commercial fusion chips for computers and other electronic devices, advanced video displays, innovative materials coatings, and the efficient destruction of chemical and radioactive wastes. The FES program is also pushing the boundaries
FPN05-44 Fusion Program Notes -House Adopts Fusion Amendment Stephen O. Dean
(DOE) and that advocated by the U. S. fusion community and the Congress. The latter, a hard won consensus, advocates a policy in which ITER is funded by funds over and above the existing core domestic fusion budget, while the DOE seems determined to fund much of the ITER costs by cutting the domestic
Selection London (1859) #12;Hermann von Helmholtz Conservation of Energy Conversion of Mechanical Energy of the =Sun 264 10 Watts�? Potential energy Solar power out Su pu n's lifetime t 14 6 10 .sec= �?= The Sun wouldDANCING WITH THE STARSDANCING WITH THE STARS QUEST FOR FUSION ENERGYQUEST FOR FUSION ENERGY Abhay
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Fusion Technology at
, very challenging heat transfer and material problem critical to the success of fusion which drives 10 of 11 Some current research at CCFE · "Heat Transfer enhancement for fusion power plant divertors at CCFE David Hancock #12;PhD and Masters Open Day 15th November 2012slide 2 of 11 Objectives · The role
Fusion EnergyFusion Energy Powering the XXI centuryPowering the XXI century
that the main cause of recent global warming is atmospheric pollution 20th International Atomic Energy AgencyNuclear Fusion (Safe & low level radioactive(Safe & low level radioactive waste, no atmospheric pollution)waste, no atmospheric pollution) 20th International Atomic Energy Agency, Fusion Energy Conference, Vilamoura, Portugal
Energetic Particle Physics In Fusion Research In Preparation For Burning Plasma Experiments
The area of energetic particle (EP) physics of fusion research has been actively and extensively researched in recent decades. The progress achieved in advancing and understanding EP physics has been substantial since the last comprehensive review on this topic by W.W. Heidbrink and G.J. Sadler [1]. That review coincided with the start of deuterium-tritium (DT) experiments on Tokamak Fusion Test reactor (TFTR) and full scale fusion alphas physics studies. Fusion research in recent years has been influenced by EP physics in many ways including the limitations imposed by the "sea" of Alfven eigenmodes (AE) in particular by the toroidicityinduced AEs (TAE) modes and reversed shear Alfven (RSAE). In present paper we attempt a broad review of EP physics progress in tokamaks and spherical tori since the first DT experiments on TFTR and JET (Joint European Torus) including helical/stellarator devices. Introductory discussions on basic ingredients of EP physics, i.e. particle orbits in STs, fundamental diagnostic techniques of EPs and instabilities, wave particle resonances and others are given to help understanding the advanced topics of EP physics. At the end we cover important and interesting physics issues toward the burning plasma experiments such as ITER (International Thermonuclear Experimental Reactor).
Gorelenkov, Nikolai N [PPPL
Fusion in coset CFT from admissible singular-vector decoupling
Fusion rules for Wess-Zumino-Witten (WZW) models at fractional level can be defined in two ways, with distinct results. The Verlinde formula yields fusion coefficients that can be negative. These signs cancel in coset fusion rules, however. On the other hand, the fusion coefficients calculated from decoupling of singular vectors are non-negative. They produce incorrect coset fusion rules, however, when factorisation is assumed. Here we give two prescriptions that yield the correct coset fusion rules from those found for the WZW models by the decoupling method. We restrict to the Virasoro minimal models for simplicity, and because decoupling results are only complete in the $\\su(2)$ case.
P. Mathieu; J. Rasmussen; M. A. Walton
Report of the Integrated Program Planning Activity for the DOE Fusion Energy Sciences Program
This report of the Integrated Program Planning Activity (IPPA) has been prepared in response to a recommendation by the Secretary of Energy Advisory Board that, ''Given the complex nature of the fusion effort, an integrated program planning process is an absolute necessity.'' We, therefore, undertook this activity in order to integrate the various elements of the program, to improve communication and performance accountability across the program, and to show the inter-connectedness and inter-dependency of the diverse parts of the national fusion energy sciences program. This report is based on the September 1999 Fusion Energy Sciences Advisory Committee's (FESAC) report ''Priorities and Balance within the Fusion Energy Sciences Program''. In its December 5,2000, letter to the Director of the Office of Science, the FESAC has reaffirmed the validity of the September 1999 report and stated that the IPPA presents a framework and process to guide the achievement of the 5-year goals listed in the 1999 report. The National Research Council's (NRC) Fusion Assessment Committee draft final report ''An Assessment of the Department of Energy's Office of Fusion Energy Sciences Program'', reviewing the quality of the science in the program, was made available after the IPPA report had been completed. The IPPA report is, nevertheless, consistent with the recommendations in the NRC report. In addition to program goals and the related 5-year, 10-year, and 15-year objectives, this report elaborates on the scientific issues associated with each of these objectives. The report also makes clear the relationships among the various program elements, and cites these relationships as the reason why integrated program planning is essential. In particular, while focusing on the science conducted by the program, the report addresses the important balances between the science and energy goals of the program, between the MFE and IFE approaches, and between the domestic and international aspects of the program. The report also outlines a process for establishing a database for the fusion research program that will indicate how each research element fits into the overall program. This database will also include near-term milestones associated with each research element, and will facilitate assessments of the balance within the program at different levels. The Office of Fusion Energy Sciences plans to begin assembling and using the database in the Spring of 2001 as we receive proposals from our laboratories and begin to prepare our budget proposal for Fiscal Year 2003.
