Sample records for international nuclear model

  1. Fragments' internal and kinetic temperatures in the framework of a Nuclear Statistical Multifragmentation Model

    E-Print Network [OSTI]

    S. R. Souza; B. V. Carlson; R. Donangelo; W. G. Lynch; M. B. Tsang

    2014-11-27T23:59:59.000Z

    The agreement between the fragments' internal and kinetic temperatures with the breakup temperature is investigated using a Statistical Multifragmentation Model which makes no a priori as- sumption on the relationship between them. We thus examine the conditions for obtaining such agreement and find that, in the framework of our model, this holds only in a relatively narrow range of excitation energy. The role played by the qualitative shape of the fragments' state densities is also examined. Our results suggest that the internal temperature of the light fragments may be affected by this quantity, whose behavior may lead to constant internal temperatures over a wide excitation energy range. It thus suggests that the nuclear thermometry may provide valuable information on the nuclear state density.

  2. International Nuclear Security

    SciTech Connect (OSTI)

    Doyle, James E. [Los Alamos National Laboratory

    2012-08-14T23:59:59.000Z

    This presentation discusses: (1) Definitions of international nuclear security; (2) What degree of security do we have now; (3) Limitations of a nuclear security strategy focused on national lock-downs of fissile materials and weapons; (4) What do current trends say about the future; and (5) How can nuclear security be strengthened? Nuclear security can be strengthened by: (1) More accurate baseline inventories; (2) Better physical protection, control and accounting; (3) Effective personnel reliability programs; (4) Minimize weapons-usable materials and consolidate to fewer locations; (5) Consider local threat environment when siting facilities; (6) Implement pledges made in the NSS process; and (7) More robust interdiction, emergency response and special operations capabilities. International cooperation is desirable, but not always possible.

  3. International Framework for Nuclear Energy Cooperation (IFNEC...

    Energy Savers [EERE]

    International Framework for Nuclear Energy Cooperation (IFNEC) Expert meetings in Romania International Framework for Nuclear Energy Cooperation (IFNEC) Expert meetings in Romania...

  4. Monitoring international nuclear activity

    SciTech Connect (OSTI)

    Firestone, R.B.

    2006-05-19T23:59:59.000Z

    The LBNL Table of Isotopes website provides primary nuclearinformation to>150,000 different users annually. We have developedthe covert technology to identify users by IP address and country todetermine the kinds of nuclear information they are retrieving. Wepropose to develop pattern recognition software to provide an earlywarning system to identify Unusual nuclear activity by country or regionSpecific nuclear/radioactive material interests We have monitored nuclearinformation for over two years and provide this information to the FBIand LLNL. Intelligence is gleaned from the website log files. Thisproposal would expand our reporting capabilities.

  5. International Nuclear Energy Research Initiative Development of Computational Models for Pyrochemical Electrorefiners of Nuclear Waste Transmutation Systems

    SciTech Connect (OSTI)

    M.F. Simpson; K.-R. Kim

    2010-12-01T23:59:59.000Z

    In support of closing the nuclear fuel cycle using non-aqueous separations technology, this project aims to develop computational models of electrorefiners based on fundamental chemical and physical processes. Spent driver fuel from Experimental Breeder Reactor-II (EBR-II) is currently being electrorefined in the Fuel Conditioning Facility (FCF) at Idaho National Laboratory (INL). And Korea Atomic Energy Research Institute (KAERI) is developing electrorefining technology for future application to spent fuel treatment and management in the Republic of Korea (ROK). Electrorefining is a critical component of pyroprocessing, a non-aqueous chemical process which separates spent fuel into four streams: (1) uranium metal, (2) U/TRU metal, (3) metallic high-level waste containing cladding hulls and noble metal fission products, and (4) ceramic high-level waste containing sodium and active metal fission products. Having rigorous yet flexible electrorefiner models will facilitate process optimization and assist in trouble-shooting as necessary. To attain such models, INL/UI has focused on approaches to develop a computationally-light and portable two-dimensional (2D) model, while KAERI/SNU has investigated approaches to develop a computationally intensive three-dimensional (3D) model for detailed and fine-tuned simulation.

  6. International scientists on nuclear winter

    SciTech Connect (OSTI)

    Malone, T.F.

    1985-12-01T23:59:59.000Z

    A report by the International Council of Scientific Unions (ICSU) leads new support to the warning of extreme climatic disruptions that would follow a nuclear war. The two-volume report does not deal explicitly with public policy questions, but focuses on scientific knowledge of physical effects and biological responses. The author reviews studies made since the warning of a nuclear winter began in 1982, and evaluates the new report. He finds the message of the report to be a clear warning that a major nuclear war would threaten the entire world. He hopes it will be a catalyst to world opinion in the same way that the public responded to the incident of radioactive fallout striking a Japanese fishing vessel in 1954.

  7. Internal dose following a major nuclear war

    SciTech Connect (OSTI)

    Peterson, K.R.; Shapiro, C.S. (Lawrence Livermore National Laboratory, Livermore, CA (Unites States))

    1992-01-01T23:59:59.000Z

    The PATHWAY model results were used, in conjunction with a hypothetical major nuclear attack on the U.S., to arrive at the ratio of internal to external dose for humans from early (48 h) fallout. Considered were the four nuclides (137Cs, 89Sr, 90Sr, 131I) that account for most of the reconstructed whole-body committed equivalent dose from internal radiation in people who lived downwind of the Nevada Test Site during atmospheric tests. Effects of climate perturbations (the 'nuclear winter' effect) on food crops were considered. These could increase internal dose estimates, depending on the severity of the climate perturbations. Internal and external doses to humans for 10 locations within the U.S. have been calculated, with varying local conditions and varying assumption about their shelters. The estimated 50-y internal dose commitment ranged from 0.0-0.17 Sv, the 48-h external dose from 0.15-4.6 Sv. The resultant ratios of internal to external committed dose received in the first months (until food transport was restored) varied from less than 0.01 to about 0.2. In all cases examined, the total dose from early fallout was found to be dominated by the external dose.

  8. Nuclear reactor internals alignment configuration

    DOE Patents [OSTI]

    Gilmore, Charles B. (Greensburg, PA); Singleton, Norman R. (Murrysville, PA)

    2009-11-10T23:59:59.000Z

    An alignment system that employs jacking block assemblies and alignment posts around the periphery of the top plate of a nuclear reactor lower internals core shroud to align an upper core plate with the lower internals and the core shroud with the core barrel. The distal ends of the alignment posts are chamfered and are closely received within notches machined in the upper core plate at spaced locations around the outer circumference of the upper core plate. The jacking block assemblies are used to center the core shroud in the core barrel and the alignment posts assure the proper orientation of the upper core plate. The alignment posts may alternately be formed in the upper core plate and the notches may be formed in top plate.

  9. PIA - 10th International Nuclear Graphite Specialists Meeting...

    Broader source: Energy.gov (indexed) [DOE]

    10th International Nuclear Graphite Specialists Meeting registration web site PIA - 10th International Nuclear Graphite Specialists Meeting registration web site More Documents &...

  10. International Framework for Nuclear Energy Cooperation to Hold...

    Energy Savers [EERE]

    International Framework for Nuclear Energy Cooperation to Hold Ministerial-Level Meeting Sept. 29 in Warsaw, Poland International Framework for Nuclear Energy Cooperation to Hold...

  11. International Nuclear Safeguards | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes | National NuclearInterlibrary LoanSafeguards | National Nuclear

  12. International Nuclear Security | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes | National NuclearInterlibrary LoanSafeguards | National

  13. International perceptions of US nuclear policy.

    SciTech Connect (OSTI)

    Stanley, Elizabeth A. (Georgetown Universtiy, Washington, DC)

    2006-02-01T23:59:59.000Z

    The report presents a summary of international perceptions and beliefs about US nuclear policy, focusing on four countries--China, Iran, Pakistan and Germany--chosen because they span the spectrum of states with which the United States has relationships. A paradox is pointed out: that although the goal of US nuclear policy is to make the United States and its allies safer through a policy of deterrence, international perceptions of US nuclear policy may actually be making the US less safe by eroding its soft power and global leadership position. Broadly held perceptions include a pattern of US hypocrisy and double standards--one set for the US and its allies, and another set for all others. Importantly, the US nuclear posture is not seen in a vacuum, but as one piece of the United States behavior on the world stage. Because of this, the potential direct side effects of any negative international perceptions of US nuclear policy can be somewhat mitigated, dependent on other US policies and actions. The more indirect and long term relation of US nuclear policy to US international reputation and soft power, however, matters immensely to successful multilateral and proactive engagement on other pressing global issues.

  14. International nuclear waste management fact book

    SciTech Connect (OSTI)

    Abrahms, C W; Patridge, M D; Widrig, J E

    1995-11-01T23:59:59.000Z

    The International Nuclear Waste Management Fact Book has been compiled to provide current data on fuel cycle and waste management facilities, R and D programs, and key personnel in 24 countries, including the US; four multinational agencies; and 20 nuclear societies. This document, which is in its second year of publication supersedes the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 12 years. The content has been updated to reflect current information. The Fact Book is organized as follows: National summaries--a section for each country that summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies--a section for each of the international agencies that has significant fuel cycle involvement and a list of nuclear societies. Glossary--a list of abbreviations/acronyms of organizations, facilities, and technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country and some general information that is presented from the perspective of the Fact Book user in the US.

  15. International Nuclear Fuel Cycle Fact Book

    SciTech Connect (OSTI)

    Leigh, I.W.; Patridge, M.D.

    1991-05-01T23:59:59.000Z

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECN/NEA activities reports; not reflect any one single source but frequently represent a consolidation/combination of information.

  16. United States-Republic of Korea (ROK) International Nuclear Energy...

    Office of Environmental Management (EM)

    United States-Republic of Korea (ROK) International Nuclear Energy Research Initiative (INERI) Annual Steering Committee Meeting United States-Republic of Korea (ROK) International...

  17. International safeguards: Accounting for nuclear materials

    SciTech Connect (OSTI)

    Fishbone, L.G.

    1988-09-28T23:59:59.000Z

    Nuclear safeguards applied by the International Atomic Energy Agency (IAEA) are one element of the non-proliferation regime'', the collection of measures whose aim is to forestall the spread of nuclear weapons to countries that do not already possess them. Safeguards verifications provide evidence that nuclear materials in peaceful use for nuclear-power production are properly accounted for. Though carried out in cooperation with nuclear facility operators, the verifications can provide assurance because they are designed with the capability to detect diversion, should it occur. Traditional safeguards verification measures conducted by inspectors of the IAEA include book auditing; counting and identifying containers of nuclear material; measuring nuclear material; photographic and video surveillance; and sealing. Novel approaches to achieve greater efficiency and effectiveness in safeguards verifications are under investigation as the number and complexity of nuclear facilities grow. These include the zone approach, which entails carrying out verifications for groups of facilities collectively, and randomization approach, which entails carrying out entire inspection visits some fraction of the time on a random basis. Both approaches show promise in particular situations, but, like traditional measures, must be tested to ensure their practical utility. These approaches are covered on this report. 15 refs., 16 figs., 3 tabs.

  18. Working Party on International Nuclear Data Evaluation Cooperation (WPEC)

    SciTech Connect (OSTI)

    Giuseppe Palmiotti

    2014-06-01T23:59:59.000Z

    The OECD Nuclear Energy Agency (NEA) is organizing the cooperation between the major nuclear data evaluation projects in the world. The NEA Working Party on International Nuclear Data Evaluation Cooperation (WPEC) was established to promote the exchange of information on nuclear data evaluation, measurement, nuclear model calculation, validation, and related topics, and to provide a framework for cooperative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint activities in the framework of dedicated WPEC subgroups. Studies recently completed comprise a number of works related to nuclear data covariance and associated processing issues, as well as more specific studies related to the resonance parameter representation in the unresolved resonance region, the gamma production from fission-product capture reactions, the U-235 capture cross-section, the EXFOR database, and the improvement of nuclear data for advanced reactor systems. Ongoing activities focus on the evaluation of Pu-239 in the resonance region, scattering angular distribution in the fast energy range, and reporting/usage of experimental data for evaluation in the resolved resonance region. New activities include two new subgroups on improved fission product yield evaluation methodologies and on modern nuclear database structures. Future activities under discussion include a pilot project of a Collaborative International Evaluated Library (CIELO) and methods to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data. In addition to the above mentioned short-term, task-oriented subgroups, the WPEC also hosts a longer-term subgroup charged with reviewing and compiling the most important nuclear data requirements in a high priority request list (HPRL).

  19. International Nuclear Fuel Cycle Fact Book

    SciTech Connect (OSTI)

    Leigh, I W; Mitchell, S J

    1990-01-01T23:59:59.000Z

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops, etc. The data listed do not reflect any one single source but frequently represent a consolidation/combination of information.

  20. International Nuclear Fuel Cycle Fact Book

    SciTech Connect (OSTI)

    Leigh, I.W.

    1992-05-01T23:59:59.000Z

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

  1. JET Papers Presented at International Atomic Energy Agency 10th International Conference on Plasma Physics and Controlled Nuclear Research

    E-Print Network [OSTI]

    JET Papers Presented at International Atomic Energy Agency 10th International Conference on Plasma Physics and Controlled Nuclear Research

  2. The Nuclear Revolution, Relative Gains, and International Nuclear Assistance

    E-Print Network [OSTI]

    Kroenig, Matthew

    2006-01-01T23:59:59.000Z

    it would transfer nuclear technology. Washington Post. 26preferences: the export of sensitive nuclear technology.export of sensitive nuclear technology presents a kind of

  3. The Nuclear Revolution, Relative Gains, and International Nuclear Assistance

    E-Print Network [OSTI]

    Kroenig, Matthew

    2006-01-01T23:59:59.000Z

    204. Bhatia, Shyam. 1988. Nuclear rivals in the Middle East.of the merits of selective nuclear proliferation. Journal ofThe Case for a Ukranian nuclear deterrent. Foreign Affairs.

  4. International Engagement | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

  5. International Exercises | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

  6. Modeling the Nuclear Fuel Cycle

    SciTech Connect (OSTI)

    Jacob J. Jacobson; A. M. Yacout; G. E. Matthern; S. J. Piet; A. Moisseytsev

    2005-07-01T23:59:59.000Z

    The Advanced Fuel Cycle Initiative is developing a system dynamics model as part of their broad systems analysis of future nuclear energy in the United States. The model will be used to analyze and compare various proposed technology deployment scenarios. The model will also give a better understanding of the linkages between the various components of the nuclear fuel cycle that includes uranium resources, reactor number and mix, nuclear fuel type and waste management. Each of these components is tightly connected to the nuclear fuel cycle but usually analyzed in isolation of the other parts. This model will attempt to bridge these components into a single model for analysis. This work is part of a multi-national laboratory effort between Argonne National Laboratory, Idaho National Laboratory and United States Department of Energy. This paper summarizes the basics of the system dynamics model and looks at some results from the model.

  7. International nuclear fuel cycle fact book. Revision 6

    SciTech Connect (OSTI)

    Harmon, K.M.; Lakey, L.T.; Leigh, I.W.; Jeffs, A.G.

    1986-01-01T23:59:59.000Z

    The International Fuel Cycle Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2.

  8. Assuaging Nuclear Energy Risks: The Angarsk International Uranium Enrichment Center

    SciTech Connect (OSTI)

    Myers, Astasia [Stanford University, Stanford, CA 94305, USA and MonAme Scientific Research Center, Ulaanbaatar (Mongolia)

    2011-06-28T23:59:59.000Z

    The recent nuclear renaissance has motivated many countries, especially developing nations, to plan and build nuclear power reactors. However, domestic low enriched uranium demands may trigger nations to construct indigenous enrichment facilities, which could be redirected to fabricate high enriched uranium for nuclear weapons. The potential advantages of establishing multinational uranium enrichment sites are numerous including increased low enrichment uranium access with decreased nuclear proliferation risks. While multinational nuclear initiatives have been discussed, Russia is the first nation to actualize this concept with their Angarsk International Uranium Enrichment Center (IUEC). This paper provides an overview of the historical and modern context of the multinational nuclear fuel cycle as well as the evolution of Russia's IUEC, which exemplifies how international fuel cycle cooperation is an alternative to domestic facilities.

  9. EU signs ITER deal Negotiations on the ITER international nuclear

    E-Print Network [OSTI]

    Korea and the US, the agreement aims to develop a project that will test the feasibility of nuclearEU signs ITER deal Negotiations on the ITER international nuclear fusion project have been on Wednesday reached a final agreement on the ITER project after years of talks. "The completion

  10. Model Action Plan for Nuclear Forensics and Nuclear Attribution

    SciTech Connect (OSTI)

    Dudder, G B; Niemeyer, S; Smith, D K; Kristo, M J

    2004-03-01T23:59:59.000Z

    Nuclear forensics and nuclear attribution have become increasingly important tools in the fight against illegal trafficking in nuclear and radiological materials. This technical report documents the field of nuclear forensics and nuclear attribution in a comprehensive manner, summarizing tools and procedures that have heretofore been described independently in the scientific literature. This report also provides national policy-makers, decision-makers, and technical managers with guidance for responding to incidents involving the interdiction of nuclear and radiological materials. However, due to the significant capital costs of the equipment and the specialized expertise of the personnel, work in the field of nuclear forensics has been restricted so far to a handful of national and international laboratories. In fact, there are a limited number of specialists who have experience working with interdicted nuclear materials and affiliated evidence. Most of the laboratories that have the requisite equipment, personnel, and experience to perform nuclear forensic analysis are participants in the Nuclear Smuggling International Technical Working Group or ITWG (see Section 1.8). Consequently, there is a need to disseminate information on an appropriate response to incidents of nuclear smuggling, including a comprehensive approach to gathering evidence that meets appropriate legal standards and to developing insights into the source and routes of nuclear and radiological contraband. Appendix A presents a ''Menu of Options'' for other Member States to request assistance from the ITWG Nuclear Forensics Laboratories (INFL) on nuclear forensic cases.

  11. Computer aided nuclear reactor modeling 

    E-Print Network [OSTI]

    Warraich, Khalid Sarwar

    1995-01-01T23:59:59.000Z

    CENTAR model), and by interacting with the user and providing feedback by checking for errors and advising corrections. The architecture of Alpha is presented with its constituent libraries explained in their internal working and external interactions...

  12. International Nuclear Fuel Cycle Fact Book. Revision 5

    SciTech Connect (OSTI)

    Harmon, K.M.; Lakey, L.T.; Leigh, I.W.; Jeffs, A.G.

    1985-01-01T23:59:59.000Z

    This Fact Book has been compiled in an effort to provide: (1) an overview of worldwide nuclear power and fuel cycle programs; and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

  13. International nuclear fuel cycle fact book. Revision 4

    SciTech Connect (OSTI)

    Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

    1984-03-01T23:59:59.000Z

    This Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids - international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

  14. ICENES '91:Sixth international conference on emerging nuclear energy systems

    SciTech Connect (OSTI)

    Not Available

    1991-01-01T23:59:59.000Z

    This document contains the program and abstracts of the sessions at the Sixth International Conference on Emerging Nuclear Energy Systems held June 16--21, 1991 at Monterey, California. These sessions included: The plenary session, fission session, fission and nonelectric session, poster session 1P; (space propulsion, space nuclear power, electrostatic confined fusion, fusion miscellaneous, inertial confinement fusion, [mu]-catalyzed fusion, and cold fusion); Advanced fusion session, space nuclear session, poster session 2P, (nuclear reactions/data, isotope separation, direct energy conversion and exotic concepts, fusion-fission hybrids, nuclear desalting, accelerator waste-transmutation, and fusion-based chemical recycling); energy policy session, poster session 3P (energy policy, magnetic fusion reactors, fission reactors, magnetically insulated inertial fusion, and nuclear explosives for power generation); exotic energy storage and conversion session; and exotic energy storage and conversion; review and closing session.

  15. International training course on nuclear materials accountability for safeguards purposes

    SciTech Connect (OSTI)

    Not Available

    1980-12-01T23:59:59.000Z

    The two volumes of this report incorporate all lectures and presentations at the International Training Course on Nuclear Materials Accountability and Control for Safeguards Purposes, held May 27-June 6, 1980, at the Bishop's Lodge near Santa Fe, New Mexico. The course, authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, was developed to provide practical training in the design, implementation, and operation of a National system of nuclear materials accountability and control that satisfies both National and IAEA International safeguards objectives. Volume I, covering the first week of the course, presents the background, requirements, and general features of material accounting and control in modern safeguard systems. Volume II, covering the second week of the course, provides more detailed information on measurement methods and instruments, practical experience at power reactor and research reactor facilities, and examples of operating state systems of accountability and control.

  16. International nuclear fuel cycle fact book: Revision 9

    SciTech Connect (OSTI)

    Leigh, I.W.

    1989-01-01T23:59:59.000Z

    The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. The Fact Book contains: national summaries in which a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; and international agencies in which a section for each of the international agencies which has significant fuel cycle involvement, and a listing of nuclear societies. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter is presented from the perspective of the Fact Book user in the United States.

  17. International nuclear fuel cycle fact book

    SciTech Connect (OSTI)

    Leigh, I.W.

    1988-01-01T23:59:59.000Z

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source or information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

  18. Nuclear Systems Modeling & Simulation | More Science | ORNL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Systems Modeling and Simulation SHARE Nuclear Systems Modeling and Simulation Reactor physics depletion model for the Advanced Test Reactor Reactor physics depletion model for the...

  19. Status and Value of International Standards for Nuclear Criticality Safety

    SciTech Connect (OSTI)

    Hopper, Calvin Mitchell [ORNL] [ORNL

    2011-01-01T23:59:59.000Z

    This presentation provides an update to the author's standards report provided at the ICNC-2007 meeting. It includes a discussion about the difference between, and the value of participating in, the development of international 'consensus' standards as opposed to nonconsensus standards. Standards are developed for a myriad of reasons. Generally, standards represent an agreed upon, repeatable way of doing something as defined by an individual or group of people. They come in various types. Examples include personal, family, business, industrial, commercial, and regulatory such as military, community, state, federal, and international standards. Typically, national and international 'consensus' standards are developed by individuals and organizations of diverse backgrounds representing the subject matter users and developers of a service or product and other interested parties or organizations. Within the International Organization for Standardization (ISO), Technical Committee 85 (TC85) on nuclear energy, Subcommittee 5 (SC5) on nuclear fuel technology, there is a Working Group 8 (WG8) on standardization of calculations, procedures, and practices related to criticality safety. WG8 has developed, and is developing, ISO standards within the category of nuclear criticality safety of fissionable materials outside of reactors (i.e., nonreactor fissionable material nuclear fuel cycle facilities). Since the presentation of the ICNC-2007 report, WG8 has issued three new finalized international standards and is developing two more new standards. Nearly all elements of the published WG8 ISO standards have been incorporated into IAEA nonconsensus guides and standards. The progression of consensus standards development among international partners in a collegial environment establishes a synergy of different concepts that broadens the perspectives of the members. This breadth of perspectives benefits the working group members in their considerations of consensus standards developments in their own countries. A testament to the value of the international standards efforts is that nearly all elements of the published WG8 ISO standards have been incorporated into IAEA nonconsensus guides and standards and are mainly consistent with international ISO member domestic standards.

  20. international exercises | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron4 Self-Scrubbing:,, , .,Shreve;SolidThermalexercises | National Nuclear

  1. International Engagement | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes | National NuclearInterlibrary Loan InterlibraryTrilateralEngagement

  2. International Exercises | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes | National NuclearInterlibrary Loan

  3. International Programs | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes | National NuclearInterlibrary LoanSafeguards | NationalPrograms |

  4. Primer on nuclear exchange models

    SciTech Connect (OSTI)

    Hafemeister, David [Physics Department, Cal Poly University, San Luis Obispo, California (United States)

    2014-05-09T23:59:59.000Z

    Basic physics is applied to nuclear force exchange models between two nations. Ultimately, this scenario approach can be used to try and answer the age old question of 'how much is enough?' This work is based on Chapter 2 of Physics of Societal Issues: Calculations on National Security, Environment and Energy (Springer, 2007 and 2014)

  5. Nuclear Systems Modeling, Simulation & Validation | ORNL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Systems Modeling and Simulation SHARE Nuclear Systems Modeling, Simulation and Validation Reactor physics depletion model for the Advanced Test Reactor Reactor physics depletion...

  6. International Nuclear Energy Research Initiative 2010 Annual...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    an accurately measured response function and Monte Carlo (MC) modeling, which will be applied to verify the (n,p) angular distribution. After developing a prototype detector, the...

  7. Spent nuclear fuel reprocessing modeling

    SciTech Connect (OSTI)

    Tretyakova, S.; Shmidt, O.; Podymova, T.; Shadrin, A.; Tkachenko, V. [Bochvar Institute, 5 Rogova str., Moscow 123098 (Russian Federation); Makeyeva, I.; Tkachenko, V.; Verbitskaya, O.; Schultz, O.; Peshkichev, I. [Russian Federal Nuclear Center - VNIITF E.I. Zababakhin, p.o.box 245, Snezhinsk, 456770 (Russian Federation)

    2013-07-01T23:59:59.000Z

    The long-term wide development of nuclear power requires new approaches towards the realization of nuclear fuel cycle, namely, closed nuclear fuel cycle (CNFC) with respect to fission materials. Plant nuclear fuel cycle (PNFC), which is in fact the reprocessing of spent nuclear fuel unloaded from the reactor and the production of new nuclear fuel (NF) at the same place together with reactor plant, can be one variant of CNFC. Developing and projecting of PNFC is a complicated high-technology innovative process that requires modern information support. One of the components of this information support is developed by the authors. This component is the programme conducting calculations for various variants of process flow sheets for reprocessing SNF and production of NF. Central in this programme is the blocks library, where the blocks contain mathematical description of separate processes and operations. The calculating programme itself has such a structure that one can configure the complex of blocks and correlations between blocks, appropriate for any given flow sheet. For the ready sequence of operations balance calculations are made of all flows, i.e. expenses, element and substance makeup, heat emission and radiation rate are determined. The programme is open and the block library can be updated. This means that more complicated and detailed models of technological processes will be added to the library basing on the results of testing processes using real equipment, in test operating mode. The development of the model for the realization of technical-economic analysis of various variants of technologic PNFC schemes and the organization of 'operator's advisor' is expected. (authors)

  8. Preparation of nuclear fuel spheres by flotation-internal gelation

    DOE Patents [OSTI]

    Haas, P.A.; Fowler, V.L.; Lloyd, M.H.

    1984-12-21T23:59:59.000Z

    A simplified internal gelation process is claimed for the preparation of gel spheres of nuclear fuels. The process utilizes perchloroethylene as a gelation medium. Gelation is accomplished by directing droplets of a nuclear fuel broth into a moving volume of hot perchloroethylene (about 85/sup 0/C) in a trough. Gelation takes place as the droplets float on the surface of the perchloroethylene and the resultant gel spheres are carried directly into an ager column which is attached to the trough. The aged spheres are disengaged from the perchloroethylene on a moving screen and are deposited in an aqueous wash column. 3 figs.

  9. International Nuclear Fuel Cycle Fact Book. Revision 12

    SciTech Connect (OSTI)

    Leigh, I.W.

    1992-05-01T23:59:59.000Z

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

  10. Micro-Continuum Modeling of Nuclear Waste Glass Corrosion

    E-Print Network [OSTI]

    Steefel, Carl

    2014-01-01T23:59:59.000Z

    21. Grambow, B. (2006). Nuclear waste glasses – How durable?Continuum Modeling of Nuclear Waste Glass Corrosion AugustContinuum Modeling of Nuclear Waste Glass Corrosion Prepared

  11. International Internships in Nuclear Safeguards and Security: Challenges and Successes

    SciTech Connect (OSTI)

    Duncan, Cristen L.; Heinberg, Cynthia L.; Killinger, Mark H.; Goodey, Kent O.; Kryuchkov, Eduard F.; Geraskin, Nikolai I.; Silaev, Maxim E.; Sokova, Elena K.; Ford, David G.

    2010-04-20T23:59:59.000Z

    All students in the Russian safeguards and security degree programs at the National Research Nuclear University MEPhI and Tomsk Polytechnic University, sponsored by the Material Protection, Control and Accounting (MPC&A) Education Project, take part in a domestic internship at a Russian enterprise or facility. In addition, a select few students are placed in an international internship. These internships provide students with a better view of how MPC&A and nonproliferation in general are addressed outside of Russia. The possibility of an international internship is a significant incentive for students to enroll in the safeguards and security degree programs. The U.S. members of the MPC&A Education Project team interview students who have been nominated by their professors. These students must have initiative and reasonable English skills. The project team and professors then select students to be tentatively placed in various international internships during the summer or fall of their final year of study. Final arrangements are then made with the host organizations. This paper describes the benefits of the joint United States/Russia cooperation for next-generation workforce development, some of the international internships that have been carried out, the benefits of these international internships, and lessons learned in implementing them.

  12. Internationally Standardized Cost Item Definitions for Decommissioning of Nuclear Installations

    SciTech Connect (OSTI)

    Lucien Teunckens; Kurt Pflugrad; Candace Chan-Sands; Ted Lazo

    2000-06-04T23:59:59.000Z

    The European Commission (EC), the International Atomic Energy Agency (IAEA), and the Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) have agreed to jointly prepare and publish a standardized list of cost items and related definitions for decommissioning projects. Such a standardized list would facilitate communication, promote uniformity, and avoid inconsistency or contradiction of results or conclusions of cost evaluations for decommissioning projects carried out for specific purposes by different groups. Additionally, a standardized structure would also be a useful tool for more effective cost management. This paper describes actual work and result thus far.

  13. International Nuclear Energy Policy and Cooperation | Department of Energy

    Office of Environmental Management (EM)

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122Commercial602 1,39732on ArmedManufacturing |Time-Based International Nuclear Energy

  14. XLV International Winter Meeting on Nuclear Physics BORMIO, Italy, January 14-21, 2007

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    XLV International Winter Meeting on Nuclear Physics BORMIO, Italy, January 14-21, 2007 The ALICE transition of nuclear matter from a hadron gas to a new state of matter, the Quark Gluon Plasma (QGP

  15. Ira Helfand, MD International Physicians for the Prevention of Nuclear War

    E-Print Network [OSTI]

    Robock, Alan

    Ira Helfand, MD International Physicians for the Prevention of Nuclear War Physicians for Social Responsibility NUCLEAR FAMINE: A BILLION PEOPLE AT RISK Global Impacts of Limited Nuclear War on Agriculture of studies have shown that a limited, regional nuclear war between India and Pakistan would cause significant

  16. Safety Series No. 75-INSAG-4, Safety Culture: A report by the International Nuclear Safety Advisory Group, International Atomic Energy Agency

    Broader source: Energy.gov [DOE]

    Safety Series No. 75-INSAG-4, Safety Culture: A report by the International Nuclear Safety Advisory Group, International Atomic Energy Agency, IAEA, 1991

  17. Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels -- Final Report under the International Nuclear Energy Research Initiative (I-NERI)

    SciTech Connect (OSTI)

    David Petti; Philippe Martin; Mayeul Phélip; Ronald Ballinger; Petti does not have NT account

    2004-12-01T23:59:59.000Z

    The objective of this INERI project was to develop improved fuel behavior models for gas reactor coated-particle fuels and to explore improved coated-particle fuel designs that could be used reliably at very high burnups and potentially in gas-cooled fast reactors. Project participants included the Idaho National Engineering Laboratory (INEEL), Centre Étude Atomique (CEA), and the Massachusetts Institute of Technology (MIT). To accomplish the project objectives, work was organized into five tasks.

  18. PROCEEDINGS OF THE INTERNATIONAL CONFERENCE ON NUCLEAR PHYSICS

    E-Print Network [OSTI]

    Saxon, D.S.

    2010-01-01T23:59:59.000Z

    Phys. A278 (1977) 387. NUCLEAR FISSION INDUCED BY ATOMICand J.R. Huizenga, in Nuclear Fission (Academic Press, Newvery soft nuclei, nuclear fission and heavy ion reactions.

  19. Center for Advanced Modeling and Simulation Intern

    SciTech Connect (OSTI)

    Gertman, Vanessa

    2010-01-01T23:59:59.000Z

    Some interns just copy papers and seal envelopes. Not at INL! Check out how Vanessa Gertman, an INL intern working at the Center for Advanced Modeling and Simulation, spent her summer working with some intense visualization software. Lots more content like this is available at INL's facebook page http://www.facebook.com/idahonationallaboratory.

  20. Center for Advanced Modeling and Simulation Intern

    ScienceCinema (OSTI)

    Gertman, Vanessa

    2013-05-28T23:59:59.000Z

    Some interns just copy papers and seal envelopes. Not at INL! Check out how Vanessa Gertman, an INL intern working at the Center for Advanced Modeling and Simulation, spent her summer working with some intense visualization software. Lots more content like this is available at INL's facebook page http://www.facebook.com/idahonationallaboratory.

  1. Application of nuclear models to neutron nuclear cross section calculations

    SciTech Connect (OSTI)

    Young, P.G.

    1982-01-01T23:59:59.000Z

    Nuclear theory is used increasingly to supplement and extend the nuclear data base that is available for applied studies. Areas where theoretical calculations are most important include the determination of neutron cross sections for unstable fission products and transactinide nuclei in fission reactor or nuclear waste calculations and for meeting the extensive dosimetry, activation, and neutronic data needs associated with fusion reactor development, especially for neutron energies above 14 MeV. Considerable progress has been made in the use of nuclear models for data evaluation and, particularly, in the methods used to derive physically meaningful parameters for model calculations. Theoretical studies frequently involve use of spherical and deformed optical models, Hauser-Feshbach statistical theory, preequilibrium theory, direct-reaction theory, and often make use of gamma-ray strength function models and phenomenological (or microscopic) level density prescriptions. The development, application, and limitations of nuclear models for data evaluation are discussed, with emphasis on the 0.1 to 50 MeV energy range. (91 references).

  2. Critical analysis of quark-meson coupling models for nuclear matter and finite nuclei

    E-Print Network [OSTI]

    Horst Mueller; Byron K. Jennings

    1998-07-09T23:59:59.000Z

    Three versions of the quark-meson coupling (QMC) model are applied to describe properties of nuclear matter and finite nuclei. The models differ in the treatment of the bag constant and in terms of nonlinear scalar self-interactions. As a consequence opposite predictions for the medium modifications of the internal nucleon structure arise. After calibrating the model parameters at equilibrium nuclear matter density, binding energies, charge radii, single-particle spectra and density distributions of spherical nuclei are analyzed and compared with QHD calculations. For the models which predict a decreasing size of the nucleon in the nuclear environment, unrealistic features of the nuclear shapes arise.

  3. Redundancy of Supply in the International Nuclear Fuel Fabrication Market: Are Fabrication Services Assured?

    SciTech Connect (OSTI)

    Seward, Amy M.; Toomey, Christopher; Ford, Benjamin E.; Wood, Thomas W.; Perkins, Casey J.

    2011-11-14T23:59:59.000Z

    For several years, Pacific Northwest National Laboratory (PNNL) has been assessing the reliability of nuclear fuel supply in support of the U.S. Department of Energy/National Nuclear Security Administration. Three international low enriched uranium reserves, which are intended back up the existing and well-functioning nuclear fuel market, are currently moving toward implementation. These backup reserves are intended to provide countries credible assurance that of the uninterrupted supply of nuclear fuel to operate their nuclear power reactors in the event that their primary fuel supply is disrupted, whether for political or other reasons. The efficacy of these backup reserves, however, may be constrained without redundant fabrication services. This report presents the findings of a recent PNNL study that simulated outages of varying durations at specific nuclear fuel fabrication plants. The modeling specifically enabled prediction and visualization of the reactors affected and the degree of fuel delivery delay. The results thus provide insight on the extent of vulnerability to nuclear fuel supply disruption at the level of individual fabrication plants, reactors, and countries. The simulation studies demonstrate that, when a reasonable set of qualification criteria are applied, existing fabrication plants are technically qualified to provide backup fabrication services to the majority of the world's power reactors. The report concludes with an assessment of the redundancy of fuel supply in the nuclear fuel market, and a description of potential extra-market mechanisms to enhance the security of fuel supply in cases where it may be warranted. This report is an assessment of the ability of the existing market to respond to supply disruptions that occur for technical reasons. A forthcoming report will address political disruption scenarios.

  4. Infrastructure development assistance modeling for nuclear power plant

    SciTech Connect (OSTI)

    Park, J. H.; Hwang, K.; Park, K. M.; Kim, S. W.; Lee, S. M. [Korea Hydro and Nuclear Power Co., LTD, 23, 106 gil, Yeongdong-daero, Gangnam-gu, 153-791 (Korea, Republic of)

    2012-07-01T23:59:59.000Z

    The purpose of this paper is to develop a model, a general frame to be utilized in assisting newcomer countries to start a nuclear power program. A nuclear power plant project involves technical complexity and high level of investment with long duration. Considering newcomers are mostly developing countries that lack the national infrastructure, key infrastructure issues may constitute the principal constraints to the development of a nuclear power program. In this regard, it is important to provide guidance and support to set up an appropriate infrastructure when we help them with the first launch of nuclear power plant project. To date, as a sole nuclear power generation company, KHNP has been invited many times to mentor or assist newcomer countries for their successful start of a nuclear power program since Republic of Korea is an exemplary case of a developing country which began nuclear power program from scratch and became a major world nuclear energy country in a short period of time. Through hosting events organized to aid newcomer countries' initiation of nuclear power projects, difficulties have been recognized. Each event had different contents according to circumstances because they were held as an unstructured and one-off thing. By developing a general model, we can give more adequate and effective aid in an efficient way. In this paper, we created a model to identify necessary infrastructures at the right stage, which was mainly based on a case of Korea. Taking into account the assistance we received from foreign companies and our own efforts for technological self-reliance, we have developed a general time table and specified activities required to do at each stage. From a donor's perspective, we explored various ways to help nuclear infrastructure development including technical support programs, training courses, and participating in IAEA technical cooperation programs on a regular basis. If we further develop the model, the next task would be to make the model more sophisticated as a 'semi-tailored model' so that it can be applied to a certain country reflecting its unique conditions. In accordance with its degree of established infrastructure, we can adjust or modify the model. Despite lots of benefits of using this model, there remain limitations such as time and budget constraints. These problems, however, can be addressed by cooperating with international organization such as the IAEA and other companies that share the same goal of helping newcomer countries introduce nuclear power. (authors)

  5. Nuclear talks in Austria International representatives will meet in Vienna on Saturday to discuss a

    E-Print Network [OSTI]

    Nuclear talks in Austria International representatives will meet in Vienna on Saturday to discuss a controversial nuclear fusion plan. The technical meeting of experts is intended to pave the way of nuclear fusion say it provides an attractive long-term energy option, because the basic materials needed

  6. Safety Reports Series No. 11, Developing Safety Culture in Nuclear Activities: Practical Suggestions to Assist Progress, International Atomic Energy Agency

    Broader source: Energy.gov [DOE]

    Safety Reports Series No. 11, Developing Safety Culture in Nuclear Activities: Practical Suggestions to Assist Progress, International Atomic Energy Agency

  7. Heat transfer modeling of dry spent nuclear fuel storage facilities

    SciTech Connect (OSTI)

    Lee, S.Y.