2 Key Achievements 7 Greenhouse Gas Reduction
Princeton University Reports Contents 2 Key Achievements 7 Greenhouse Gas Reduction Campus Energy was established in 2008, the University has invested $5.3 million in energy-savings projects, resulting in annual of a 5.2-megawatt solar collector field. · Audit the remaining 20 of the top 50 energy- consuming
Nano-Machines Achieve Huge Mechanical Breakthrough
NANO TECH Nano-Machines Achieve Huge Mechanical Breakthrough Dublin, Ireland (SPX) Sep 08, 2005 that use molecular 'nano'-machines of this kind to help perform physical tasks. Nano-machines could also owners set to return to battered Orleans l Six dead, two missing after heavy rains hit Page 1 of 3Nano
Leigh, David A.
achieving economic growth: Topics by E-print Network
remain simpleITERATIVE COMBINATORIAL AUCTIONS: ACHIEVING ECONOMIC AND COMPUTATIONAL EFFICIENCY David Christopher Chen, Yiling 6 ITERATIVE COMBINATORIAL AUCTIONS: ACHIEVING...
Observation of nuclear fusion driven by a pyroelectric crystalQ1
in a room temperature solid-state setting, including `cold' fusion5 and `bubble' fusion6 , have met.............................................................. Observation of nuclear fusion driven ............................................................................................................................................................................. While progress in fusion research continues with magnetic1 and inertial2 confinement, alternative
Gimzewski, James
Symplectic fusion rings and their metric
The fusion of fields in a rational conformal field theory gives rise to a ring structure which has a very particular form. All such rings studied so far were shown to arise from some potentials. In this paper the fusion rings of the WZW models based on the symplectic group are studied. It is shown that they indeed arise from potentials which are described. These potentials give rise to new massive perturbations of superconformal hermitian symmetric models. The metric of the perturbation is computed and is shown to be given by solutions of the sinh--gordon equation. The kink structure of the theories is described, and it is argued that these field theories are integrable. The $S$ matrices for the fusion theories are argued to be non--minimal extensions of the $G_k\\times G_1/ G_{k+1}$ $S$ matrices with the adjoint perturbation, in the case of $G=SU(N)$.
D. Gepner; A. Schwimmer
Progress in Fusion Materials Research
reactors � Qualification requires all of the mechanical property testing on unirradiated material, plus. Koizumi et al., Proc. Int. Gas Turbines Conf., 2003, paper TS-119 #12;6 Managed by UT-Battelle for the U is strongly dependent on annealing conditions FHR: fast heating rate (>1000�C/min) SFR: slow heating rate (10
antireceptor antibody-photosensitizer fusion: Topics by E-print...
U N C L A S S I F I E D Operated by the Los Alamos National Security, LLC for the DOENNSA Slide 2 147 MIT Plasma Science and Fusion Center Fusion Technology & Engineering...
An architectural selection framework for data fusion in sensor platforms
The role of data fusion in sensor platforms is becoming increasingly important in various domains of science, technology and business. Fusion pertains to the merging or integration of information towards an enhanced level ...
Mirza, Atif R
Vintage DOE: What is Fusion | Department of Energy
Vintage DOE: What is Fusion Vintage DOE: What is Fusion January 10, 2011 - 12:45pm Addthis Ginny Simmons Ginny Simmons Former Managing Editor for Energy.gov, Office of Public...
Accelerator Fusion Research Division 1991 summary of activities
This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations.
Accelerator & Fusion Research Division 1991 summary of activities
Accelerator and fusion research division. 1992 Summary of activities
This report contains brief discussions on research topics in the following area: Heavy-Ion Fusion Accelerator Research; Magnetic Fusion Energy; Advanced Light Source; Center for Beam Physics; Superconducting Magnets; and Bevalac Operations.