    1999-07-01T23:59:59.000Z

    The present work was undertaken to provide heat transfer model that accurately predicts the thermal performance of dry spent nuclear fuel storage facilities. One of the storage configurations being considered for DOE Aluminum-clad Spent Nuclear Fuel (Al-SNF), such as the Material and Testing Reactor (MTR) fuel, is in a dry storage facility. To support design studies of storage options a computational and experimental program has been conducted at the Savannah River Site (SRS). The main objective is to develop heat transfer models including natural convection effects internal to an interim dry storage canister and to geologic codisposal Waste Package (WP). Calculated temperatures will be used to demonstrate engineering viability of a dry storage option in enclosed interim storage and geologic repository WP and to assess the chemical and physical behaviors of the Al-SNF in the dry storage facilities. The current paper describes the modeling approaches and presents the computational results along with the experimental data.

  8. Heat Transfer Modeling of Dry Spent Nuclear Fuel Storage Facilities

    SciTech Connect (OSTI)

    Lee, S.Y.

    1999-01-13T23:59:59.000Z

    The present work was undertaken to provide heat transfer model that accurately predicts the thermal performance of dry spent nuclear fuel storage facilities. One of the storage configurations being considered for DOE Aluminum-clad Spent Nuclear Fuel (Al-SNF), such as the Material and Testing Reactor (MTR) fuel, is in a dry storage facility. To support design studies of storage options a computational and experimental program has been conducted at the Savannah River Site (SRS). The main objective is to develop heat transfer models including natural convection effects internal to an interim dry storage canister and to geological codisposal Waste Package (WP). Calculated temperatures will be used to demonstrate engineering viability of a dry storage option in enclosed interim storage and geological repository WP and to assess the chemical and physical behaviors of the Al-SNF in the dry storage facilities. The current paper describes the modeling approaches and presents the computational results along with the experimental data.

  9. Safeguards Guidance Document for Designers of Commercial Nuclear Facilities: International Nuclear Safeguards Requirements and Practices For Uranium Enrichment Plants

    SciTech Connect (OSTI)

    Robert Bean; Casey Durst

    2009-10-01T23:59:59.000Z

    This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called “Safeguards-by-Design.” This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichment plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, “International Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials,” published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is fundamentally a legal document. As such, it is written in a legalese that is understood by specialists in international law and treaties, but not by most outside of this field, including designers of nuclear facilities. For this reason, many of the requirements have been simplified and restated. However, in all cases, the relevant source document and passage is noted so that readers may trace the requirement to the source. This is a helpful living guide, since some of these requirements are subject to revision over time. More importantly, the practices by which the requirements are met are continuously modernized by the IAEA and nuclear facility operators to improve not only the effectiveness of international nuclear safeguards, but also the efficiency. As these improvements are made, the following guidelines should be updated and revised accordingly.

  10. INTERDICTION MODELING FOR SMUGGLED NUCLEAR MATERIAL Nedialko B. Dimitrov, Marc A. Gonzalez, Dennis P. Michalopoulos, David P. Morton,

    E-Print Network [OSTI]

    Morton, David

    (DOE) seeks to reduce the risk of illicit trafficking of nuclear material through international and smuggling of nuclear material and (ii) to detect and therefore prevent actual smuggling attemptsINTERDICTION MODELING FOR SMUGGLED NUCLEAR MATERIAL Nedialko B. Dimitrov, Marc A. Gonzalez, Dennis

  11. Quantum Internal Model Principle: Decoherence Control

    E-Print Network [OSTI]

    Narayan Ganesan; Tzyh-Jong Tarn

    2010-12-10T23:59:59.000Z

    In this article, we study the problem of designing a Decoherence Control for quantum systems with the help of a scalable ancillary quantum control and techniques from geometric control theory, in order to successfully and completely decouple an open quantum system from its environment. We re-formulate the problem of decoherence control as a disturbance rejection scheme which also leads us to the idea of Internal Model Principle for quantum control systems which is first of its kind in the literature. It is shown that decoupling a quantum disturbance from an open quantum system, is possible only with the help of a quantum controller which takes into account the model of the environmental interaction. This is demonstrated for a simple 2-qubit system wherein the effects of decoherence are completely eliminated. The theory provides conditions to be imposed on the controller to ensure perfect decoupling. Hence the problem of decoherence control naturally gives rise to the quantum internal model principle which relates the disturbance rejecting control to the model of the environmental interaction. Classical internal model principle and disturbance decoupling focus on different aspects viz. perfect output tracking and complete decoupling of output from external disturbances respectively. However for quantum systems, the two problems come together and merge in order to produce an effective platform for decoherence control. In this article we introduce a seminal connection between disturbance decoupling and the corresponding analog for internal model principle for quantum systems.

  12. NUCLEAR ENERGY SYSTEM COST MODELING

    SciTech Connect (OSTI)

    Francesco Ganda; Brent Dixon

    2012-09-01T23:59:59.000Z

    The U.S. Department of Energy’s Fuel Cycle Technologies (FCT) Program is preparing to perform an evaluation of the full range of possible Nuclear Energy Systems (NES) in 2013. These include all practical combinations of fuels and transmuters (reactors and sub-critical systems) in single and multi-tier combinations of burners and breeders with no, partial, and full recycle. As part of this evaluation, Levelized Cost of Electricity at Equilibrium (LCAE) ranges for each representative system will be calculated. To facilitate the cost analyses, the 2009 Advanced Fuel Cycle Cost Basis Report is being amended to provide up-to-date cost data for each step in the fuel cycle, and a new analysis tool, NE-COST, has been developed. This paper explains the innovative “Island” approach used by NE-COST to streamline and simplify the economic analysis effort and provides examples of LCAE costs generated. The Island approach treats each transmuter (or target burner) and the associated fuel cycle facilities as a separate analysis module, allowing reuse of modules that appear frequently in the NES options list. For example, a number of options to be screened will include a once-through uranium oxide (UOX) fueled light water reactor (LWR). The UOX LWR may be standalone, or may be the first stage in a multi-stage system. Using the Island approach, the UOX LWR only needs to be modeled once and the module can then be reused on subsequent fuel cycles. NE-COST models the unit operations and life cycle costs associated with each step of the fuel cycle on each island. This includes three front-end options for supplying feedstock to fuel fabrication (mining/enrichment, reprocessing of used fuel from another island, and/or reprocessing of this island’s used fuel), along with the transmuter and back-end storage/disposal. Results of each island are combined based on the fractional energy generated by each islands in an equilibrium system. The cost analyses use the probability distributions of key parameters and employs Monte Carlo sampling to arrive at an island’s cost probability density function (PDF). When comparing two NES to determine delta cost, strongly correlated parameters can be cancelled out so that only the differences in the systems contribute to the relative cost PDFs. For example, one comparative analysis presented in the paper is a single stage LWR-UOX system versus a two-stage LWR-UOX to LWR-MOX system. In this case, the first stage of both systems is the same (but with different fractional energy generation), while the second stage of the UOX to MOX system uses the same type transmuter but the fuel type and feedstock sources are different. In this case, the cost difference between systems is driven by only the fuel cycle differences of the MOX stage.

  13. World nuclear fuel market: proceedings of the international conference on nuclear energy

    SciTech Connect (OSTI)

    Not Available

    1982-01-01T23:59:59.000Z

    Thirteen papers, along with discussion and comments, are divided into four conference sessions covering: the prospect for primary markets for enriched uranium; secondary trading markets for enriched uranium; the management of irradiatied fuel and economics of reprocessing; and an evaluation of plutonium recycling in thermal reactors. The speakers address technical, economic, and political issues relating to both front-end and back-end management of the fuel cycle. The papers were presented at the 9th International Conference on Nuclear Energy in Nice, France during October, 1982. A separate abstract was prepared for each of the 13 papers selected for the Energy Data Base (EDB), Energy Research Abstracts (ERA), and Energy Abstracts for Policy Analysis (EAPA). (DCK)

  14. Computer aided nuclear reactor modeling

    E-Print Network [OSTI]

    Warraich, Khalid Sarwar

    1995-01-01T23:59:59.000Z

    after model has been sent to CENTAR). We then present an interactive, graphical, icon based modeling program, Alpha, that lets the user "draw" the model on screen and translates it into a syn tactically correct CENTAR input model which is also free...

  15. OPTIMAL CONTROL WITH ADAPTIVE INTERNAL DYNAMICS MODELS

    E-Print Network [OSTI]

    Vijayakumar, Sethu

    . The optimal feedback control law for systems with non-linear dynamics and non-quadratic costs can be foundOPTIMAL CONTROL WITH ADAPTIVE INTERNAL DYNAMICS MODELS Djordje Mitrovic, Stefan Klanke, and Sethu, optimal control, adaptive control, robot simulation Abstract: Optimal feedback control has been proposed

  16. Synopsis of the international workshop on illicit trafficking of nuclear material

    SciTech Connect (OSTI)

    Niemeyer, S.

    1997-03-01T23:59:59.000Z

    In this paper a synopsis is presented of the second ITWG (Nuclear Smuggling International Technical Working Group) meeting that was held in Obninsk, Russia, on December 2-4, 1996, at the Institute of Physics and Power Engineering.

  17. Nuclear ribosomal internal transcribed spacer (ITS) region as a universal DNA barcode marker for Fungi

    E-Print Network [OSTI]

    Nuclear ribosomal internal transcribed spacer (ITS) region as a universal DNA barcode marker Biodiversity (Mycology and Microbiology), Agriculture and Agri-Food Canada, Ottawa, ON, Canada K1A 0C6; c the nuclear ribosomal RNA cistron were compared together with regions of three representative protein- coding

  18. Nuclear Fallout Models – An Overview

    SciTech Connect (OSTI)

    Hodges, Matthew [UNLV

    2014-10-21T23:59:59.000Z

    This presentation is an introduction to a full report, which is a tutorial for individuals using the products of the models reviewed.

  19. Modeling the Nuclear Fuel Cycle

    SciTech Connect (OSTI)

    Jacob J. Jacobson; Mary Lou Dunzik-Gougar; Christopher A. Juchau

    2010-08-01T23:59:59.000Z

    A review of existing nuclear fuel cycle systems analysis codes was performed to determine if any existing codes meet technical and functional requirements defined for a U.S. national program supporting the global and domestic assessment, development and deployment of nuclear energy systems. The program would be implemented using an interconnected architecture of different codes ranging from the fuel cycle analysis code, which is the subject of the review, to fundamental physical and mechanistic codes. Four main functions are defined for the code: (1) the ability to characterize and deploy individual fuel cycle facilities and reactors in a simulation, while discretely tracking material movements, (2) the capability to perform an uncertainty analysis for each element of the fuel cycle and an aggregate uncertainty analysis, (3) the inclusion of an optimization engine able to optimize simultaneously across multiple objective functions, and (4) open and accessible code software and documentation to aid in collaboration between multiple entities and facilitate software updates. Existing codes, categorized as annualized or discrete fuel tracking codes, were assessed according to the four functions and associated requirements. These codes were developed by various government, education and industrial entities to fulfill particular needs. In some cases, decisions were made during code development to limit the level of detail included in a code to ease its use or to focus on certain aspects of a fuel cycle to address specific questions. The review revealed that while no two of the codes are identical, they all perform many of the same basic functions. No code was able to perform defined function 2 or several requirements of functions 1 and 3. Based on this review, it was concluded that the functions and requirements will be met only with development of a new code, referred to as GENIUS.

  20. International Source Book: Nuclear Fuel Cycle Research and Development Vol 1 Volume 1

    SciTech Connect (OSTI)

    Harmon,, K. M.; Lakey,, L. T.

    1983-07-01T23:59:59.000Z

    This document starts with an overview that summarizes nuclear power policies and waste management activities for nations with significant commercial nuclear fuel cycle activities either under way or planned. A more detailed program summary is then included for each country or international agency conducting nuclear fuel cycle and waste management research and development. This first volume includes the overview and the program summaries of those countries listed alphabetically from Argentina to Italy.

  1. International Source Book: Nuclear Fuel Cycle Research and Development Volume 2

    SciTech Connect (OSTI)

    Harmon,, K. M.; Lakey,, L. T.

    1982-11-01T23:59:59.000Z

    This document starts with an overview that summarizes nuclear power policies and waste management activities for nations with significant commercial nuclear fuel cycle activities either under way or planned. A more detailed program summary is then included for each country or international agency conducting nuclear fuel cycle and waste management research and development. This second volume includes the program summaries of those countries listed alphabetically from Japan to Yugoslavia. Information on international agencies and associations, particularly the IAEA, NEA, and CEC, is provided also.

  2. Nuclear Decay Data in the MIRD (Medical Internal Radiation Dose) Format

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    MIRD is a database of evaluated nuclear decay data for over 2,100 radioactive nuclei. Data are extracted from ENSDF, processed by the program RadList, and used for medical internal radiation dose calculations. When using the MIRD interface, tables of nuclear and atomic radiations from nuclear decay and decay scheme drawings will be produced in the MIRD format from the Evaluated Nuclear Structure Data File (ENSDF) for the specified nuclide. Output may be either HTML-formatted tables and JPEG drawings, PostScript tables and drawings, or PDF tables and drawings.

  3. Utility system integration and optimization models for nuclear power management

    E-Print Network [OSTI]

    Deaton, Paul Ferris

    1973-01-01T23:59:59.000Z

    A nuclear power management model suitable for nuclear utility systems optimization has been developed for use in multi-reactor fuel management planning over periods of up to ten years. The overall utility planning model ...

  4. Nuclear winter revisited with a modern climate model and current nuclear arsenals: Still catastrophic consequences

    E-Print Network [OSTI]

    Stenchikov, Georgiy L.

    drops at the surface that would threaten global agriculture for at least a year. The global nuclear of world agriculture, the arms race and cold war ended. Since then, the global nuclear arsenal has beenNuclear winter revisited with a modern climate model and current nuclear arsenals: Still

  5. Documentation of a Model Action Plan to Deter Illicit Nuclear Trafficking

    SciTech Connect (OSTI)

    Smith, D; Kristo, M; Niemeyer, S; Dudder, G

    2006-07-28T23:59:59.000Z

    Theft, illegal possession, smuggling, or attempted unauthorized sale of nuclear and radiological materials remains a worldwide problem. The Nuclear Smuggling International Technical Working Group (ITWG) has adopted a model action plan to guide investigation of these cases through a systematic approach to nuclear forensics. The model action plan was recently documented and provides recommendations concerning incident response, collection of evidence in conformance with required legal standards, laboratory sampling and distribution of samples, radioactive materials analysis, including categorization and characterization of samples, forensics analysis of conventional evidence, and case development including interpretation of forensic signatures.

  6. Documentation of a model action plan to deter illicit nuclear trafficking

    SciTech Connect (OSTI)

    Smith, D. K.; Kristo, M. J.; Niemeyer, S.; Dudder, Gordon B.

    2008-05-04T23:59:59.000Z

    Theft, illegal possession, smuggling, or attempted unathorized sale of nuclear and radiological materials remains a worldwide problem. The Nuclear Smuggling International Technical Working Group (ITWG) has adopted a model action plan to guide investigation of these cases through a systematic approach to nuclear forensics. The model action plan was recently documented and provides recommendations concerning incident response, collection of evidence in conformance with required legal standards, laboratory sampling and distribution of samples, radioactive materials analysis, including categorization and characterization of samples, forensics analysis of conventional evidence, and case development including interpretation of forensic signatures.

  7. INTERNATIONAL JOURNAL OF HYDROGEN ENERGY Accepted June 2008 HYDROGEN STORAGE FOR MIXED WIND-NUCLEAR POWER PLANTS IN

    E-Print Network [OSTI]

    Cañizares, Claudio A.

    evaluation of hydrogen production and storage for a mixed wind-nuclear power plant considering some new : nuclear power plant production (MW) GP : total wind-nuclear power plant production (MW) EP : electrolyzerINTERNATIONAL JOURNAL OF HYDROGEN ENERGY Accepted June 2008 1 HYDROGEN STORAGE FOR MIXED WIND-NUCLEAR

  8. Proceedings of GLOBAL 2013: International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads

    SciTech Connect (OSTI)

    NONE

    2013-07-01T23:59:59.000Z

    The Global conference is a forum for the discussion of the scientific, technical, social and regulatory aspects of the nuclear fuel cycle. Relevant topics include global utilization of nuclear energy, current fuel cycle technologies, advanced reactors, advanced fuel cycles, nuclear nonproliferation and public acceptance.

  9. ICENES `91:Sixth international conference on emerging nuclear energy systems. Program and abstracts

    SciTech Connect (OSTI)

    Not Available

    1991-12-31T23:59:59.000Z

    This document contains the program and abstracts of the sessions at the Sixth International Conference on Emerging Nuclear Energy Systems held June 16--21, 1991 at Monterey, California. These sessions included: The plenary session, fission session, fission and nonelectric session, poster session 1P; (space propulsion, space nuclear power, electrostatic confined fusion, fusion miscellaneous, inertial confinement fusion, {mu}-catalyzed fusion, and cold fusion); Advanced fusion session, space nuclear session, poster session 2P, (nuclear reactions/data, isotope separation, direct energy conversion and exotic concepts, fusion-fission hybrids, nuclear desalting, accelerator waste-transmutation, and fusion-based chemical recycling); energy policy session, poster session 3P (energy policy, magnetic fusion reactors, fission reactors, magnetically insulated inertial fusion, and nuclear explosives for power generation); exotic energy storage and conversion session; and exotic energy storage and conversion; review and closing session.

  10. Elementary! A Nuclear Forensics Workshop Teaches Vital Skills to International Practitioners

    SciTech Connect (OSTI)

    Brim, Cornelia P.; Minnema, Lindsay T.

    2014-04-01T23:59:59.000Z

    The article describes the Nuclear Forensics Workshop sponsored by the International Atomic Energy Agency (IAEA), the Office of Nonproliferation and International Security (NIS) and hosted by Pacific Northwest National Laboratory October 28-November 8, 2013 in Richland,Washington. Twenty-six participants from 10 countries attended the workshop. Experts from from Los Alamos, Lawrence Livermore, and Pacific Northwest national laboratories collaborated with an internationally recognized cadre of experts from the U.S. Department of Homeland Security and other U.S. agencies, IAEA, the Australian Nuclear Science and Technology Organisation, the United Kingdom Atomic Weapons Establishment (AWE), and the European Union Joint Research Center Institute for Transuranium Elements, to train practitioners in basic methodologies of nuclear forensic examinations.

  11. International nuclear fuel cycle fact book. [Contains glossary

    SciTech Connect (OSTI)

    Leigh, I.W.; Lakey, L.T.; Schneider, K.J.; Silviera, D.J.

    1987-01-01T23:59:59.000Z

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is a consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

  12. Internal Stress in a Model Elasto-Plastic Fluid

    E-Print Network [OSTI]

    Takeshi Ooshida; Ken Sekimoto

    2005-12-03T23:59:59.000Z

    Plastic materials can carry memory of past mechanical treatment in the form of internal stress. We introduce a natural definition of the vorticity of internal stress in a simple two-dimensional model of elasto-plastic fluids, which generates the internal stress. We demonstrate how the internal stress is induced under external loading, and how the presence of the internal stress modifies the plastic behavior.

  13. Safeguards Guidance for Designers of Commercial Nuclear Facilities – International Safeguards Requirements for Uranium Enrichment Plants

    SciTech Connect (OSTI)

    Philip Casey Durst; Scott DeMuth; Brent McGinnis; Michael Whitaker; James Morgan

    2010-04-01T23:59:59.000Z

    For the past two years, the United States National Nuclear Security Administration, Office of International Regimes and Agreements (NA-243), has sponsored the Safeguards-by-Design Project, through which it is hoped new nuclear facilities will be designed and constructed worldwide more amenable to nuclear safeguards. In the course of this project it was recognized that commercial designer/builders of nuclear facilities are not always aware of, or understand, the relevant domestic and international safeguards requirements, especially the latter as implemented by the International Atomic Energy Agency (IAEA). To help commercial designer/builders better understand these requirements, a report was prepared by the Safeguards-by-Design Project Team that articulated and interpreted the international nuclear safeguards requirements for the initial case of uranium enrichment plants. The following paper summarizes the subject report, the specific requirements, where they originate, and the implications for design and construction. It also briefly summarizes the established best design and operating practices that designer/builder/operators have implemented for currently meeting these requirements. In preparing the subject report, it is recognized that the best practices are continually evolving as the designer/builder/operators and IAEA consider even more effective and efficient means for meeting the safeguards requirements and objectives.

  14. Few-body models for nuclear astrophysics

    SciTech Connect (OSTI)

    Descouvemont, P., E-mail: pdesc@ulb.ac.be [Physique Nucléaire Théorique et Physique Mathématique, C.P. 229, Université Libre de Bruxelles (ULB), B 1050 Brussels (Belgium); Baye, D., E-mail: dbaye@ulb.ac.be [Physique Nucléaire Théorique et Physique Mathématique, C.P. 229, Université Libre de Bruxelles (ULB), B 1050 Brussels (Belgium); Physique Quantique, C.P. 165/82, Université Libre de Bruxelles (ULB), B 1050 Brussels (Belgium); Suzuki, Y., E-mail: suzuki@nt.sc.niigata-u.ac.jp [Department of Physics, Niigata University, Niigata 950-2181 (Japan); RIKEN Nishina Center, Wako 351-0198 (Japan); Aoyama, S., E-mail: aoyama@cc.niigata-u.ac.jp [Center for Academic Information Service, Niigata University, Niigata 950-2181 (Japan); Arai, K., E-mail: arai@nagaoka-ct.ac.jp [Division of General Education, Nagaoka National College of Technology, 888 Nishikatakai, Nagaoka, Niigata 940-8532 (Japan)

    2014-04-15T23:59:59.000Z

    We present applications of microscopic models to nuclear reactions of astrophysical interest, and we essentially focus on few-body systems. The calculation of radiative-capture and transfer cross sections is outlined, and we discuss the corresponding reaction rates. Microscopic theories are briefly presented, and we emphasize on the matrix elements of four-body systems. The microscopic extension of the R-matrix theory to nuclear reactions is described. Applications to the {sup 2}H(d, ?){sup 4}He, {sup 2}H(d, p){sup 3}H and {sup 2}H(d, n){sup 3}He reactions are presented. We show the importance of the tensor force to reproduce the low-energy behaviour of the cross sections.

  15. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 034007 (8pp) doi:10.1088/0029-5515/50/3/034007

    E-Print Network [OSTI]

    Morrison, Philip J.,

    2010-01-01T23:59:59.000Z

    -dimensional (2D), two-field version of this model has been intensively investigated in [4­6] and a 3D extensionIOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 034007 for obtaining 0029-5515/10/034007+08$30.00 1 © 2010 IAEA, Vienna Printed in the UK #12;Nucl. Fusion 50 (2010

  16. International Symposium on Fusion Nuclear Technology (ISFNT-5) SAFETY ISSUES ASSOCIATED WITH MOBILIZED ACTIVATION

    E-Print Network [OSTI]

    California at Los Angeles, University of

    International Symposium on Fusion Nuclear Technology (ISFNT-5) SAFETY ISSUES ASSOCIATED WITH MOBILIZED ACTIVATION PRODUCTS IN SELECTED APEX DESIGNS K. A. McCarthy, D. A. Petti, R. L. Moore, and B. J. In this paper we concentrate on mobilization of first wall materials during ingress events, and provide guidance

  17. Advanced international training course on state systems of accounting for and control of nuclear materials

    SciTech Connect (OSTI)

    Not Available

    1981-10-01T23:59:59.000Z

    This report incorporates all lectures and presentations at the Advanced International Training Course on State Systems of Accounting for and Control of Nuclear Material held April 27 through May 12, 1981 at Santa Fe and Los Alamos, New Mexico, and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards. Major emphasis for the 1981 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory, the Battelle Pacific Northwest Laboratory, and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at both the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, Richland, Washington.

  18. Sandia Weapon Intern Program visits KCP | National Nuclear Security

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved: 5-13-14 FEDERALAmerica HighSTART Signed |Nuclear

  19. Savannah River Site hosts military interns | National Nuclear Security

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved: 5-13-14 FEDERALAmerica HighSTART SignedhostsNuclearAdministration

  20. Weapons Intern Program participants visit Pantex | National Nuclear

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved: 5-13-14Russian Nuclear Warheads Arrives inAdministrationSecurity

  1. Statement to the IAEA International Conference on Nuclear Security |

    Office of Environmental Management (EM)

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently AskedEnergyIssues DOE's NuclearSpurring SolarSystem,

  2. International Framework for Nuclear Energy Cooperation to Hold

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    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 onYouTube YouTube Note: Since the.pdfBreaking ofOil & Gas » Methane Hydrate » International

  3. International Nuclear Energy Research Initiative (I-NERI) Annual Reports |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    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 onYouTube YouTube Note: Since the.pdfBreaking ofOil & Gas » Methane Hydrate » InternationalEnergyDepartment of

  4. International Nuclear Energy Research Initiative: 2012 Annual Report |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    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 onYouTube YouTube Note: Since the.pdfBreaking ofOil & Gas » Methane Hydrate » InternationalEnergyDepartment

  5. International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-15 NURETH15-xxx Pisa, Italy, May 12-15, 2013

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-15 NURETH15-xxx technologies in the context of generation IV nuclear power reactors. In order to improve electric efficiency during last years as a possible energy conversion cycle for Sodium nuclear Fast Reactors (SFRs) [1

  6. Porous nuclear fuel element with internal skeleton for high-temperature gas-cooled nuclear reactors

    DOE Patents [OSTI]

    Youchison, Dennis L.; Williams, Brian E.; Benander, Robert E.

    2013-09-03T23:59:59.000Z

    Porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's), and to processes for fabricating them. Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, the nuclear fuel may be deposited inside of a highly porous skeletal structure made of, for example, reticulated vitreous carbon foam.

  7. Global economics/energy/environmental (E{sup 3}) modeling of long-term nuclear energy futures

    SciTech Connect (OSTI)

    Krakowski, R.A.; Davidson, J.W.; Bathke, C.G.; Arthur, E.D.; Wagner, R.L. Jr.

    1997-09-01T23:59:59.000Z

    A global energy, economics, environment (E{sup 3}) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Using this model, consistent nuclear energy scenarios are constructed. A spectrum of future is examined at two levels in a hierarchy of scenario attributes in which drivers are either external or internal to nuclear energy. Impacts of a range of nuclear fuel-cycle scenarios are reflected back to the higher-level scenario attributes. An emphasis is placed on nuclear materials inventories (in magnitude, location, and form) and their contribution to the long-term sustainability of nuclear energy and the future competitiveness of both conventional and advanced nuclear reactors.

  8. Technosocial Modeling for Determining the Status and Nature of a State’s Nuclear Activities

    SciTech Connect (OSTI)

    Gastelum, Zoe N.; Harvey, Julia B.

    2009-09-25T23:59:59.000Z

    The International Atomic Energy Agency State Evaluation Process: The Role of Information Analysis in Reaching Safeguards Conclusions (Mathews et al. 2008), several examples of nonproliferation models using analytical software were developed that may assist the IAEA with collecting, visualizing, analyzing, and reporting information in support of the State Evaluation Process. This paper focuses on one of the examples a set of models developed in the Proactive Scenario Production, Evidence Collection, and Testing (ProSPECT) software that evaluates the status and nature of a state’s nuclear activities. The models use three distinct subject areas to perform this assessment: the presence of nuclear activities, the consistency of those nuclear activities with national nuclear energy goals, and the geopolitical context in which those nuclear activities are taking place. As a proof-of-concept for the models, a crude case study was performed. The study, which attempted to evaluate the nuclear activities taking place in Syria prior to September 2007, yielded illustrative, yet inconclusive, results. Due to the inconclusive nature of the case study results, changes that may improve the model’s efficiency and accuracy are proposed.

  9. Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Software Verification and Validation (V&V) Plan Requirements Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software Verification and Validation (V&V) Plan Requirements...

  10. Numerically Estimating Internal Models of Dynamic Virtual Objects

    E-Print Network [OSTI]

    Sekuler, Robert

    human subjects to manipulate a computer-animated virtual object. This virtual object (vO) was a high, human cognition, human information processing, ideal performer, internal model, virtual object, virtual, specifically how humans acquire an internal model of a dynamic virtual object. Our methodology minimizes

  11. Nuclear EMC Effect in a Statistical Model

    E-Print Network [OSTI]

    Yunhua Zhang; Lijing Shao; Bo-Qiang Ma

    2009-09-02T23:59:59.000Z

    A simple statistical model in terms of light-front kinematic variables is used to explain the nuclear EMC effect in the range $x \\in [0.2,~0.7]$, which was constructed by us previously to calculate the parton distribution functions (PDFs) of the nucleon. Here, we treat the temperature $T$ as a parameter of the atomic number $A$, and get reasonable results in agreement with the experimental data. Our results show that the larger $A$, the lower $T$ thus the bigger volume $V$, and these features are consistent with other models. Moreover, we give the predictions of the quark distribution ratios, \\emph{i.e.}, $q^A(x) / q^D(x)$, $\\bar{q}^A(x) / \\bar{q}^D(x)$, and $s^A(x) / s^D(x)$, and also the gluon ratio $g^A(x) / g^D(x)$ for iron as an example. The predictions are different from those by other models, thus experiments aiming at measuring the parton ratios of antiquarks, strange quarks, and gluons can provide a discrimination of different models.

  12. The Lifecycle of Bayesian Network Models Developed for Multi-Source Signature Assessment of Nuclear Programs

    SciTech Connect (OSTI)

    Gastelum, Zoe N.; White, Amanda M.; Whitney, Paul D.; Gosink, Luke J.; Sego, Landon H.

    2013-06-04T23:59:59.000Z

    The Multi-Source Signatures for Nuclear Programs project, part of Pacific Northwest National Laboratory’s (PNNL) Signature Discovery Initiative, seeks to computationally capture expert assessment of multi-type information such as text, sensor output, imagery, or audio/video files, to assess nuclear activities through a series of Bayesian network (BN) models. These models incorporate knowledge from a diverse range of information sources in order to help assess a country’s nuclear activities. The models span engineering topic areas, state-level indicators, and facility-specific characteristics. To illustrate the development, calibration, and use of BN models for multi-source assessment, we present a model that predicts a country’s likelihood to participate in the international nuclear nonproliferation regime. We validate this model by examining the extent to which the model assists non-experts arrive at conclusions similar to those provided by nuclear proliferation experts. We also describe the PNNL-developed software used throughout the lifecycle of the Bayesian network model development.

  13. Review of the Shoreham Nuclear Power Station Probabilistic Risk Assessment: internal events and core damage frequency

    SciTech Connect (OSTI)

    Ilberg, D.; Shiu, K.; Hanan, N.; Anavim, E.

    1985-11-01T23:59:59.000Z

    A review of the Probabilistic Risk Assessment of the Shoreham Nuclear Power Station was conducted with the broad objective of evaluating its risks in relation to those identified in the Reactor Safety Study (WASH-1400). The scope of the review was limited to the ''front end'' part, i.e., to the evaluation of the frequencies of states in which core damage may occur. Furthermore, the review considered only internally generated accidents, consistent with the scope of the PRA. The review included an assessment of the assumptions and methods used in the Shoreham study. It also encompassed a reevaluation of the main results within the scope and general methodological framework of the Shoreham PRA, including both qualitative and quantitative analyses of accident initiators, data bases, and accident sequences which result in initiation of core damage. Specific comparisons are given between the Shoreham study, the results of the present review, and the WASH-1400 BWR, for the core damage frequency. The effect of modeling uncertainties was considered by a limited sensitivity study so as to show how the results would change if other assumptions were made. This review provides an independently assessed point value estimate of core damage frequency and describes the major contributors, by frontline systems and by accident sequences. 17 figs., 81 tabs.

  14. Nuclear nonproliferation and safety: Challenges facing the International Atomic Energy Agency

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    The Chairman of the Senate Committee on Govermental Affairs asked the United States General Accounting Office (GAO) to review the safeguards and nuclear power plant safety programs of the International Atomic Energy Agency (IAEA). This report examines (1) the effectiveness of IAEA`s safeguards program and the adequacy of program funding, (2) the management of U.S. technical assistance to the IAEA`s safeguards program, and (3) the effectiveness of IAEA`s program for advising United Nations (UN) member states about nuclear power plant safety and the adequacy of program funding. Under its statute and the Treaty on the Non-Proliferation of Nuclear Weapons, IAEA is mandated to administer safeguards to detect diversions of significant quantities of nuclear material from peaceful uses. Because of limits on budget growth and unpaid contributions, IAEA has had difficulty funding the safeguards program. IAEA also conducts inspections of facilities or locations containing declared nuclear material, and manages a program for reviewing the operational safety of designated nuclear power plants. The U.S. technical assistance program for IAEA safeguards, overseen by an interagency coordinating committee, has enhanced the agency`s inspection capabilities, however, some weaknesses still exist. Despite financial limitations, IAEA is meeting its basic safety advisory responsibilities for advising UN member states on nuclear safety and providing requested safety services. However, IAEA`s program for reviewing the operational safety of nuclear power plants has not been fully effective because the program is voluntary and UN member states have not requested IAEA`s review of all nuclear reactors with serious problems. GAO believes that IAEA should have more discretion in selecting reactors for review.

  15. Propagation of uncertainties in the nuclear DFT models

    E-Print Network [OSTI]

    Markus Kortelainen

    2014-09-04T23:59:59.000Z

    Parameters of the nuclear density functional theory (DFT) models are usually adjusted to experimental data. As a result they carry certain theoretical error, which, as a consequence, carries out to the predicted quantities. In this work we address the propagation of theoretical error, within the nuclear DFT models, from the model parameters to the predicted observables. In particularly, the focus is set on the Skyrme energy density functional models.

  16. Modeling fabrication of nuclear components: An integrative approach

    SciTech Connect (OSTI)

    Hench, K.W.

    1996-08-01T23:59:59.000Z

    Reduction of the nuclear weapons stockpile and the general downsizing of the nuclear weapons complex has presented challenges for Los Alamos. One is to design an optimized fabrication facility to manufacture nuclear weapon primary components in an environment of intense regulation and shrinking budgets. This dissertation presents an integrative two-stage approach to modeling the casting operation for fabrication of nuclear weapon primary components. The first stage optimizes personnel radiation exposure for the casting operation layout by modeling the operation as a facility layout problem formulated as a quadratic assignment problem. The solution procedure uses an evolutionary heuristic technique. The best solutions to the layout problem are used as input to the second stage - a simulation model that assesses the impact of competing layouts on operational performance. The focus of the simulation model is to determine the layout that minimizes personnel radiation exposures and nuclear material movement, and maximizes the utilization of capacity for finished units.

  17. Models of neutron star atmospheres enriched with nuclear burning ashes

    E-Print Network [OSTI]

    Nättilä, Joonas; Kajava, Jari J E; Poutanen, Juri

    2015-01-01T23:59:59.000Z

    Low-mass X-ray binaries hosting neutron stars (NS) exhibit thermonuclear (type-I) X-ray bursts, which are powered by unstable nuclear burning of helium and/or hydrogen into heavier elements deep in the NS "ocean". In some cases the burning ashes may rise from the burning depths up to the NS photosphere by convection, leading to the appearance of the metal absorption edges in the spectra, which then force the emergent X-ray burst spectra to shift toward lower energies. These effects may have a substantial impact on the color correction factor $f_c$ and the dilution factor $w$, the parameters of the diluted blackbody model $F_E \\approx w B_E(f_c T_{eff})$ that is commonly used to describe the emergent spectra from NSs. The aim of this paper is to quantify how much the metal enrichment can change these factors. We have developed a new NS atmosphere modeling code, which has a few important improvements compared to our previous code required by inclusion of the metals. The opacities and the internal partition func...

  18. International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6) Nara, Japan, October 4-8, 2004.

    E-Print Network [OSTI]

    The 6th International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6 Junbeom Yoo, Suhyun Park, Hojung Bang, Taihyo Kim, Sungdeok Cha Korea Advanced Institute of Science for assuring quality of software. In the area of nuclear power plant control systems, testing on software

  19. White paper on VU for Modeling Nuclear Energy Systems

    SciTech Connect (OSTI)

    Klein, R; Turinsky, P

    2009-05-07T23:59:59.000Z

    The purpose of this whitepaper is to provide a framework for understanding the role that Verification and Validation (V&V), Uncertainty Quantification (UQ) and Risk Quantification, collectively referred to as VU, is expected to play in modeling nuclear energy systems. We first provide background for the modeling of nuclear energy based systems. We then provide a brief discussion that emphasizes the critical elements of V&V as applied to nuclear energy systems but is general enough to cover a broad spectrum of scientific and engineering disciplines that include but are not limited to astrophysics, chemistry, physics, geology, hydrology, chemical engineering, mechanical engineering, civil engineering, electrical engineering, nu nuclear engineering material clear science science, etc. Finally, we discuss the critical issues and challenges that must be faced in the development of a viable and sustainable VU program in support of modeling nuclear energy systems.

  20. Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

    SciTech Connect (OSTI)

    Kisner, Roger A [ORNL; Mullens, James Allen [ORNL; Wilson, Thomas L [ORNL; Wood, Richard Thomas [ORNL; Korsah, Kofi [ORNL; Qualls, A L [ORNL; Muhlheim, Michael David [ORNL; Holcomb, David Eugene [ORNL; Loebl, Andy [ORNL

    2007-08-01T23:59:59.000Z

    Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

  1. BFS, a Legacy to the International Reactor Physics, Criticality Safety, and Nuclear Data Communities

    SciTech Connect (OSTI)

    J. Blair Briggs; Anatoly Tsibulya; Yevgeniy Rozhikhin

    2012-03-01T23:59:59.000Z

    Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. Two Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA) activities, the International Criticality Safety Benchmark Evaluation Project (ICSBEP), initiated in 1992, and the International Reactor Physics Experiment Evaluation Project (IRPhEP), initiated in 2003, have been identifying existing integral experiment data, evaluating those data, and providing integral benchmark specifications for methods and data validation for nearly two decades. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. Data provided by these two projects will be of use to the international reactor physics, criticality safety, and nuclear data communities for future decades The Russian Federation has been a major contributor to both projects with the Institute of Physics and Power Engineering (IPPE) as the major contributor from the Russian Federation. Included in the benchmark specifications from the BFS facilities are 34 critical configurations from BFS-49, 61, 62, 73, 79, 81, 97, 99, and 101; spectral characteristics measurements from BFS-31, 42, 57, 59, 61, 62, 73, 97, 99, and 101; reactivity effects measurements from BFS-62-3A; reactivity coefficients and kinetics measurements from BFS-73; and reaction rate measurements from BFS-42, 61, 62, 73, 97, 99, and 101.