XII-109/ 96 May 1996 REFLECTIONS ON FUSION.FUTURE
, and requires a higher capital investment. The shielding necessary to protect the superconducting coils. #12;2. FUSION RESEARCH GENERAL `Ihe fusion program is can-ied out by the main developed countries
Fusion cross sections at deep subbarrier energies
A recent publication reports that heavy-ion fusion cross sections at extreme subbarrier energies show a continuous change of their logarithmic slope with decreasing energy, resulting in a much steeper excitation function compared with theoretical predictions. We show that the energy dependence of this slope is partly due to the asymmetric shape of the Coulomb barrier, that is its deviation from a harmonic shape. We also point out that the large low-energy slope is consistent with the surprisingly large surface diffusenesses required to fit recent high-precision fusion data.
K. Hagino; N. Rowley; M. Dasgupta
Compressed Gas Safety for Experimental Fusion Facilities
Experimental fusion facilities present a variety of hazards to the operators and staff. There are unique or specialized hazards, including magnetic fields, cryogens, radio frequency emissions, and vacuum reservoirs. There are also more general industrial hazards, such as a wide variety of electrical power, pressurized air and cooling water systems in use, there are crane and hoist loads, working at height, and handling compressed gas cylinders. This paper outlines the projectile hazard associated with compressed gas cylinders and methods of treatment to provide for compressed gas safety. This information should be of interest to personnel at both magnetic and inertial fusion experiments.
Cadwallader, L.C. [Idaho National Engineering and Environmental Laboratory (United States)
Topological Matter, Integrable Models and Fusion Rings
We show how topological $G_k/G_k$ models can be embedded into the topological matter models that are obtained by perturbing the twisted $N=2$ supersymmetric, hermitian symmetric, coset models. In particular, this leads to an embedding of the fusion ring of $G$ as a sub-ring of the perturbed, chiral primary ring. The perturbation of the twisted $N=2$ model that leads to the fusion ring is also shown to lead to an integrable $N=2$ supersymmetric field theory when the untwisted $N=2$ superconformal field theory is perturbed by the same operator and its hermitian conjugate.
D. Nemeschansky; N. P. Warner
Pairing Effects in Nuclear Fusion Reaction
We simulate a heavy-ion collision using the canonical-basis time-dependent Hartree-Fock-Bogoliubov theory (Cb-TDHFB) treating pairing correlation in the three-dimensional coordinate space. We apply the Cb-TDHFB to 22O+22O collision with a contact-type pairing energy functional, and compare results of Cb-TDHFB and TDHF to investigate the effects of pairing correlations in nuclear fusion. Our results seem to indicate that pairing effects do not increase the fusion cross section in this system.
Shuichiro Ebata; Takashi Nakatsukasa
Fusion Propulsion and Power for Future Flight
There are innovative magnetic and electric confinement fusion power and propulsion system designs with potential for: vacuum specific impulses of 1500-2000 seconds with rocket engine thrust/mass ratios of 5-10 g`s; environmentally favorable exhaust emissions if aneutronic fusion propellants can be used; a 2 to 3-fold reduction in the mass of hypersonic airliners and SSTO aerospace planes; a 10 to 20 fold reduction in Mars expedition mass and cost (if propellant from planetary atmospheres is used); and feasibility or in-feasibility of these systems could be confirmed with a modest applied research and exploratory development cost.
Froning, H.D. Jr.
First wall for polarized fusion reactors
A first-wall or first-wall coating for use in a fusion reactor having polarized fuel may be formed of a low-Z non-metallic material having slow spin relaxation, i.e., a depolarization rate greater than 1 sec/sup -1/. Materials having these properties include hydrogenated and deuterated amorphous semiconductors. A method for preventing the rapid depolarization of a polarized plasma in a fusion device may comprise the step of providing a first-wall or first-wall coating formed of a low-Z, non-metallic material having a depolarization rate greater than 1 sec/sup -1/.
Greenside, H.S.; Budny, R.V.; Post, D.E. Jr.
Experimental fusion facilities present a variety of hazards to the operators and staff. There are unique or specialized hazards, including magnetic fields, cryogens, radio frequency emissions, and vacuum reservoirs. There are also more general industrial hazards, such as a wide variety of electrical power, pressurized air, and cooling water systems in use, there are crane and hoist loads, working at height, and handling compressed gas cylinders. This paper outlines the projectile hazard assoicated with compressed gas cylinders and mthods of treatment to provide for compressed gas safety. This information should be of interest to personnel at both magnetic and inertial fusion experiments.
Lee C. Cadwallader
Accelerator-based fusion with a low temperature target
Neutron generators are in use in a number of scientific and commercial endeavors. They function by triggering fusion reactions between accelerated ions (usually deuterons) and a stationary cold target (e.g., containing tritium). This setup has the potential to generate energy. It has been shown that if the energy transfer between injected ions and target electrons is sufficiently small, net energy gain can be achieved. Three possible avenues are: (a) a hot target with high electron temperature, (b) a cold non-neutral target with an electron deficiency, or (c) a cold target with a high Fermi energy. A study of the third possibility is reported in light of recent research that points to a new phase of hydrogen, which is hypothesized to be related to metallic hydrogen. As such, the target is considered to be composed of nuclei and delocalized electrons. The electrons are treated as conduction electrons, with the average minimum excitation energy being approximately equal to 40% of the Fermi energy. The Fermi energy is directly related to the electron density. Preliminary results indicate that if the claimed electron densities in the new phase of hydrogen were achieved in a target, the energy transfer to electrons would be small enough to allow net energy gain.
Phillips, R. E.; Ordonez, C. A. [Department of Physics, University of North Texas, Denton, Texas 76203-5017 (United States)
Fusion of Dilute $A_L$ Lattice Models
The fusion procedure is implemented for the dilute $A_L$ lattice models and a fusion hierarchy of functional equations with an $su(3)$ structure is derived for the fused transfer matrices. We also present the Bethe ansatz equations for the dilute $A_L$ lattice models and discuss their connection with the fusion hierarchy. The solution of the fusion hierarchy for the eigenvalue spectra of the dilute $A_L$ lattice models will be presented in a subsequent paper.
Yu-kui Zhou; Paul A. Pearce; Uwe Grimm
Real Time Monitoring: Achieving Energy Efficiency
ABSTRACT: IECBO?s International Conference for Enhanced Building Operations November 17-18, 2009 Austin, Texas. Energy @ Work www.Energy-Efficiency.com File: Rouse_ Abstract Contact: scott.rouse@energy-efficiency....com, (416) 402-0525 Proposal Type: o Electronic proposal for presentation Title of Paper: o Real Time Monitoring: Achieving Energy Efficiency! Conference: o ICEBO?s International Conference for Enhanced Building Operations Submitted by: o...
Rouse, S.
NNSA Highlights 2014 Achievements | National Nuclear Security
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Secretary's 2013 Achievement Awards | Department of Energy
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Secretary's 2014 Achievement Awards | Department of Energy
Energy Savers [EERE]
AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartment of Energyof the Americas | Department ofofDelivered |Technology4 Achievement
Fusion energy Fusion powers the Sun, and all stars, in which light nuclei fuse together at high temperatures
Fusion energy · Fusion powers the Sun, and all stars, in which light nuclei fuse together at high in excess of 100 million degrees, much higher than in the Sun. The hot hydrogen gas (known as a `plasma
Activities of the University Fusion Association! D.P. Brennan
.universityfusion.org! #12;STABILITY is extremely important in university funding! Our university programs in fusion science.! The stability of funding for fusion research is Key to the sustainment of a robust university communityActivities of the University Fusion Association! D.P. Brennan Princeton University Presented
A Cognitive Vision System for Nuclear Fusion Device Monitoring
to produce controlled thermonuclear fusion power by magnetic confinement of a plasma (fully ionized gasA Cognitive Vision System for Nuclear Fusion Device Monitoring Vincent Martin1 , Victor Moncada1 optimizations. The framework is generic and can be easily adapted to different fusion device environ- ments
23 Department of Advanced Energy Nuclear Fusion Research Education Program 22 8 24) (1) (2) (3) (4) (5) (6) (7) (8) #12;- 7 - 23 Guide to Nuclear Fusion Research firstname.lastname@example.com tel: 046-856-2121 12 http://www. k.u-tokyo.ac.jp/fusion-pro/ #12;- 3 - (1) TOEFL TOEIC
Fusion Nuclear Science and Technology (FNST) Challenges and Facilities
Fusion Nuclear Science and Technology (FNST) Challenges and Facilities on the Pathway to DEMO Princeton,NJ 7-10 September 2011 1 #12;Fusion Nuclear Science and Technology (FNST) must be the Central Mountain to climb Since we have never done any experiments on FNST in a real fusion nuclear environment, we
26 Department of Advanced Energy Nuclear Fusion Research Education Program 25 8 20) #12; 26 Guide to Nuclear Fusion Research Education Program 03-5841-6563 E-mail : ae: 050-336-27836 mail: firstname.lastname@example.com tel: 050-3362-5919 , 7 12 http://www. k.u-tokyo.ac.jp/fusion
NSTX Upgrade: ST research to accelerate fusion development
parameter regimes to advance predictive capability - for ITER and beyond � Develop ST as fusion energy-Z + Li Theme 4. Harnessing Fusion Power Leader in physics basis and design of low-A fusion systems Theme non-inductive ramp-up from ~0.4 1MA � HI-start-up Te, ne too low for fast-wave, NBI coupling need
Bold Step by the World to Fusion Energy: ITER
THE DESIGN OF ITER · ITER PROJECT & ROLE OF THE UNITED STATES · PATH FROM ITER TO PRACTICAL FUSION POWER #12;Elements of a D-T Fusion Energy System ~ D-Li Plasma Heating Drivers or Confinement Balance of PlantD = nT = n TOTAL THERMAL ENERGY IN FUSION FUEL, DEFINE "ENERGY CONFINEMENT TIME", E ENERGY BALANCE dW d
COLD FUSION ONE YEAR AFTER R. Battiston and C. Presilla
230 COLD FUSION ONE YEAR AFTER R. Battiston and C. Presilla Dipartimento di Fi$ica dell The one year long history of cold fusion is critically reviewed on the basis of the more recent results has of science. In this lecture we will discuss of the status of the cold fusion searches one year
Presilla, Carlo
Accelerator and Fusion Research Division 1989 summary of activities
This report discusses the research being conducted at Lawrence Berkeley Laboratory's Accelerator and Fusion Research Division. The main topics covered are: heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; high-energy physics technology; and bevalac operations.