  2. International Conference on the Physics of Reactors "Nuclear Power: A Sustainable Resource" Casino-Kursaal Conference Center, Interlaken, Switzerland, September 14-19, 2008

    E-Print Network [OSTI]

    Boyer, Edmond

    International Conference on the Physics of Reactors "Nuclear Power: A Sustainable Resource" Casino International Forum for the new nuclear energy systems, we have developed a new concept of molten salt reactor Products which poison the core can be extracted without stopping reactor operation; nuclear waste

  3. International Topical Meeting on Nuclear Reactor Thermal hydraulics, NURETH-15 NURETH15-599 Pisa, Italy, May 12-17, 2013

    E-Print Network [OSTI]

    Haviland, David

    The 15th International Topical Meeting on Nuclear Reactor Thermal hydraulics, NURETH-15 NURETH15 of steam explosion shock wave propagation. #12;The 15th International Topical Meeting on Nuclear Reactor to note that stratified melt-coolant configuration can be formed in several scenarios of nuclear reactor

  4. International Legal Framework for Denuclearization and Nuclear Disarmament – Present Situation and Prospects

    SciTech Connect (OSTI)

    Gastelum, Zoe N.

    2012-12-16T23:59:59.000Z

    This thesis is the culminating project for my participation in the OECD NEA International School of Nuclear Law. This paper will begin by providing a historical background to current disarmament and denuclearization treaties. This paper will discuss the current legal framework based on current and historical activities related to denuclearization and nuclear disarmament. Then, it will propose paths forward for the future efforts, and describe the necessary legal considerations. Each treaty or agreement will be examined in respect to its requirements for: 1) limitations and implementation; 2) and verification and monitoring. Then, lessons learned in each of the two areas (limitations and verification) will be used to construct a proposed path forward at the end of this paper.

  5. (International symposium on fusion nuclear technology, Tokyo, Japan, April 10, 1988): Foreign trip report

    SciTech Connect (OSTI)

    Bell, G.E.

    1988-05-24T23:59:59.000Z

    A presentation entitled ''Experimental and Analytical Investigations of Mass Transfer Processes of /sup 12/Cr-1MoVW Steel in Thermally-Convected Lithium Systems'' was made by G.E. Bell (coauthors M.A. Abdou (UCLA) and P.F. Tortorelli (ORNL)) at a poster session of the International Symposium on Fusion Nuclear Technology (ISFNT). The results presented were taken from work performed while Mr. Bell was an Oak Ridge Associated Universities Fellow at ORNL from October 1986 to March 1988. A consistent theme throughout the conference was the need for collaboration within and among national efforts to achieve the goal of an engineering test reactor.

  6. Proceedings of the Third International Workshop on the implementation of ALARA at nuclear power plants

    SciTech Connect (OSTI)

    Khan, T.A. [comp.] [Brookhaven National Lab., Upton, NY (United States); Roecklein, A.K. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications

    1995-03-01T23:59:59.000Z

    This report contains the papers presented and the discussions that took place at the Third International Workshop on ALARA Implementation at Nuclear Power Plants, held in Hauppauge, Long Island, New York from May 8--11, 1994. The purpose of the workshop was to bring together scientists, engineers, health physicists, regulators, managers and other persons who are involved with occupational dose control and ALARA issues. The countries represented were: Canada, Finland, France, Germany, Japan, Korea, Mexico, the Netherlands, Spain, Sweden, the United Kingdom and the United States. The workshop was organized into twelve sessions and three panel discussions. Individual papers have been cataloged separately.

  7. Fire models for assessment of nuclear power plant fires

    SciTech Connect (OSTI)

    Nicolette, V.F.; Nowlen, S.P.

    1989-01-01T23:59:59.000Z

    This paper reviews the state-of-the-art in available fire models for the assessment of nuclear power plants fires. The advantages and disadvantages of three basic types of fire models (zone, field, and control volume) and Sandia's experience with these models will be discussed. It is shown that the type of fire model selected to solve a particular problem should be based on the information that is required. Areas of concern which relate to all nuclear power plant fire models are identified. 17 refs., 6 figs.

  8. Proceedings of the Fourth International Workshop on Software Engineering and Artificial Intelligence for High Energy and Nuclear Physics, eds. B. Denby and D. PerretGallix, International Journal of Modern

    E-Print Network [OSTI]

    Peterson, Carsten

    Intelligence for High Energy and Nuclear Physics, eds. B. Denby and D. Perret­Gallix, International Journal on Software Engineering and Artificial Intelligence for High Energy and Nuclear Physics, Pisa, Italy, April 3

  9. Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational

    E-Print Network [OSTI]

    Nagurney, Anna

    Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach Anna Medical Nuclear Supply Chain Design #12;Outline Background and Motivation Supply Chain Challenges The Medical Nuclear Supply Chain Network Design Model The Computational Approach Summary and Suggestions

  10. RTI International Develops SSL Luminaire Reliability Model |...

    Broader source: Energy.gov (indexed) [DOE]

    is developing and validating accelerated life testing (ALT) methodologies and a reliability model for predicting the lifetime of integrated solid-state lighting...

  11. Ground motion data for International Collider models

    SciTech Connect (OSTI)

    Volk, J.T.; LeBrun, P.; Shiltsev, V.; Singatulin, S.; /Fermilab

    2007-11-01T23:59:59.000Z

    The proposed location for the International Linear Collider (ILC) in the Americas region is Fermilab in Batavia Illinois. If built at this location the tunnels would be located in the Galena Platteville shale at a depth of 100 or more meters below the surface. Studies using hydro static water levels and seismometers have been conducted in the MINOS hall and the LaFrange Mine in North Aurora Illinois to determine the level of ground motion. Both these locations are in the Galena Platteville shale and indicate the typical ground motion to be expected for the ILC. The data contains both natural and cultural noise. Coefficients for the ALT law are determined. Seismic measurements at the surface and 100 meters below the surface are presented.

  12. Light-front nuclear shell-model

    SciTech Connect (OSTI)

    Johnson, M.B.

    1990-01-01T23:59:59.000Z

    I examine the effects of nuclear structure on high-energy, high-momentum transfer processes, specifically the EMC effect. For pedagogical reasons, a fictitious but simple two-body system consisting of two equal-mass particles interacting in a harmonic oscillator potential has been chosen. For this toy nucleus, I utilize a widely-used link between instant-form and light-front dynamics, formulating nuclear structure and deep-inelastic scattering consistently in the laboratory system. Binding effects are compared within conventional instant-form and light-front dynamical frameworks, with appreciable differences being found in the two cases. 20 refs.

  13. A model for international border management systems.

    SciTech Connect (OSTI)

    Duggan, Ruth Ann

    2008-09-01T23:59:59.000Z

    To effectively manage the security or control of its borders, a country must understand its border management activities as a system. Using its systems engineering and security foundations as a Department of Energy National Security Laboratory, Sandia National Laboratories has developed such an approach to modeling and analyzing border management systems. This paper describes the basic model and its elements developed under Laboratory Directed Research and Development project 08-684.

  14. Reactor Vessel and Reactor Vessel Internals Segmentation at Zion Nuclear Power Station - 13230

    SciTech Connect (OSTI)

    Cooke, Conrad; Spann, Holger [Siempelkamp Nuclear Services: 5229 Sunset Blvd., (Suite M), West Columbia, SC, 29169 (United States)] [Siempelkamp Nuclear Services: 5229 Sunset Blvd., (Suite M), West Columbia, SC, 29169 (United States)

    2013-07-01T23:59:59.000Z

    Zion Nuclear Power Station (ZNPS) is a dual-unit Pressurized Water Reactor (PWR) nuclear power plant located on the Lake Michigan shoreline, in the city of Zion, Illinois approximately 64 km (40 miles) north of Chicago, Illinois and 67 km (42 miles) south of Milwaukee, Wisconsin. Each PWR is of the Westinghouse design and had a generation capacity of 1040 MW. Exelon Corporation operated both reactors with the first unit starting production of power in 1973 and the second unit coming on line in 1974. The operation of both reactors ceased in 1996/1997. In 2010 the Nuclear Regulatory Commission approved the transfer of Exelon Corporation's license to ZionSolutions, the Long Term Stewardship subsidiary of EnergySolutions responsible for the decommissioning of ZNPS. In October 2010, ZionSolutions awarded Siempelkamp Nuclear Services, Inc. (SNS) the contract to plan, segment, remove, and package both reactor vessels and their respective internals. This presentation discusses the tools employed by SNS to remove and segment the Reactor Vessel Internals (RVI) and Reactor Vessels (RV) and conveys the recent progress. SNS's mechanical segmentation tooling includes the C-HORCE (Circumferential Hydraulically Operated Cutting Equipment), BMT (Bolt Milling Tool), FaST (Former Attachment Severing Tool) and the VRS (Volume Reduction Station). Thermal segmentation of the reactor vessels will be accomplished using an Oxygen- Propane cutting system. The tools for internals segmentation were designed by SNS using their experience from other successful reactor and large component decommissioning and demolition (D and D) projects in the US. All of the designs allow for the mechanical segmentation of the internals remotely in the water-filled reactor cavities. The C-HORCE is designed to saw seven circumferential cuts through the Core Barrel and Thermal Shield walls with individual thicknesses up to 100 mm (4 inches). The BMT is designed to remove the bolts that fasten the Baffle Plates to the Baffle Former Plates. The FaST is designed to remove the Baffle Former Plates from the Core Barrel. The VRS further volume reduces segmented components using multiple configurations of the 38i and horizontal reciprocating saws. After the successful removal and volume reduction of the Internals, the RV will be segmented using a 'First in the US' thermal cutting process through a co-operative effort with Siempelkamp NIS Ingenieurgesellschaft mbH using their experience at the Stade NPP and Karlsruhe in Germany. SNS mobilized in the fall of 2011 to commence execution of the project in order to complete the RVI segmentation, removal and packaging activities for the first unit (Unit 2) by end of the 2012/beginning 2013 and then mobilize to the second unit, Unit 1. Parallel to the completion of the segmentation of the reactor vessel internals at Unit 1, SNS will segment the Unit 2 pressure vessel and at completion move to Unit 1. (authors)

  15. Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities. Outcomes of the International Conference, 11-15 December 2006, Athens, Greece

    SciTech Connect (OSTI)

    Batandjieva, B.; Laraia, M. [International Atomic Energy Agency, Vienna (Austria)

    2008-01-15T23:59:59.000Z

    Full text of publication follows: decommissioning activities are increasing worldwide covering wide range of facilities - from nuclear power plant, through fuel cycle facilities to small laboratories. The importance of these activities is growing with the recognition of the need for ensuring safe termination of practices and reuse of sites for various purposes, including the development of new nuclear facilities. Decommissioning has been undertaken for more than forty years and significant knowledge has been accumulated and lessons have been learned. However the number of countries encountering decommissioning for the first time is increasing with the end of the lifetime of the facilities around the world, in particular in countries with small nuclear programmes (e.g. one research reactor) and limited human and financial resources. In order to facilitate the exchange of lessons learned and good practices between all Member States and to facilitate and improve safety of the planned, ongoing and future decommissioning projects, the IAEA in cooperation with the Nuclear Energy Agency to OECD, European Commission and World Nuclear Association organised the international conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities, held in Athens, Greece. The conference also highlighted areas where future cooperation at national and international level is required in order to improve decommissioning planning and safety during decommissioning and to facilitate decommissioning by selecting appropriate strategies and technologies for decontamination, dismantling and management of waste. These and other aspects discussed at the conference are presented in this paper, together with the planned IAEA measures for amendment and implementation of the International Action Plan on Decommissioning of Nuclear Facilities and its future programme on decommissioning.

  16. A nuclear data acquisition system flow control model

    SciTech Connect (OSTI)

    Hack, S.N.

    1988-02-01T23:59:59.000Z

    A general Petri Net representation of a nuclear data acquisition system model is presented. This model provides for the unique requirements of a nuclear data acquisition system including the capabilities of concurrently acquiring asynchronous and synchronous data, of providing multiple priority levels of flow control arbitration, and of permitting multiple input sources to reside at the same priority without the problem of channel lockout caused by a high rate data source. Finally, a previously implemented gamma camera/physiological signal data acquisition system is described using the models presented.

  17. Nuclear Mass Datasets and Models at nuclearmasses.org

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    This online repository for nuclear mass information allows nuclear researchers to upload their own mass values, store then, share them with colleagues, and, in turn, visualize and analyze the work of others. The Resources link provides access to published information or tools on other websites. The Contributions page is where users will find software, documents, experimental mass data sets, and theoretical mass models that have been uploaded for sharing with the scientific community.

  18. TAMCN: a tool for aggregate modeling of civil nuclear materials

    E-Print Network [OSTI]

    Watson, Aaron Michael

    2002-01-01T23:59:59.000Z

    substantial quantity of material to the amount of civil separated plutonium present today, so we thought it wise to begin here. We have developed a model of the nuclear fuel cycle in Western Europe and Japan using STELLA®. Our model uses the simple "stock...

  19. International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

    SciTech Connect (OSTI)

    Not Available

    1984-06-01T23:59:59.000Z

    This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held October 17 through November 4, 1983, at Santa Fe and Los Alamos, New Mexico and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a State system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1983 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, the Battelle Pacific Northwest Laboratory, Westinghouse Fast Flux Test Facility Visitor Center, and Washington Public Power System nuclear reactor facilities in Richland, Washington. Individual presentations were indexed for inclusion in the Energy Data Base.

  20. 1993 International conference on nuclear waste management and environmental remediation, Prague, Czech Republic, September 5--11, 1993. Combined foreign trip report

    SciTech Connect (OSTI)

    Slate, S.C. [comp.; Allen, R.E. [ed.

    1993-12-01T23:59:59.000Z

    The purpose of the trip was to attend the 1993 International Conference on Nuclear Waste Management and Environmental Remediation. The principal objective of this conference was to facilitate a truly international exchange of information on the management of nuclear wastes as well as contaminated facilities and sites emanating from nuclear operations. The conference was sponsored by the American Society of Mechanical Engineers, the Czech and Slovak Mechanical Engineering Societies, and the Czech and Slovak Nuclear Societies in cooperation with the Commission of the European Communities, the International Atomic Energy Agency, and the OECD Nuclear Agency. The conference was cosponsored by the American Nuclear Society, the Atomic Energy Society of Japan, the Canadian Nuclear Society, the (former USSR) Nuclear Society, and the Japan Society of Mechanical Engineers. This was the fourth in a series of biennial conferences, which started in Hong Kong, in 1987. This report summarizes shared aspects of the trip; however, each traveler`s observations and recommendations are reported separately.

  1. Comparison of Different Internal Dosimetry Systems for Selected Radionuclides Important to Nuclear Power Production

    SciTech Connect (OSTI)

    Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL; Manger, Ryan P [ORNL

    2013-08-01T23:59:59.000Z

    This report compares three different radiation dosimetry systems currently applied by various U.S. Federal agencies and dose estimates based on these three dosimetry systems for a set of radionuclides often identified in power reactor effluents. These dosimetry systems were developed and applied by the International Commission on Radiological Protection at different times over the past six decades. Two primary modes of intake of radionuclides are addressed: ingestion in drinking water and inhalation. Estimated doses to individual organs and to the whole body based on each dosimetry system are compared for each of four age groups: infant, child, teenager, and adult. Substantial differences between dosimetry systems in estimated dose per unit intake are found for some individual radionuclides, but differences in estimated dose per unit intake generally are modest for mixtures of radionuclides typically found in nuclear power plant effluents.

  2. Production of small uranium dioxide microspheres for cermet nuclear fuel using the internal gelation process

    SciTech Connect (OSTI)

    Collins, Robert T [ORNL] [ORNL; Collins, Jack Lee [ORNL] [ORNL; Hunt, Rodney Dale [ORNL] [ORNL; Ladd-Lively, Jennifer L [ORNL] [ORNL; Patton, Kaara K [ORNL] [ORNL; Hickman, Robert [NASA Marshall Space Flight Center, Huntsville, AL] [NASA Marshall Space Flight Center, Huntsville, AL

    2014-01-01T23:59:59.000Z

    The U.S. National Aeronautics and Space Administration (NASA) is developing a uranium dioxide (UO2)/tungsten cermet fuel for potential use as the nuclear cryogenic propulsion stage (NCPS). The first generation NCPS is expected to be made from dense UO2 microspheres with diameters between 75 and 150 m. Previously, the internal gelation process and a hood-scale apparatus with a vibrating nozzle were used to form gel spheres, which became UO2 kernels with diameters between 350 and 850 m. For the NASA spheres, the vibrating nozzle was replaced with a custom designed, two-fluid nozzle to produce gel spheres in the desired smaller size range. This paper describes the operational methodology used to make 3 kg of uranium oxide microspheres.

  3. 288 Int. J. Nuclear Energy Science and Technology, Vol. 7, No. 4, 2013 Multi-physics modelling of nuclear reactors

    E-Print Network [OSTI]

    Demazière, Christophe

    of nuclear reactors: current practices in a nutshell Christophe Demazière Department of Applied Physics of nuclear reactors are based on the use of different solvers for resolving the different physical fields and the corresponding approximations. Keywords: nuclear reactors; multi-physics; multi-scale; modelling; deterministic

  4. Journal of Nuclear Materials, Volumes 367-370, 2007, 1586-1589 Designing Optimised Experiments for the International Fusion

    E-Print Network [OSTI]

    Cambridge, University of

    Journal of Nuclear Materials, Volumes 367-370, 2007, 1586-1589 Designing Optimised Experiments for the International Fusion Materials Irradiation Facility R. Kemp1 G.A. Cottrell2 and H.K.D.H. Bhadesia1 1 Department EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, Oxon., OX14 3DB, UK Abstract

  5. International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

    SciTech Connect (OSTI)

    Not Available

    1986-06-01T23:59:59.000Z

    This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held June 3 through June 21, 1985, at Santa Fe and Los Alamos, New Mexico, and San Clemente, California. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the Course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1985 course was placed on safeguards methods used at item-control facilities, particularly nuclear power generating stations and test reactors. An introduction to safeguards methods used at bulk handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants, was also included. The course was conducted by the University of California's Los Alamos National Laboratory and the Southern California Edison Company. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the San Onofre Nuclear Generating Station, San Clemente, California.

  6. Multiphase transport model for relativistic nuclear collisions 

    E-Print Network [OSTI]

    Zhang, B.; Ko, Che Ming; Li, Ba; Lin, ZW.

    2000-01-01T23:59:59.000Z

    To study heavy ion collisions at energies available from the Relativistic Heavy Ion Collider (RHIC), we have developed a multiphase transport model that includes both initial partonic and final hadronic interactions. Specifically, the Zhang's parton...

  7. Multiphase transport model for relativistic nuclear collisions

    E-Print Network [OSTI]

    Zhang, B.; Ko, Che Ming; Li, Ba; Lin, ZW.

    2000-01-01T23:59:59.000Z

    To study heavy ion collisions at energies available from the Relativistic Heavy Ion Collider (RHIC), we have developed a multiphase transport model that includes both initial partonic and final hadronic interactions. Specifically, the Zhang's parton...