Dynamic microscopic theory of fusion using DC-TDHF
The density-constrained time-dependent Hartree-Fock (DC-TDHF) theory is a fully microscopic approach for calculating heavy-ion interaction potentials and fusion cross sections below and above the fusion barrier. We discuss recent applications of DC-TDHF method to fusion of light and heavy systems.
Umar, A. S.; Oberacker, V. E.; Keser, R.; Maruhn, J. A.; Reinhard, P.-G. [Department of Physics and Astronomy, Vanderbilt University, Nashville, Tennessee 37235 (United States); RTE University, Science and Arts Faculty, Department of Physics, 53100, Rize (Turkey); Institut fuer Theoretische Physik, Goethe-Universitaet, D-60438 Frankfurt am Main (Germany); Institut fur Theoretische Physik, Universitat Erlangen, D-91054 Erlangen (Germany)
Energy Scaling Laws for Distributed Inference in Random Fusion Networks
the minimum spanning tree, and above by a suboptimal policy, referred to as Data Fusion for Markov Random, the policy with the minimum average energy consumption is bounded below by the average energy of fusion along models, Eu- clidean random graphs, stochastic geometry and data fusion. I. INTRODUCTION WE consider
Yukich, Joseph E.
Lasers and Inertial Confinement Fusion in the United States
thermonuclear device began the Inertial Confinement Fusion Era I1860 · StanislawUlamandEdward Teller developedLasers and Inertial Confinement Fusion in the United States R. L. McCrory Director and Vice Provost confinement fusion (ICF) has grown as successively larger lasers have been built I1859 · The
Fusion11 Conference Summary Carlos A. Bertulani,a
, the international project for thermonuclear fusion. This project (presently estimated at 15 billion euros) will open physics and material science. The generation of commercial en- ergy by using thermonuclear fusionFusion11 Conference Summary Carlos A. Bertulani,a Department of Physics and Astronomy, Texas A
Bertulani, Carlos A. - Department of Physics and Astronomy, Texas A&M University
Performance Characterization for Fusion Co-design Applications
fusion is a long-term solution for producing electrical power for the world, and the large thermonuclear1 Performance Characterization for Fusion Co-design Applications Praveen Narayanan, Alice Koniges international device (ITER) being constructed will produce net energy and a path to fusion energy provided
Oliker, Leonid
China To Build Its Own Fusion Reactor ENERGY TECH
Thermonuclear Experimental Reactor project reached agreement in Moscow Tuesday to construct the first fusion devices in thermonuclear reaction," and that "Chinese scientists started to develop a fusion operationChina To Build Its Own Fusion Reactor ENERGY TECH by Edward Lanfranco Beijing (UPI) July 1, 2005
Massachusetts Institute of Technology, Plasma Fusion Center, Technical Research Programs
A review is given of the technical programs carried out by the Plasma Fusion Center. The major divisions of work areas are applied plasma research, confinement experiments, fusion technology and engineering, and fusion systems. Some objectives and results of each program are described. (MOW)
The objectives of this research project are: (1) To design sensor data fusion algorithms that can synergistically combine defect related information from heterogeneous sensors used in gas pipeline inspection for reliably and accurately predicting the condition of the pipe-wall. (2) To develop efficient data management techniques for signals obtained during multisensor interrogation of a gas pipeline. During this reporting period, Rowan University fabricated test specimens with simulated defects for nondestructive evaluation (NDE); designed and developed two versions of a test platform for performing multi-sensor interrogation of test specimens under loaded conditions simulating pressurized gas pipelines; and performed magnetic flux leakage (MFL), ultrasonic testing (UT), thermal imaging and acoustic emission (AE) NDE on the test specimens. The data resulting from this work will be employed for designing multi-sensor data fusion algorithms.
Shreekanth Mandayam; Robi Polikar; John C. Chen
Heavy ion fusion science research for high energy density physics and fusion applications
cost direct plasma MHD direct conversion [38], as well as toT-lean targets and direct conversion for heavy ion fusion. [conversion loss of beam energy into x-rays. High ablation velocities with heavy ion direct
Logan, B.G.
IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014002 (10pp) doi:10.1088/0029-5515/50/1/014002
Harnessing the energy of thermonuclear fusion reactions is one of the greatest challenges of our time. FusionIOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014002 (10pp) doi:10.1088/0029-5515/50/1/014002 ITER on the road to fusion energy Kaname Ikeda Director
Direct Numerical Simulations of the Kraichnan Model: Scaling Exponents and Fusion Rules
We present results from direct numerical simulations of the Kraichnan model for passive scalar advection by a rapidly-varying random scaling velocity field for intermediate values of the velocity scaling exponent. These results are compared with the scaling exponents predicted for this model by Kraichnan. Further, we test the recently proposed fusion rules which govern the scaling properties of multi-point correlations, and present results on the linearity of the conditional statistics of the Laplacian operator on the scalar field.
Adrienne L. Fairhall; Barak Galanti; Victor S. L'vov; Itamar Procaccia
Cold fusion: Electrolytic processes. (Latest citations from the Inspec database). Published Search
The bibliography contains citations concerning the production of excess heat during the electrolysis of heavy water, known as cold fusion. Citations cover the design of electrolytic cells, cathode materials, and experimental conditions required to produce excess heat. Neutron emission and detection, calorimetry, and crystallography of the electrodes are discussed. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)
Thermo-Mechanical Response of a TRISO Fuel Particle in a Fusion/Fission Engine for Incineration of Weapons Grade Plutonium
The Laser Inertial Fusion-based (LIFE) engine is an advanced energy concept under development at Lawrence Livermore National Laboratory (LLNL). LIFE engine could be used to drive a subcritical fission blanket with fertile or fissile fuel. Current LIFE engine designs envisages fuel in pebble bed form with TRISO (tristructural isotropic) particles embedded in a graphite matrix, and pebbles flowing in molten salt Flibe (2LiF+BeF{sub 2}) coolant at T {approx} 700C. Weapons-grade plutonium (WGPu) fuel is an attractive option for LIFE engine involving the achievement of high fractional burnups in a short lifetime frame. However, WGPu LIFE engine operating conditions of high neutron fast fluence, high radiation damage, and high Helium and Hydrogen production pose severe challenges for typical TRISO particles. The thermo-mechanical fuel performance code HUPPCO (High burn-Up fuel Pebble Performance COde) currently under development accounts for spatial and time dependence of the material elastic properties, temperature, and irradiation swelling and creep mechanisms. In this work, some aspects of the thermo-mechanical response of TRISO particles used for incineration of weapons grade fuel in LIFE engine are analyzed. Preliminary results show the importance of developing reliable high-fidelity models of the performance of these new fuel designs and the need of new experimental data relevant to WGPu LIFE conditions.
Caro, M; DeMange, P; Marian, J; Caro, A
RENEWABLE ENERGY GROUPS COVET FUSION'S BUDGET A group called the Energy Efficiency Education-effective and environmentally sound energy- efficiency and renewable energy programs." Rep. Philip R. Sharp (D-IN) and chair the resolution, H. Con. Res. 188). Sharp said "For too long, cost-effectiveefficiencyand renewable energy
MAST-Upgrade Advancing compact fusion sources
of innovation. It will also put the UK in a leading position to develop engineering systems for the future to the drive towards commercial fusion power. 1. Testing reactor concepts. MAST-Upgrade will be the first machine to include the Super-X divertor design, an innovative plasma exhaust system that, if successful
Fusion yield: Guderley model and Tsallis statistics
The reaction rate probability integral is extended from Maxwell-Boltzmann approach to a more general approach by using the pathway model introduced by Mathai [Mathai A.M.:2005, A pathway to matrix-variate gamma and normal densities, Linear Algebra and Its Applications}, 396, 317-328]. The extended thermonuclear reaction rate is obtained in closed form via a Meijer's G-function and the so obtained G-function is represented as a solution of a homogeneous linear differential equation. A physical model for the hydrodynamical process in a fusion plasma compressed and laser-driven spherical shock wave is used for evaluating the fusion energy integral by integrating the extended thermonuclear reaction rate integral over the temperature. The result obtained is compared with the standard fusion yield obtained by Haubold and John in 1981.[Haubold, H.J. and John, R.W.:1981, Analytical representation of the thermonuclear reaction rate and fusion energy production in a spherical plasma shock wave, Plasma Physics, 23, 399-...
Haubold, H J
Nuclear diagnostics for inertial confinement fusion implosions
This abstract contains viewgraphs on nuclear diagnostic techniques for inertial confinement fusion implosions. The viewgraphs contain information on: reactions of interest in ICF; advantages and disadvantages of these methods; the properties nuclear techniques can measure; and some specifics on the detectors used.
Murphy, T.J.