  8. The Japan Times Printer Friendly Articles France has won the competition to host the International Thermonuclear Experimental Reactor (ITER), the world's first nuclear-

    E-Print Network [OSTI]

    the International Thermonuclear Experimental Reactor (ITER), the world's first nuclear- fusion reactor. Japan fought wins by withdrawing ITER bid Thermonuclear fusion utilizes the same process that powers the sun -- nuclear-fusion reactions -- to produce energy. Scientists at the ITER plant will create nuclear-fusion

  9. Report of a workshop on nuclear forces and nonproliferation Woodrow Wilson international center for scholars, Washington, DC October 28, 2010

    SciTech Connect (OSTI)

    Pilat, Joseph F [Los Alamos National Laboratory

    2010-12-08T23:59:59.000Z

    A workshop sponsored by the Los Alamos National Laboratory in cooperation with the Woodrow Wilson International Center for Scholars was held at the Wilson Center in Washington, DC, on October 28, 2010. The workshop addressed evolving nuclear forces and their impacts on nonproliferation in the context of the new strategic environment, the Obama Administration's Nuclear Posture Review and the 2010 NPT Review Conference. The discussions reflected the importance of the NPR for defining the role of US nuclear forces in dealing with 21st century threats and providing guidance for National Nuclear Security Administration (NNSA) and Department of Defense (DoD) programs and, for many but not all participants, highlighted its role in the successful outcome of the NPT RevCon. There was widespread support for the NPR and its role in developing the foundations for a sustainable nuclear-weapon program that addresses nuclear weapons, infrastructure and expertise in the broader nonproliferation, disarmament and international security contexts. However, some participants raised concerns about its implementation and its long-term effectiveness and sustainability.

  10. LIMITED POWER BURSTS IN DISTRIBUTED MODELS OF NUCLEAR REACTORS

    E-Print Network [OSTI]

    Bazhenov, Maxim

    LIMITED POWER BURSTS IN DISTRIBUTED MODELS OF NUCLEAR REACTORS M. V. Bazhenov and E. F. Sabaev UDC employed for analyzing reactor dynamics. Equations of this type are used for analyzing the stability of the reactor power, etc. Among these problems the question of the boundedness of reactor power bursts

  11. Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational

    E-Print Network [OSTI]

    Nagurney, Anna

    Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach Anna Chain Challenges The Medical Nuclear Supply Chain Network Design Model The Computational Approach Medical Nuclear Supply Chain Design #12;This presentation is based on the paper, "Medical Nuclear Supply

  12. The Daya Bay Nuclear Plant Project in the Light of International Environmental Law

    E-Print Network [OSTI]

    Mushkat, Roda

    1990-01-01T23:59:59.000Z

    result from locating a nuclear plant so close to the Hongat 1292 (1975). THE DA YA BAY NUCLEAR PLANT PROJECT national1986) (H.K. ). THE DA YA BAY NUCLEAR PLANT PROJECT IV. THE "

  13. Proton-neutron pairing correlations in the nuclear shell model

    E-Print Network [OSTI]

    Lei Yang; S. Pittel; B. Thakur; N. Sandulescu; A. Poves; Yu-Min Zhao

    2010-06-16T23:59:59.000Z

    A shell-model study of proton-neutron pairing in f - p shell nuclei using a parametrized hamiltonian that includes deformation and spin-orbit effects as well as isoscalar and isovector pairing is reported. By working in a shell-model framework we are able to assess the role of the various modes of proton-neutron pairing in the presence of nuclear deformation without violating symmetries. Results are presented for $^{44}$Ti, $^{46}$Ti and $^{48}$Cr.

  14. An international initiative on long-term behavior of high-level nuclear waste glass

    SciTech Connect (OSTI)

    Gin, Stephane [CEA Marcoule DTCD SECM LCLT, Bagnols/Ceze (France); Abdelouas, Abdessalam [SUBATECH, Nantes (France); Criscenti, Louise J. [Sandia National Laboratories, Albuquerque, NM (United States); Ebert, W. L. [Argonne National Laboratory (ANL), Argonne, IL (United States); Ferrand, Karine [SCK·CEN, Mol (Belgium); Geisler, Thorsten [Rheinische Friedrich-Wilhelms-Univ., Bonn (Germany); Harrison, Mike T. [National Nuclear Laboratory, Sellafield, Cumbria (United Kingdom); Inagaki, Yaohiro [Kyushu Univ. (Japan). Dept. Appl. Quantum Physics and Nuclear Engineering; Mitsui, Seiichiro [Japan Atomic Energy Agency, Ibaraki (Japan); Mueller, Karl T. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States). Environmental and Molecular Science Lab.; Marra, James C. [Savannah River National Laboratory, Aiken, SC (United States); Pantano, Carlo G. [Penn State Univ., State College, PA (United States); Pierce, Eric M. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Ryan, Joseph V. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Schofield, James M. [AMEC, Harwell Oxford (United Kingdom); Steefel, Carl I. [Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States). Earth Sciences Div.; Vienna, John D. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

    2013-06-01T23:59:59.000Z

    Nations producing borosilicate glass as an immobilization material for radioactive wastes resulting from spent nuclear fuel reprocessing have reinforced scientific collaboration to obtain consensus on mechanisms controlling the long-term dissolution rate of glass. This goal is deemed to be crucial for the development of reliable performance assessment models for geological disposal. The collaborating laboratories all conduct fundamental and/or applied research with modern materials science techniques. The paper briefly reviews the radioactive waste vitrification programmes of the six participant nations and summarizes the state-of-the-art of glass corrosion science, emphasizing common scientific needs and justifications for on-going initiatives.

  15. INTEGRATION OF FACILITY MODELING CAPABILITIES FOR NUCLEAR NONPROLIFERATION ANALYSIS

    SciTech Connect (OSTI)

    Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

    2011-07-18T23:59:59.000Z

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  16. Nuclear Systems Modeling, Simulation & Validation | ORNL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for Renewable Energy:Nanowire3627 Federal Register /76SafeguardsSystems Modeling and

  17. Scalar dark matter models with significant internal bremsstrahlung

    SciTech Connect (OSTI)

    Giacchino, Federica; Tytgat, Michel H.G. [Service de Physique Théorique, Université Libre de Bruxelles, Boulevard du Triomphe, CP225, 1050 Brussels (Belgium); Lopez-Honorez, Laura, E-mail: federica.giacchino@ulb.ac.be, E-mail: llopezho@vub.ac.be, E-mail: mtytgat@ulb.ac.be [Theoretische Natuurkunde, Vrije Universiteit Brussel and The International Solvay Institutes, Pleinlaan 2, B-1050 Brussels (Belgium)

    2013-10-01T23:59:59.000Z

    There has been interest recently on particle physics models that may give rise to sharp gamma ray spectral features from dark matter annihilation. Because dark matter is supposed to be electrically neutral, it is challenging to build weakly interacting massive particle models that may accommodate both a large cross section into gamma rays at, say, the Galactic center, and the right dark matter abundance. In this work, we consider the gamma ray signatures of a class of scalar dark matter models that interact with Standard Model dominantly through heavy vector-like fermions (the vector-like portal). We focus on a real scalar singlet S annihilating into lepton-antilepton pairs. Because this two-body final-state annihilation channel is d-wave suppressed in the chiral limit, ?{sub ff-bar}v?v{sup 4}, we show that virtual internal bremsstrahlung emission of a gamma ray gives a large correction, both today and at the time of freeze-out. For the sake of comparison, we confront this scenario to the familiar case of a Majorana singlet annihilating into light lepton-antilepton pairs, and show that the virtual internal bremsstrahlung signal may be enhanced by a factor of (up to) two orders of magnitude. We discuss the scope and possible generalizations of the model.

  18. Modeling and Control of Multi-Contact Centers of Pressure and Internal Forces in Humanoid Robots

    E-Print Network [OSTI]

    Sentis, Luis

    Modeling and Control of Multi-Contact Centers of Pressure and Internal Forces in Humanoid Robots loops and exploit the virtual linkage model to develop a controller that guides internal force behavior on modeling multi- grasp behaviors and the associated internal forces acting between manipulators [14]. Using

  19. Nuclear shell-model code for massive parallel computation, "KSHELL"

    E-Print Network [OSTI]

    Noritaka Shimizu

    2013-10-21T23:59:59.000Z

    A new code for nuclear shell-model calculations, "KSHELL", is developed. It aims at carrying out both massively parallel computation and single-node computation in the same manner. We solve the Schr\\"{o}dinger's equation in the $M$-scheme shell-model model space, utilizing Thick-Restart Lanczos method. During the Lanczos iteration, the whole Hamiltonian matrix elements are generated "on-the-fly" in every matrix-vector multiplication. The vectors of the Lanczos method are distributed and stored on memory of each parallel node. We report that the newly developed code has high parallel efficiency on FX10 supercomputer and a PC with multi-cores.

  20. Nuclear EMC effect in non-extensive statistical model

    SciTech Connect (OSTI)

    Trevisan, Luis A. [Departamento de Matematica e Estatistica, Universidade Estadual de Ponta Grossa, 84010-790, Ponta Grossa, PR (Brazil); Mirez, Carlos [ICET, Universidade Federal dos Vales do Jequitinhonha e Mucuri - UFVJM, Campus do Mucuri, Rua do Cruzeiro 01, Jardim Sao Paulo, 39803-371, Teofilo Otoni, MG (Brazil)

    2013-05-06T23:59:59.000Z

    In the present work, we attempt to describe the nuclear EMC effect by using the proton structure functions obtained from the non-extensive statistical quark model. We record that such model has three fundamental variables, the temperature T, the radius, and the Tsallis parameter q. By combining different small changes, a good agreement with the experimental data may be obtained. Another interesting point of the model is to allow phenomenological interpretation, for instance, with q constant and changing the radius and the temperature or changing the radius and q and keeping the temperature.

  1. Annual report of the international nuclear research initiative OSMOSE project (FY05).

    SciTech Connect (OSTI)

    Klann, R. T.; Hudelot, J. P.; Perret, G.; Drin, N.; Nuclear Engineering Division; Commissariat a l'Energie Atomique

    2007-10-03T23:59:59.000Z

    The goal of the OSMOSE program is to measure the reactivity effect of minor actinides in known neutron spectra of interest to the Generation-IV reactor program and other programs and to create a database of these results for use as an international benchmark for the minor actinides. The results are then compared to calculational models to verify and validate integral absorption cross-sections for the minor actinides. The OSMOSE program includes all aspects of the experimental program -- including the fabrication of fuel pellets and samples, the oscillation of the samples in the MINERVE reactor for the measurement of the reactivity effect, reactor physics modeling of the MINERVE reactor, and the data analysis and interpretation of the experimental results.

  2. Annual report of the international nuclear energy research initiative OSMOSE project (FY06).

    SciTech Connect (OSTI)

    Klann, R. T.; Hudelot, J. P.; Drin, N.; Zhong, Z.; Nuclear Engineering Division; Commissariat a l Energie Atomique

    2007-08-29T23:59:59.000Z

    The goal of the OSMOSE program is to measure the reactivity effect of minor actinides in known neutron spectra of interest to the Generation-IV reactor program and other programs and to create a database of these results for use as an international benchmark for the minor actinides. The results are then compared to calculation models to verify and validate integral absorption cross-sections for the minor actinides. The OSMOSE program includes all aspects of the experimental program--including the fabrication of fuel pellets and samples, the oscillation of the samples in the MINERVE reactor for the measurement of the reactivity effect, reactor physics modeling of the MINERVE reactor, and the data analysis and interpretation of the experimental results.

  3. Sixth American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies NPIC&HMIT 2009, Knoxville, Tennessee, April 5-9, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL

    E-Print Network [OSTI]

    Heljanko, Keijo

    Sixth American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, automation 1 INTRODUCTION In nuclear power plants (NPPs), novel digitalized I&C systems enable complicated, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009) VERIFICATION OF SAFETY LOGIC DESIGNS

  4. ITER: The International Thermonuclear Experimental Reactor and the Nuclear Weapons Proliferation

    E-Print Network [OSTI]

    André Gsponer; Jean-pierre Hurni

    2004-01-01T23:59:59.000Z

    militarytechnical reasons and implications of the very probable siting of ITER (the International Thermonuclear

  5. Modeling and Simulation of Nuclear Medicine Patient Service Management in DEVS

    E-Print Network [OSTI]

    Ntaimo, Lewis

    -specialty of radiology, uses relatively new technology to diagnose and treat patients. Procedures (tests) in nuclear in nuclear medicine, which uses new technology to treat and diagnose patients. Nuclear medicine proceduresModeling and Simulation of Nuclear Medicine Patient Service Management in DEVS Eduardo P

  6. Instability of asymmetric nuclear matter in the extended Zimanyi-Moszkowski model

    E-Print Network [OSTI]

    and the critical phenomena in nuclear matter. The nuclear multifragmentation is considered as the spinodal decom the empirical value of the critical temperature [13] for nuclear matter. Recently, the author has developedInstability of asymmetric nuclear matter in the extended Zimanyi-Moszkowski model K. Miyazaki

  7. Ground state energy fluctuations in the Nuclear Shell Model

    E-Print Network [OSTI]

    Victor Velazquez; Jorge G. Hirsch; Alejandro Frank; Jose Barea; Andres P. Zuker

    2005-03-29T23:59:59.000Z

    Statistical fluctuations of the nuclear ground state energies are estimated using shell model calculations in which particles in the valence shells interact through well defined forces, and are coupled to an upper shell governed by random 2-body interactions. Induced ground-state energy fluctuations are found to be one order of magnitude smaller than those previously associated with chaotic components, in close agreement with independent perturbative estimates based on the spreading widths of excited states.

  8. 20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.

    SciTech Connect (OSTI)

    Ramirez, Amanda Ann

    2008-09-01T23:59:59.000Z

    The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.

  9. Development of a Preliminary Decommissioning Plan Following the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations - 13361

    SciTech Connect (OSTI)

    Moshonas Cole, Katherine; Dinner, Julia; Grey, Mike [Candesco - A Division of Kinectrics Inc, 26 Wellington E 3rd floor, Toronto, Ontario, M5E 1S2 (Canada)] [Candesco - A Division of Kinectrics Inc, 26 Wellington E 3rd floor, Toronto, Ontario, M5E 1S2 (Canada); Daniska, Vladimir [DECOM a.s., Sibirska 1, 917 01 Trnava (Slovakia)] [DECOM a.s., Sibirska 1, 917 01 Trnava (Slovakia)

    2013-07-01T23:59:59.000Z

    The International Structure for Decommissioning Costing (ISDC) of Nuclear Installations, published by OECD/NEA, IAEA and EC is intended to provide a uniform list of cost items for decommissioning projects and provides a standard format that permits international cost estimates to be compared. Candesco and DECOM have used the ISDC format along with two costing codes, OMEGA and ISDCEX, developed from the ISDC by DECOM, in three projects: the development of a preliminary decommissioning plan for a multi-unit CANDU nuclear power station, updating the preliminary decommissioning cost estimates for a prototype CANDU nuclear power station and benchmarking the cost estimates for CANDU against the cost estimates for other reactor types. It was found that the ISDC format provides a well defined and transparent basis for decommissioning planning and cost estimating that assists in identifying gaps and weaknesses and facilitates the benchmarking against international experience. The use of the ISDC can also help build stakeholder confidence in the reliability of the plans and estimates and the adequacy of decommissioning funding. (authors)

  10. On selection and operation of an international interim storage facility for spent nuclear fuel

    E-Print Network [OSTI]

    Burns, Joe, 1966-

    2004-01-01T23:59:59.000Z

    Disposal of post-irradiation fuel from nuclear reactors has been an issue for the nuclear industry for many years. Most countries currently have no long-term disposal strategy in place. Therefore, the concept of an ...

  11. Nuclear Hybrid Energy System Modeling: RELAP5 Dynamic Coupling Capabilities

    SciTech Connect (OSTI)

    Piyush Sabharwall; Nolan Anderson; Haihua Zhao; Shannon Bragg-Sitton; George Mesina

    2012-09-01T23:59:59.000Z

    The nuclear hybrid energy systems (NHES) research team is currently developing a dynamic simulation of an integrated hybrid energy system. A detailed simulation of proposed NHES architectures will allow initial computational demonstration of a tightly coupled NHES to identify key reactor subsystem requirements, identify candidate reactor technologies for a hybrid system, and identify key challenges to operation of the coupled system. This work will provide a baseline for later coupling of design-specific reactor models through industry collaboration. The modeling capability addressed in this report focuses on the reactor subsystem simulation.

  12. and INTERNATIONAL ATOMIC ENERGY AGENCYIOP PUBLISHING NUCLEAR FUSION Nucl. Fusion 48 (2008) 024016 (13pp) doi:10.1088/0029-5515/48/2/024016

    E-Print Network [OSTI]

    Solna, Knut

    2008-01-01T23:59:59.000Z

    and INTERNATIONAL ATOMIC ENERGY AGENCYIOP PUBLISHING NUCLEAR FUSION Nucl. Fusion 48 (2008) 024016 Vinca, Belgrade, Serbia 2 National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Gifu

  13. Ties That Do Not Bind: Russia and the International Liberal Order

    E-Print Network [OSTI]

    Krickovic, Andrej

    2012-01-01T23:59:59.000Z

    effect on international relations. Nuclear weapons andeffect on international relations. Nuclear weapons and

  14. Nuclear mass systematics by complementing the Finite Range Droplet Model with neural networks

    E-Print Network [OSTI]

    S. Athanassopoulos; E. Mavrommatis; K. A. Gernoth; J. W. Clark

    2005-11-30T23:59:59.000Z

    A neural-network model is developed to reproduce the differences between experimental nuclear mass-excess values and the theoretical values given by the Finite Range Droplet Model. The results point to the existence of subtle regularities of nuclear structure not yet contained in the best microscopic/phenomenological models of atomic masses. Combining the FRDM and the neural-network model, we create a hybrid model with improved predictive performance on nuclear-mass systematics and related quantities.

  15. Japanese suppliers in transition from domestic nuclear reactor vendors to international suppliers

    SciTech Connect (OSTI)

    Forsberg, C.W.; Reich, W.J.; Rowan, W.J.

    1994-06-27T23:59:59.000Z

    Japan is emerging as a major leader and exporter of nuclear power technology. In the 1990s, Japan has the largest and strongest nuclear power supply industry worldwide as a result of the largest domestic nuclear power plant construction program. The Japanese nuclear power supply industry has moved from dependence on foreign technology to developing, design, building, and operating its own power plants. This report describes the Japanese nuclear power supply industry and examines one supplier--the Mitsubishi group--to develop an understanding of the supply industry and its relationship to the utilities, government, and other organizations.

  16. Nuclear Futures Analysis and Scenario Building

    SciTech Connect (OSTI)

    Arthur, E.D.; Beller, D.; Canavan, G.H.; Krakowski, R.A.; Peterson, P.; Wagner, R.L.

    1999-07-09T23:59:59.000Z

    This LDRD project created and used advanced analysis capabilities to postulate scenarios and identify issues, externalities, and technologies associated with future ''things nuclear''. ''Things nuclear'' include areas pertaining to nuclear weapons, nuclear materials, and nuclear energy, examined in the context of future domestic and international environments. Analysis tools development included adaptation and expansion of energy, environmental, and economics (E3) models to incorporate a robust description of the nuclear fuel cycle (both current and future technology pathways), creation of a beginning proliferation risk model (coupled to the (E3) model), and extension of traditional first strike stability models to conditions expected to exist in the future (smaller force sizes, multipolar engagement environments, inclusion of actual and latent nuclear weapons (capability)). Accomplishments include scenario development for regional and global nuclear energy, the creation of a beginning nuclear architecture designed to improve the proliferation resistance and environmental performance of the nuclear fuel cycle, and numerous results for future nuclear weapons scenarios.

  17. Use of MCNP for characterization of reactor vessel internals waste from decommissioned nuclear reactors

    SciTech Connect (OSTI)

    Love, E.F.; Pauley, K.A.; Reid, B.D.

    1995-09-01T23:59:59.000Z

    This study describes the use of the Monte Carlo Neutron-Photon (MCNP) code for determining activation levels of irradiated reactor vessel internals hardware. The purpose of the analysis is to produce data for the Department of Energy`s Greater-Than-Class C Low-Level Radioactive Waste Program. An MCNP model was developed to analyze the Yankee Rowe reactor facility. The model incorporates reactor geometry, material compositions, and operating history data acquired from Yankee Atomic Electric Company. In addition to the base activation analysis, parametric studies were performed to determine the sensitivity of activation to specific parameters. A component sampling plan was also developed to validate the model results, although the plan was not implemented. The calculations for the Yankee Rowe reactor predict that only the core baffle and the core support plates will be activated to levels above the Class C limits. The parametric calculations show, however, that the large uncertainties in the material compositions could cause errors in the estimates that could also increase the estimated activation level of the core barrel to above the Class C limits. Extrapolation of the results to other reactor facilities indicates that in addition to the baffle and support plates, core barrels may also be activated to above Class C limits; however the classification will depend on the specific operating conditions of the reactor and the specific material compositions of the metal, as well as the use of allowable concentration averaging practices in packaging and classifying the waste.

  18. Transformation between statistical ensembles in the modelling of nuclear fragmentation

    E-Print Network [OSTI]

    Chaudhuri, G; Mallik, S

    2013-01-01T23:59:59.000Z

    We explore the conditions under which the particle number conservation constraint deforms the predictions of fragmentation observables as calculated in the grand canonical ensemble. We derive an analytical formula allowing to extract canonical results from a grand canonical calculation and vice versa. This formula shows that exact canonical results can be recovered for observables varying linearly or quadratically with the number of particles, independent of the grand canonical particle number fluctuations. We explore the validity of such grand canonical extrapolation for different fragmentation observables in the framework of the analytical Grand Canonical or Canonical Thermodynamical Model [(G)CTM] of nuclear multifragmentation. It is found that corrections to the grand canonical expectations can be evaluated with high precision, provided the system does not experience a first order phase transition. In particular, because of the Coulomb quenching of the liquid-gas phase transition of nuclear matter, we fin...

  19. Effect of dust models on global nuclear winter. Master's thesis

    SciTech Connect (OSTI)

    Pontier, P.Q.

    1986-03-01T23:59:59.000Z

    A series of optical-depth calculations were accomplished to assess the effects of various existing dust and soot models on the transmission of incident sunlight. A change in the standard deviation of the particle-size distribution from two to four, assuming constant total density, resulted in a decrease in the visible optical depth by a factor of ten. A technique using a method of direct integration was developed for the calculation of the effective optical depth of nuclear-induced dust and soot clouds. Contributions from directly transmitted photons, first scattered photons using anisotropic cross sections, and all subsequently scattered photons were used to calculate the amount of light transmitted through the cloud. Absorption effects were also included. The results of this study were comparable to the results of several recent nuclear winter studies.

  20. Nuclear Level Densities for Modeling Nuclear Reactions: An Efficient Approach Using Statistical Spectroscopy

    SciTech Connect (OSTI)

    Calvin W. Johnson

    2005-08-10T23:59:59.000Z

    The general goal of the project is to develop and implement computer codes and input files to compute nuclear densities of state. Such densities are important input into calculations of statistical neutron capture, and are difficult to access experimentally. In particular, we will focus on calculating densities for nuclides in the mass range A {approx} 50-100. We use statistical spectroscopy, a moments method based upon a microscopic framework, the interacting shell model. Second year goals and milestones: Develop two or three competing interactions (based upon surface-delta, Gogny, and NN-scattering) suitable for application to nuclei up to A = 100. Begin calculations for nuclides with A = 50-70.

  1. Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling

    SciTech Connect (OSTI)

    Danon, Yaron; Nazarewicz, Witold; Talou, Patrick

    2013-02-18T23:59:59.000Z

    This project addresses three important gaps in existing evaluated nuclear data libraries that represent a significant hindrance against highly advanced modeling and simulation capabilities for the Advanced Fuel Cycle Initiative (AFCI). This project will: Develop advanced theoretical tools to compute prompt fission neutrons and gamma-ray characteristics well beyond average spectra and multiplicity, and produce new evaluated files of U and Pu isotopes, along with some minor actinides; Perform state-of-the-art fission cross-section modeling and calculations using global and microscopic model input parameters, leading to truly predictive fission cross-sections capabilities. Consistent calculations for a suite of Pu isotopes will be performed; Implement innovative data assimilation tools, which will reflect the nuclear data evaluation process much more accurately, and lead to a new generation of uncertainty quantification files. New covariance matrices will be obtained for Pu isotopes and compared to existing ones. The deployment of a fleet of safe and efficient advanced reactors that minimize radiotoxic waste and are proliferation-resistant is a clear and ambitious goal of AFCI. While in the past the design, construction and operation of a reactor were supported through empirical trials, this new phase in nuclear energy production is expected to rely heavily on advanced modeling and simulation capabilities. To be truly successful, a program for advanced simulations of innovative reactors will have to develop advanced multi-physics capabilities, to be run on massively parallel super- computers, and to incorporate adequate and precise underlying physics. And all these areas have to be developed simultaneously to achieve those ambitious goals. Of particular interest are reliable fission cross-section uncertainty estimates (including important correlations) and evaluations of prompt fission neutrons and gamma-ray spectra and uncertainties.

  2. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013) Sun Valley, Idaho, USA, May 5-9, 2013, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2013)

    E-Print Network [OSTI]

    Kelley, C. T. "Tim"

    International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013) Sun Valley, Idaho, USA, May 5-9, 2013, on CD-ROM, American Nuclear Society, La transport criticality problems. Traditional methods for computing this eigenvalue/eigenvector pair

  3. | International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 54 (2014) 043016 (8pp) doi:10.1088/0029-5515/54/4/043016

    E-Print Network [OSTI]

    Harilal, S. S.

    . Hassanein Center for Materials under Extreme Environment, School of Nuclear Engineering, Purdue University| International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 54 (2014) 043016 (8pp) doi:10 becomes well coupled to the melt motion. Under the plasma impact with high velocity of 5000 m s-1 , the W

  4. | International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 54 (2014) 033008 (8pp) doi:10.1088/0029-5515/54/3/033008

    E-Print Network [OSTI]

    Harilal, S. S.

    . Miloshevsky and A. Hassanein Center for Materials under Extreme Environment, School of Nuclear Engineering| International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 54 (2014) 033008 (8pp) doi:10 is observed on the melt surface in the absence of plasma impact. The magnetic field of 5 T that is parallel

  5. International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9) N9P0302 Kaohsiung, Taiwan, September 9-13, 2012

    E-Print Network [OSTI]

    Haviland, David

    The 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9 Kudinov Division of Nuclear Power Safety, Royal Institute of Technology (KTH), Roslagstullsbacken 21, SE proportional to terminal melt spread thickness. At certain thickness, the melt layer becomes non

  6. Nonextensive critical effects in relativistic nuclear mean field models

    E-Print Network [OSTI]

    J. Rozynek; G. Wilk

    2011-02-22T23:59:59.000Z

    We present a possible extension of the usual relativistic nuclear mean field models widely used to describe nuclear matter towards accounting for the influence of possible intrinsic fluctuations caused by the environment. Rather than individually identifying their particular causes we concentrate on the fact that such effects can be summarily incorporated in the changing of the statistical background used, from the usual (extensive) Boltzman-Gibbs one to the nonextensive taken in the form proposed by Tsallis with a dimensionless nonextensivity parameter $q$ responsible for the above mentioned effects (for $q \\rightarrow 1$ one recovers the usual BG case). We illustrate this proposition on the example of the QCD-based Nambu - Jona-Lasinio (NJL) model of a many-body field theory describing the behavior of strongly interacting matter presenting its nonextensive version. We check the sensitivity of the usual NJL model to a departure from the BG scenario expressed by the value of $| q - 1|$, in particular in the vicinity of critical points.

  7. Towards a detailed soot model for internal combustion engines

    SciTech Connect (OSTI)

    Mosbach, Sebastian; Celnik, Matthew S.; Raj, Abhijeet; Kraft, Markus [Department of Chemical Engineering and Biotechnology, University of Cambridge, Pembroke Street, Cambridge CB2 3RA (United Kingdom); Zhang, Hongzhi R. [Department of Chemical Engineering, University of Utah, 1495 East 100 South, Kennecott Research Building, Salt Lake City, UT 84112 (United States); Kubo, Shuichi [Frontier Research Center, Toyota Central R and D Labs., Inc., Nagakute, Aichi 480-1192 (Japan); Kim, Kyoung-Oh [Higashifuji Technical Center, Toyota Motor Corporation, Mishuku 1200, Susono, Shizuoka 480-1193 (Japan)

    2009-06-15T23:59:59.000Z

    In this work, we present a detailed model for the formation of soot in internal combustion engines describing not only bulk quantities such as soot mass, number density, volume fraction, and surface area but also the morphology and chemical composition of soot aggregates. The new model is based on the Stochastic Reactor Model (SRM) engine code, which uses detailed chemistry and takes into account convective heat transfer and turbulent mixing, and the soot formation is accounted for by SWEEP, a population balance solver based on a Monte Carlo method. In order to couple the gas-phase to the particulate phase, a detailed chemical kinetic mechanism describing the combustion of Primary Reference Fuels (PRFs) is extended to include small Polycyclic Aromatic Hydrocarbons (PAHs) such as pyrene, which function as soot precursor species for particle inception in the soot model. Apart from providing averaged quantities as functions of crank angle like soot mass, volume fraction, aggregate diameter, and the number of primary particles per aggregate for example, the integrated model also gives detailed information such as aggregate and primary particle size distribution functions. In addition, specifics about aggregate structure and composition, including C/H ratio and PAH ring count distributions, and images similar to those produced with Transmission Electron Microscopes (TEMs), can be obtained. The new model is applied to simulate an n-heptane fuelled Homogeneous Charge Compression Ignition (HCCI) engine which is operated at an equivalence ratio of 1.93. In-cylinder pressure and heat release predictions show satisfactory agreement with measurements. Furthermore, simulated aggregate size distributions as well as their time evolution are found to qualitatively agree with those obtained experimentally through snatch sampling. It is also observed both in the experiment as well as in the simulation that aggregates in the trapped residual gases play a vital role in the soot formation process. (author)

  8. ''Nuclear Winter'': A diagnosis of atmospheric general circulation model simulations

    SciTech Connect (OSTI)

    Covey, C.; Thompson, S.L.; Schneider, S.H.

    1985-06-20T23:59:59.000Z

    We investigate the adiabatic and diabatic thermal balance of an atmospheric general circulation model (GCM) under two conditions: the control case, representing today's atmosphere, and a ''nuclear winter'' scenario in which virtually all sunlight in northern hemisphere and mid-latitudes is absorbed in the upper troposphere by prescribed dense smoke clouds hypothesized to result from the burning of many cities in a nuclear war. We also examine the changes in moisture and cloudiness simulated by the model. Our object is to examine the reliability of existing simulations of the climatic response to assumed dense, widespread, high-altitude smoke and to identify improvements needed in model parameterizations. We find that in the smoke-perturbed case our model simulation of land surface temperature is particularly influenced (i.e., warmed) by parameterized diffusion of heat downward from the lower troposphere. In turn the lower troposphere over land is supplied with heat transported from the relatively warm oceans. Thermal balance in the perturbed atmosphere as a whole is dominated by intense solar heating of the upper troposphere smoke layer in mid-latitudes balanced by parameterized dry convection and large-scale dynamical heat transport. Clouds largely disappear in the mid to upper troposphere in smoke-affected regions as a consequence of a decrease in local relative humidity that results from temperature increases and, to a smaller extent, from a reduction of vertical moisture transport. The computation of substantial downward vertical heat diffusion into the lowest model layer is almost certainly an overestimate for the smoke-perturbed conditions of high vertical stability.

  9. Robust Linearization of RF Amplifiers Using NonLinear Internal Model Control Method

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Robust Linearization of RF Amplifiers Using NonLinear Internal Model Control Method Smail Bachir #1, the nonlinear Internal Model Control (IMC) method is introduced and applied to linearize high frequency Power to be controlled [8]. If the model is a perfect representation of the non linear system, the controller can

  10. Model-predicted distribution of wind-induced internal wave energy in the world's oceans

    E-Print Network [OSTI]

    Miami, University of

    Model-predicted distribution of wind-induced internal wave energy in the world's oceans Naoki 9 July 2008; published 30 September 2008. [1] The distribution of wind-induced internal wave energy-induced internal wave energy in the world's oceans, J. Geophys. Res., 113, C09034, doi:10.1029/2008JC004768. 1

  11. International energy outlook 1996

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This International Energy Outlook presents historical data from 1970 to 1993 and EIA`s projections of energy consumption and carbon emissions through 2015 for 6 country groups. Prospects for individual fuels are discussed. Summary tables of the IEO96 world energy consumption, oil production, and carbon emissions projections are provided in Appendix A. The reference case projections of total foreign energy consumption and of natural gas, coal, and renewable energy were prepared using EIA`s World Energy Projection System (WEPS) model. Reference case projections of foreign oil production and consumption were prepared using the International Energy Module of the National Energy Modeling System (NEMS). Nuclear consumption projections were derived from the International Nuclear Model, PC Version (PC-INM). Alternatively, nuclear capacity projections were developed using two methods: the lower reference case projections were based on analysts` knowledge of the nuclear programs in different countries; the upper reference case was generated by the World Integrated Nuclear Evaluation System (WINES)--a demand-driven model. In addition, the NEMS Coal Export Submodule (CES) was used to derive flows in international coal trade. As noted above, foreign projections of electricity demand are now projected as part of the WEPS. 64 figs., 62 tabs.

  12. INTERNATIONAL AGREEMENTS

    Office of Environmental Management (EM)

    generators, reactor pressure vessel and internals, cables, piping, pumps, valves) - optimization of nuclear power plant generation capacity (digital I&C upgrades, advanced...

  13. Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators; Summary Report of an IAEA Technical Meeting

    SciTech Connect (OSTI)

    Abriola, D.; Tuli, J.

    2009-03-23T23:59:59.000Z

    The IAEA Nuclear Data Section convened the 18th meeting of the International Network of Nuclear Structure and Decay Data Evaluators at the IAEA Headquarters, Vienna, 23 to 27 March 2009. This meeting was attended by 22 scientists from 14 Member States, plus IAEA staff, concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, recommendations/conclusions, data centre reports, and various proposals considered, modified and agreed by the participants are contained within this document. The International Network of Nuclear Structure and Decay Data (NSDD) Evaluators holds biennial meetings under the auspices of the IAEA, and consists of evaluation groups and data service centres in several countries. This network has the objective of providing up-to-date nuclear structure and decay data for all known nuclides by evaluating all existing experimental data. Data resulting from this international evaluation collaboration is included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets (NDS).

  14. Numerical methods for the simulation of a corrosion model in a nuclear waste deep repository $

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Numerical methods for the simulation of a corrosion model in a nuclear waste deep repository $ C of the French nuclear waste management agency ANDRA, investigations are conducted to optimize and finalize by the Nuclear Waste Management Agency ANDRA Corresponding author. Phone: +49 30 20372 560, Fax: +49 30 2044975

  15. Seismic modeling and analysis of a prototype heated nuclear waste storage tunnel, Yucca Mountain, Nevada

    E-Print Network [OSTI]

    Snieder, Roel

    Seismic modeling and analysis of a prototype heated nuclear waste storage tunnel, Yucca Mountain was heated to replicate the effects of long-term storage of decaying nuclear waste and to study the effects for the long- term storage of high-level nuclear waste from reactors and decom- missioned atomic weapons

  16. Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach

    E-Print Network [OSTI]

    Nagurney, Anna

    Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach Anna of medical nuclear supply chains. Our focus is on the molybdenum supply chain, which is the most commonly is of special relevance to healthcare given the medical nuclear product's widespread use as well as the aging

  17. Evolution of a Visual Impact Model to Evaluate Nuclear Plant Siting and Design Option1

    E-Print Network [OSTI]

    Standiford, Richard B.

    Evolution of a Visual Impact Model to Evaluate Nuclear Plant Siting and Design Option1 2/ Brian A and economic options for the analysis of nuclear plant siting possibilities (Burnham 1974; Jones, April 1975 of nuclear plant siting options for the AEC. BNWL's multi-disciplinary impact evaluation pro- cedure required

  18. ccsd00001474, Model-independent tracking of criticality signals in nuclear multifragmentation data

    E-Print Network [OSTI]

    ccsd­00001474, version 2 ­ 6 Sep 2004 Model-independent tracking of criticality signals in nuclear Physique Nucléaire, IN2P3-CNRS et Université F-69622 Villeurbanne, France. 8 Institute of Nuclear Physics, Pl-31342 Kraków, Poland. 9 National Institute for Physics and Nuclear Engineering, RO-76900 Bucharest

  19. Critical phenomena of nuclear matter in the extended Zimanyi-Moszkowski model

    E-Print Network [OSTI]

    Critical phenomena of nuclear matter in the extended Zimanyi-Moszkowski model K. Miyazaki Abstract in nuclear multifragmentation reactions and the critical temperature has been derived as TC = 20 3 MeV in Ref] to estimate the critical temperature for in...nite nuclear matter, that is, TC = 16:6 0:86 Me

  20. MODELING ATMOSPHERIC RELEASES OF TRITIUM FROM NUCLEAR INSTALLATIONS

    SciTech Connect (OSTI)

    Okula, K

    2007-01-17T23:59:59.000Z

    Tritium source term analysis and the subsequent dispersion and consequence analyses supporting the safety documentation of Department of Energy nuclear facilities are especially sensitive to the applied software analysis methodology, input data and user assumptions. Three sequential areas in tritium accident analysis are examined in this study to illustrate where the analyst should exercise caution. Included are: (1) the development of a tritium oxide source term; (2) use of a full tritium dispersion model based on site-specific information to determine an appropriate deposition scaling factor for use in more simplified, broader modeling, and (3) derivation of a special tritium compound (STC) dose conversion factor for consequence analysis, consistent with the nature of the originating source material. It is recommended that unless supporting, defensible evidence is available to the contrary, the tritium release analyses should assume tritium oxide as the species released (or chemically transformed under accident's environment). Important exceptions include STC situations and laboratory-scale releases of hydrogen gas. In the modeling of the environmental transport, a full phenomenology model suggests that a deposition velocity of 0.5 cm/s is an appropriate value for environmental features of the Savannah River Site. This value is bounding for certain situations but non-conservative compared to the full model in others. Care should be exercised in choosing other factors such as the exposure time and the resuspension factor.

  1. New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear...

    Energy Savers [EERE]

    States reassess seismic hazards. The Central and Eastern United States Seismic Source Characterization for Nuclear Facilities model and report is the culmination of a four-year...