Fusion Technology Working Group Presented by
Snowmass Fusion Technology Working Group Summary Presented by M. Abdou, S. Milora Snowmass July 23, 1999 #12;Technology Working Group Subgroup # 1 Subgroup # 2 Solid Walls Ulrickson / Mattas Liquid Walls / Ying Chamber Technology Abdou / Ulrickson Heating/CD/Fueling Swain / Temkin Magnets Schultz / Woolley
Safeguard Requirements for Fusion Power Plants
Nuclear proliferation risks from magnetic fusion energy associated with access to fissile materials can be divided into three main categories: 1) clandestine production of fissile material in an undeclared facility, 2) covert production and diversion of such material in a declared and safeguarded facility, and 3) use of a declared facility in a breakout scenario, in which a state openly produces fissile material in violation of international agreements. The degree of risk in each of these categories is assessed, taking into account both state and non-state actors, and it is found that safeguards are required for fusion energy to be highly attractive from a non-proliferation standpoint. Specific safeguard requirements and R&D needs are outlined for each category of risk, and the technical capability of the ITER experiment, under construction, to contribute to this R&D is noted. A preliminary analysis indicates a potential legal pathway for fusion power systems to be brought under the Treaty for the Non-Proliferation of Nuclear Weapons. "Vertical" proliferation risks associated with tritium and with the knowledge that can be gained from inertial fusion energy R&D are outlined.
Robert J. Goldston and Alexander Glaser
Energy Sources Used for Fusion Welding
) Energy Sources Used for Fusion Welding Thomas W. Eagar, Massachusetts Institute of Technology WELDING AND JOINING processes are es- sential for the development of virtually every manufactured product this situation. First, welding and joining are multifaceted, both in terms of process variations (such as fas
Eagar, Thomas W.
The spheromak as a compact fusion reactor
After summarizing the economic and utility-based rationale for compact, higher-power-density fusion reactors, the gun-sustained spheromak concept is explored as one of a number of poloidal-field-dominated confinement configurations that might improve the prospects for economically attractive and operationally simplified fusion power plants. Using a comprehensive physics/engineering/costing model for the spheromak, guided by realistic engineering constraints and physics extrapolation, a range of cost-optimized reactor design points is presented, and the sensitivity of cost to key physics, engineering, and operational variables is reported. The results presented herein provide the basis for conceptual engineering designs of key fusion-power-core (FPC) subsystems and more detailed plasma modeling of this promising, high mass-power-density concept, which stresses single-piece FPC maintenance, steady-state current drive through electrostatic magnetic helicity injection, a simplified co-axial electrode-divertor, and efficient resistive-coal equilibrium-field coils. The optimal FPC size and the cost estimates project a system that competes aggressively with the best offered by alternative energy sources while simplifying considerably the complexity that has generally been associated with most approaches to magnetic fusion energy.
Hagenson, R.L.; Krakowski, R.A.
for U.S. fusion research. This presentation proposes a mission for a major new U.S. facility, leading-even behind us, it is now time to address the logically first of the combined physics and technology% Japan 13% U.S. 10% China 10% India 10% Russia 10% S. Korea China Europe India Japan (w/EU) South Korea U
Edmund J. Synakowski Fusion Power Associates Meeting
by the University of California, Lawrence Livermore National Laboratory, under contract W-7405-Eng-48 #12;10/2/06 11 capabilities · IFE opportunities: NIF and present research elements The LLNL FEP research & resources enable Fusion Energy Program: leadership roles in both MFE and IFE, buoyed by ITER, NIF science, and LLNL
Summary of Topic1 Fusion Power Extraction
Extraction and Tritium Fuel Cycle � What choices are available for material, coolant, breeder, configuration availability of external tritium supply? #12;FW/Blanket concepts for fusion power extraction and tritium&D and facilities strongly overlap RAFM Steel PbLi Breeder Helium Cooled Ceramic Breeder Beryllium Helium Cooled Pb
Heavy Ion Fusion Science Virtual National Laboratory
to today's large NP accelerators like GSI-FAIR, RHIC economical for 1-2 GWe baseload power plants. Heavy chambers. · Competitive economics: projected in several power plant studies and with no high levelSlide 1 Heavy Ion Fusion Science Virtual National Laboratory Briefing for the National Academy
the fusion trend line Stan Milora (ORNL)
and create materials that can endure neutron, plasma and heat fluxes in a commercial power plant. Secretary and enabling technologies relevant to power plants and 2) the feasibility of a single new facility to address://vlt.ornl.gov/ VLT Virtual Laboratory for Technology For Fusion Energy Science #12;2 Managed by UT-Battelle for the U
Image Fusion for MR Bias Correction
. For example, for fast-spin echo (FSE) pulse sequences, the MR signal is given by this equation: · Target T1Image Fusion for MR Bias Correction Ayres Fan Stochastic Systems Group Joint work with W. Wells, J strength · Spatially varying field strength encodes spatial location in the frequency domain #12;MR Imaging
Willsky, Alan S.
· There are a number of steps along the path demonstrate ignition on the National Ignition Facility (NIF with polar drive on the NIF. Summary The development of commercial inertial fusion energy (IFE are Recommendation 2-1:The target physics programs on NIF, Nike, Omega, and Z should receive continued high priority
Cost Accounting System for fusion studies
A Cost Accounting System that is applicable to all magnetic fusion reactor design studies has been developed. This system provides: (1) definitions of the elements of cost and methods for the combination of these elements to form a cost estimate; (2) a Code of Accounts that uses a functional arrangement for identification of the plant components; and (3) definitions and methods to analyze actual cost data so that the data can be directly reported into this Cost Accounting System. The purpose of the Cost Accounting System is to provide the structure for the development of a fusion cost data base and for the development of validated cost estimating procedures. This system has been developed through use at the Fusion Engineering Design Center (FEDC) and has been applied to different confinement concepts (tokamaks and tandem mirrors) and to different types of projects (experimental devices and commercial power plants). The use of this Cost Accounting System by all magnetic fusion projects will promote the development of a common cost data base, allow the direct comparison of cost estimates, and ultimately establish the cost credibility of the program.
Hamilton, W.R.; Keeton, D.C.; Thomson, S.L.
LIFE Power Plant Fusion Power Associates
LIFE Power Plant Fusion Power Associates December 14, 2011 Mike Dunne LLNL #12;NIf-1111-23714.ppt LIFE power plant 2 #12;LIFE delivery timescale NIf-1111-23714.ppt 3 #12;Timely delivery is enabled dpa) � Removes ion threat and mitigates x-ray threat � allows simple steel piping � No need
FESAC Fusion Development Path Rob Goldston
Exploration/Proof of Principle IFE IREs MFE PE Exp'ts Engineering Science/ Technology Development ComponentFESAC Fusion Development Path Rob Goldston Graduate Student Seminar March 21, 2005 #12;Panel Power Associates · Robert Goldston (Chair), Princeton Plasma Physics Laboratory · Amanda Hubbard, MIT
Fusion, driver of innovation. Niek Lopes Cardozo
, Japan, China, Russia, S-Korea and India want fusion because ·! Zero CO2, Clean, Safe ·! Security ITER 10-fold power multiplication @ 500 MW Europe USA RF Japan China S-Korea India Europe, the USA? Comparable to ashes of coal plant ! Acceptable FFuueell ccyyccllee,, ttrriittiiuumm ggeenneerraattiioonn #12
Franssen, Michael
Automated Discovery: a Fusion of Multidisciplinary Principles
Automated Discovery: a Fusion of Multidisciplinary Principles Jan M. _Zytkow Computer Science; Piatetsky-Shapiro & Frawley, 1991; Shen, 1993; Shrager & Langley; Simon, Valdes-Perez & Sleeman, 1997; Kulkarni & Simon, 1987; Kocabas & Langley, 1995; Valdes- Perez, 1993. The mere accumulation of new
Ras, Zbigniew W.
Adiabatic Heavy Ion Fusion Potentials for Fusion at Deep Sub-barrier Energies
The fusion cross sections from well above barrier to extreme sub-barrier energies have been analysed using the energy (E) and angular momentum (L) dependent barrier penetration model ({\\small{ELDBPM}}). From this analysis, the adiabatic limits of fusion barriers have been determined for a wide range of heavy ion systems. The empirical prescription of Wilzynska and Wilzynski has been used with modified radius parameter and surface tension coefficient values consistent with the parameterization of the nuclear masses. The adiabatic fusion barriers calculated from this prescription are in good agreement with the adiabatic barriers deduced from {\\small{ELDBPM}} fits to fusion data. The nuclear potential diffuseness is larger at adiabatic limit, resulting in a lower $\\hbar\\omega$ leading to increase of "logarithmic slope" observed at energies well below the barrier. The effective fusion barrier radius and curvature values are anomalously smaller than the predictions of known empirical prescriptions. A detailed comparison of the systematics of fusion barrier with and without L-dependence has been presented.
S. V. S. Sastry; S. Kailas; A. K. Mohanty; A. Saxena
Achievable Qubit Rates for Quantum Information Wires
Suppose Alice and Bob have access to two separated regions, respectively, of a system of electrons moving in the presence of a regular one-dimensional lattice of binding atoms. We consider the problem of communicating as much quantum information, as measured by the qubit rate, through this quantum information wire as possible. We describe a protocol whereby Alice and Bob can achieve a qubit rate for these systems which is proportional to N^(-1/3) qubits per unit time, where N is the number of lattice sites. Our protocol also functions equally in the presence of interactions modelled via the t-J and Hubbard models.
Hulya Yadsan-Appleby; Tobias J. Osborne
Secretary's Achievement Award (SING) | Department of Energy
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Secretary's Achievement Award | Department of Energy
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