  2. Overview of the International R&D Recycling Activities of the Nuclear Fuel Cycle

    SciTech Connect (OSTI)

    Patricia Paviet-Hartmann

    2012-10-01T23:59:59.000Z

    Nuclear power has demonstrated over the last 30 years its capacity to produce base-load electricity at a low, predictable and stable cost due to the very low economic dependence on the price of uranium. However the management of used nuclear fuel remains the “Achilles’ Heel” of this energy source since the storage of used nuclear fuel is increasing as evidenced by the following number with 2,000 tons of UNF produced each year by the 104 US nuclear reactor units which equates to a total of 62,000 spent fuel assemblies stored in dry cask and 88,000 stored in pools. Two options adopted by several countries will be presented. The first one adopted by Europe, Japan and Russia consists of recycling the used nuclear fuel after irradiation in a nuclear reactor. Ninety six percent of uranium and plutonium contained in the spent fuel could be reused to produce electricity and are worth recycling. The separation of uranium and plutonium from the wastes is realized through the industrial PUREX process so that they can be recycled for re-use in a nuclear reactor as a mixed oxide (MOX) fuel. The second option undertaken by Finland, Sweden and the United States implies the direct disposal of used nuclear fuel into a geologic formation. One has to remind that only 30% of the worldwide used nuclear fuel are currently recycled, the larger part being stored (90% in pool) waiting for scientific or political decisions. A third option is emerging with a closed fuel cycle which will improve the global sustainability of nuclear energy. This option will not only decrease the volume amount of nuclear waste but also the long-term radiotoxicity of the final waste, as well as improving the long-term safety and the heat-loading of the final repository. At the present time, numerous countries are focusing on the R&D recycling activities of the ultimate waste composed of fission products and minor actinides (americium and curium). Several new chemical extraction processes, such as TRUSPEAK, EXAM, or LUCA processes are pursued worldwide and their approaches will be highlighted.

  3. Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 1

    SciTech Connect (OSTI)

    none,

    1983-02-01T23:59:59.000Z

    Separate abstracts are included for each of the papers presented concerning current issues in nuclear power plant safety; national programs in nuclear power plant safety; radiological source terms; probabilistic risk assessment methods and techniques; non LOCA and small-break-LOCA transients; safety goals; pressurized thermal shocks; applications of reliability and risk methods to probabilistic risk assessment; human factors and man-machine interface; and data bases and special applications.

  4. THERMODYNAMIC MODEL FOR URANIUM DIOXIDE BASED NUCLEAR FUEL

    SciTech Connect (OSTI)

    Thompson, Dr. William T. [Royal Military College of Canada; Lewis, Dr. Brian J [Royal Military College of Canada; Corcoran, E. C. [Royal Military College of Canada; Kaye, Dr. Matthew H. [Royal Military College of Canada; White, S. J. [Royal Military College of Canada; Akbari, F. [Atomic Energy of Canada Limited, Chalk River Laboratories; Higgs, Jamie D. [Atomic Energy of Canada Limited, Point Lepreau; Thompson, D. M. [Praxair Inc.; Besmann, Theodore M [ORNL; Vogel, S. C. [Los Alamos National Laboratory (LANL)

    2007-01-01T23:59:59.000Z

    Many projects involving nuclear fuel rest on a quantitative understanding of the co-existing phases at various stages of burnup. Since the many fission products have considerably different abilities to chemically associate with oxygen, and the oxygen-to-metal molar ratio is slowly changing, the chemical potential of oxygen is a function of burnup. Concurrently, well-recognized small fractions of new phases such as inert gas, noble metals, zirconates, etc. also develop. To further complicate matters, the dominant UO2 fuel phase may be non-stoichiometric and most of the minor phases themselves have a variable composition dependent on temperature and possible contact with the coolant in the event of a sheathing breach. A thermodynamic fuel model to predict the phases in partially burned CANDU (CANada Deuterium Uranium) nuclear fuel containing many major fission products has been under development. The building blocks of the model are the standard Gibbs energies of formation of the many possible compounds expressed as a function of temperature. To these data are added mixing terms associated with the appearance of the component species in particular phases. In operational terms, the treatment rests on the ability to minimize the Gibbs energy in a multicomponent system, in our case using the algorithms developed by Eriksson. The model is capable of handling non-stoichiometry in the UO2 fluorite phase, dilute solution behaviour of significant solute oxides, noble metal inclusions, a second metal solid solution U(Pd-Rh-Ru)3, zirconate, molybdate, and uranate solutions as well as other minor solid phases, and volatile gaseous species.

  5. Leveraging U.S. nuclear weapons policy to advance U.S. nonproliferation goals : implications of major theories of international relations.

    SciTech Connect (OSTI)

    Walter, Andrew

    2009-06-01T23:59:59.000Z

    National policymakers are currently considering a dilemma of critical importance to the continued security of the United States: how can U.S. nuclear weapons policies be leveraged to benefit U.S. nuclear nonproliferation goals in the near-term, without sacrificing U.S. national security? In its role supporting U.S. nuclear weapons policy, Sandia National Laboratories has a responsibility to provide objective technical advice to support policy deliberations on this question. However, to best fulfill this duty Sandia must have a broader understanding of the context of the problem. To help develop this understanding, this paper analyzes the two predominant analytical perspectives of international relations theory to explore their prescriptions for how nuclear weapons and nonproliferation policies interact. As lenses with which to view and make sense of the world, theories of international relations must play a crucial role in framing the trade-offs at the intersection of the nuclear weapons and nonproliferation policy domains. An analysis of what these theories suggest as courses of action to leverage nuclear weapons policies to benefit nonproliferation goals is then offered, with particular emphasis on where the policy prescriptions resulting from the respective theories align to offer near-term policy changes with broad theoretical support. These policy prescriptions are then compared to the 2001 Nuclear Posture Review to understand what the theories indicate policymakers may have gotten right in their dealing with the nuclear dilemma, and where they may have gone wrong. Finally, a brief international relations research agenda is proposed to help address the dilemma between nuclear deterrence and nuclear nonproliferation policies, with particular emphasis on how such an agenda can best support the needs of the policy community and a potential 'all things nuclear' policy deliberation and decision-support framework.

  6. Development of nuclear models for higher energy calculations

    SciTech Connect (OSTI)

    Bozoian, M.; Siciliano, E.R.; Smith, R.D.

    1988-01-01T23:59:59.000Z

    Two nuclear models for higher energy calculations have been developed in the regions of high and low energy transfer, respectively. In the former, a relativistic hybrid-type preequilibrium model is compared with data ranging from 60 to 800 MeV. Also, the GNASH exciton preequilibrium-model code with higher energy improvements is compared with data at 200 and 318 MeV. In the region of low energy transfer, nucleon-nucleus scattering is predominately a direct reaction involving quasi-elastic collisions with one or more target nucleons. We discuss various aspects of quasi-elastic scattering which are important in understanding features of cross sections and spin observables. These include (1) contributions from multi-step processes; (2) damping of the continuum response from 2p-2h excitations; (3) the ''optimal'' choice of frame in which to evaluate the nucleon-nucleon amplitudes; and (4) the effect of optical and spin-orbit distortions, which are included in a model based on the RPA the DWIA and the eikonal approximation. 33 refs., 15 figs.

  7. VISION -- A Dynamic Model of the Nuclear Fuel Cycle

    SciTech Connect (OSTI)

    J. J. Jacobson; A. M. Yacout; S. J. Piet; D. E. Shropshire; G. E. Matthern

    2006-02-01T23:59:59.000Z

    The Advanced Fuel Cycle Initiative’s (AFCI) fundamental objective is to provide technology options that – if implemented – would enable long-term growth of nuclear power while improving sustainability and energy security. The AFCI organization structure consists of four areas; Systems Analysis, Fuels, Separations and Transmutations. The Systems Analysis Working Group is tasked with bridging the program technical areas and providing the models, tools, and analyses required to assess the feasibility of design and deploy¬ment options and inform key decision makers. An integral part of the Systems Analysis tool set is the development of a system level model that can be used to examine the implications of the different mixes of reactors, implications of fuel reprocessing, impact of deployment technologies, as well as potential “exit” or “off ramp” approaches to phase out technologies, waste management issues and long-term repository needs. The Verifiable Fuel Cycle Simulation Model (VISION) is a computer-based simulation model that allows performing dynamic simulations of fuel cycles to quantify infrastructure requirements and identify key trade-offs between alternatives. VISION is intended to serve as a broad systems analysis and study tool applicable to work conducted as part of the AFCI (including costs estimates) and Generation IV reactor development studies.

  8. Modelling international wind energy diffusion: Are the patterns of induced diffusion `S'

    E-Print Network [OSTI]

    Feigon, Brooke

    Modelling international wind energy diffusion: Are the patterns of induced diffusion `S' shaped datasets, the paper explores the patterns of international wind energy diffusion in OECD countries. The model employed in the paper predicted that wind energy, as a complex and expensive innovation, would

  9. A Planar Anode -Supported Solid Oxide Fuel Cell Model with Internal Reforming of Natural Gas

    E-Print Network [OSTI]

    Boyer, Edmond

    1 A Planar Anode - Supported Solid Oxide Fuel Cell Model with Internal Reforming of Natural Gas.brault@univ-orleans.fr Abstract Solid Oxide Fuel Cells (SOFCs) are of great interest due to their high energy efficiency, low, a mathematical model of a co - flow planar anode - supported solid oxide fuel cell with internal reforming

  10. ITER: The International Thermonuclear Experimental Reactor and the Nuclear Weapons Proliferation Implications of Thermonuclear-Fusion Energy Systems

    E-Print Network [OSTI]

    André Gsponer; Jean-pierre Hurni

    2004-01-01T23:59:59.000Z

    This paper contains two parts: (I) A list of “points ” highlighting the strategic-political and militarytechnical reasons and implications of the very probable siting of ITER (the International Thermonuclear Experimental Reactor) in Japan, which should be confirmed sometimes in early 2004. (II) A technical analysis of the nuclear weapons proliferation implications of inertial- and magnetic-confinement fusion systems substantiating the technical points highlighted in the first part, and showing that while full access to the physics of thermonuclear weapons is the main implication of ICF, full access to large-scale tritium technology is the main proliferation impact of MCF. The conclusion of the paper is that siting ITER in a country such as Japan, which already has a large separated-plutonium stockpile, and an ambitious laser-driven ICF program (comparable in size and quality to those of the United States or France) will considerably increase its latent (or virtual) nuclear weapons proliferation status, and foster further nuclear proliferation throughout the world. The safety and environmental problems related to the operation of largescale fusion facilities such as ITER (which contain massive amounts of hazardous and/or radioactive materials such as tritium, lithium, and beryllium, as well as neutron-activated structural materials) are not addressed in this paper.

  11. 3D CFD ELECTROCHEMICAL AND HEAT TRANSFER MODEL OF AN INTERNALLY MANIFOLDED SOLID OXIDE ELECTROLYSIS CELL

    SciTech Connect (OSTI)

    Grant L. Hawkes; James E. O'Brien; Greg Tao

    2011-11-01T23:59:59.000Z

    A three-dimensional computational fluid dynamics (CFD) electrochemical model has been created to model high-temperature electrolysis cell performance and steam electrolysis in an internally manifolded planar solid oxide electrolysis cell (SOEC) stack. This design is being evaluated at the Idaho National Laboratory for hydrogen production from nuclear power and process heat. Mass, momentum, energy, and species conservation and transport are provided via the core features of the commercial CFD code FLUENT. A solid-oxide fuel cell (SOFC) model adds the electrochemical reactions and loss mechanisms and computation of the electric field throughout the cell. The FLUENT SOFC user-defined subroutine was modified for this work to allow for operation in the SOEC mode. Model results provide detailed profiles of temperature, operating potential, steam-electrode gas composition, oxygen-electrode gas composition, current density and hydrogen production over a range of stack operating conditions. Single-cell and five-cell results will be presented. Flow distribution through both models is discussed. Flow enters from the bottom, distributes through the inlet plenum, flows across the cells, gathers in the outlet plenum and flows downward making an upside-down ''U'' shaped flow pattern. Flow and concentration variations exist downstream of the inlet holes. Predicted mean outlet hydrogen and steam concentrations vary linearly with current density, as expected. Effects of variations in operating temperature, gas flow rate, oxygen-electrode and steam-electrode current density, and contact resistance from the base case are presented. Contour plots of local electrolyte temperature, current density, and Nernst potential indicate the effects of heat transfer, reaction cooling/heating, and change in local gas composition. Results are discussed for using this design in the electrolysis mode. Discussion of thermal neutral voltage, enthalpy of reaction, hydrogen production, cell thermal efficiency, cell electrical efficiency, and Gibbs free energy are discussed and reported herein.

  12. Shell model nuclear matrix elements for competing mechanisms contributing to double beta decay

    SciTech Connect (OSTI)

    Horoi, Mihai [Department of Physics, Central Michigan University, Mount Pleasant, Michigan, 48859 (United States)

    2013-12-30T23:59:59.000Z

    Recent progress in the shell model approach to the nuclear matrix elements for the double beta decay process are presented. This includes nuclear matrix elements for competing mechanisms to neutrionless double beta decay, a comparison between closure and non-closure approximation for {sup 48}Ca, and an updated shell model analysis of nuclear matrix elements for the double beta decay of {sup 136}Xe.

  13. An evaluation of thermal modeling techniques utilized for nuclear fuel rods 

    E-Print Network [OSTI]

    Simmons, Jeffrey Warren

    1989-01-01T23:59:59.000Z

    AN EVALUATION OF THERMAL MODELING TECHNIQUES UTILIZED FOR NUCLEAR FUEL RODS A Thesis by JEFFREY WARREN SIMMONS Submitted to the Office of Graduate Studies of Texas Asr M University in partial fulfillment of the requirements for the degree... of MASTER OF SCIENCE August 1989 Major Subject: Nuclear Engineering AN EVALUATION OF THERMAL MODELING TECHNIQUES UTILIZED FOR NUCLEAR FUEL RODS A Thesis by ~Y WARREN SIMMONS Approved as to style and content by: K. L. Peddicord (Chair of Committee...

  14. Overview of the international R&D recycling activities of the nuclear fuel cycle

    SciTech Connect (OSTI)

    Patricia Paviet-Hartmann

    2012-12-01T23:59:59.000Z

    Nuclear power has demonstrated over the last thirty years its capacity to produce base-load electricity at a low, predictable and stable cost due to the very low economic dependence of the price of uranium. However the management of used nuclear fuel (UNF) remains the “Achilles’ heel of this energy source since the storage of UNF is increasing as evidenced by the following number with 2,000 to 2,300 of UNF produced each year by the 104 US nuclear reactor units which equates to a total of 62,000 UNF assemblies stored in dry cask storage and 88,000 stored in pools. Alarmingly, more than half of US commercial reactor sites have filled their pools to capacity and have had to add dry cask storage facilities. Two options adopted by several countries will be discussed. The first one adopted by Europe, Japan and Russia consists of recycling the used nuclear fuel after irradiation in a nuclear reactor. Ninety six percent of uranium and plutonium contained in the spent fuel could be reused to produce electricity and are worth recycling. The separation of uranium and plutonium from the wastes is realized through the industrial PUREX process so that they can be recycled for re-use in a nuclear reactor as a mixed oxide (MOX) fuel. The second option undertaken by Finland, Sweden and the United States implies the direct disposal of UNF into a geologic formation. One has to remind that only 30% of the worldwide UNF are currently recycled, the larger part being stored (90% in pool) waiting for scientific or political decisions. A third option is emerging with a closed fuel cycle which will improve the global sustainability of nuclear energy. This option will not only decrease the volume amount of nuclear waste but also the long-term radiotoxicity of the final waste, as well as improving the long-term safety and the heat-loading of the final repository. At the present time, numerous countries are focusing on the R&D recycling activities of the ultimate waste composed of fission products and minor actinides (americium and curium). Several new chemical extraction processes, such as TRUSPEAK, EXAM, or LUCA processes are pursued worldwide and their approaches will be highlighted.

  15. The proton-neutron symplectic model of nuclear collective motions

    E-Print Network [OSTI]

    H. G. Ganev

    2014-10-17T23:59:59.000Z

    A proton-neutron symplectic model of collective motions, based on the non-compact symplectic group $Sp(12,R)$, is introduced by considering the symplectic geometry of the two-component many-particle nuclear system. The possible classical collective motions are determined by different dynamical groups that can be constructed from the symplectic generators. The relation of the $Sp(12,R)$ irreps with the shell-model classification of the basis states is considered by extending of the state space to the direct product space of $SU_{p}(3) \\otimes SU_{n}(3)$ irreps, generalizing in this way the Elliott's $SU(3)$ model for the case of two-component system. The $Sp(12,R)$ model appears then as a natural multi-major-shell extension of the generalized proton-neutron $SU(3)$ scheme which takes into account the core collective excitations of monopole and quadrupole, as well as dipole type associated with the giant resonance vibrational degrees of freedom. Each $Sp(12,R)$ irreducible representation is determined by a symplectic bandhead or an intrinsic $U(6)$ space which can be fixed by the underlying proton-neutron shell-model structure, so the theory becomes completely compatible with the Pauli principle. It is shown that this intrinsic $U(6)$ structure is of vital importance for the appearance of the low-lying collective bands with both the positive and negative parity. The full range of low-lying collective states can then be described by the microscopically based intrinsic $U(6)$ structure, renormalized by coupling to the giant resonance vibrations.

  16. Consensus Based Nuclear Public-Hearing System Model

    SciTech Connect (OSTI)

    Young Wook Lee; Suk Hoon Kim; Young Ho Cho; Hyun Seok Ko; Dong Hoon Shin; Chang Sun Kang [Seoul National University (Korea, Republic of); Joo Hyun Moon [Ministry of Science and Technology (Korea, Republic of)

    2006-07-01T23:59:59.000Z

    Although the government admit the benefit of construction of a nuclear facility for national electric source, related policy could be developed and carried out only if the public, especially who have some stake on it, recognize the benefit and accept the policy. For public participation, Korea has a system of public-hearing in accordance with the law. Because of the absence of the detailed way for public opinion aggregation and for the reflection of the aggregated opinion, Korean public-hearing system is only a conceptual model. Therefore, some specific system for Korean Public-Hearing should be developed and applied. In this study, to share the right of decision making, which is an ultimate concept for public participation, decision making components and the characteristics of each phase are analyzed. The criteria weight for assessment and comparison with alternatives are founded as a valuation factor of the decision making components, which should be based on the social consensus. On these foundations, a system for aggregation and reflection of the public opinion was proposed. The system named 'CPDM' (Consensus based Participatory Decision Making) has three authority groups for decision making. At first, 'advisory experts group' play a role for the technical assessment and the serve utility value on the criteria for each alternatives. Next, 'participatory deliberation group' play a role for consensus building on the relative-importance (weight) between the criteria by feedback to promote degree of consensus. Lastly including gentlemen of the long robe, 'expert group for decision making' play a role to reflect the utility and weight and make a decision with agreement for performance of it. Also, in this study, a mathematical model for the quantification of the degree of consensus was conceptualized using Ordered Weighted Averaging (OWA) aggregation operator and fuzzy similarity theory, which is a comparison concept. Since this model enables influence of each criteria and each participant on collective consensus to be analyzed, a direction to promote consensus building can be derived. That is to say, this model can support consensus building and promote public acceptance for the nuclear industry and related policy. (authors)

  17. An improved structural mechanics model for the FRAPCON nuclear fuel performance code

    E-Print Network [OSTI]

    Mieloszyk, Alexander James

    2012-01-01T23:59:59.000Z

    In order to provide improved predictions of Pellet Cladding Mechanical Interaction (PCMI) for the FRAPCON nuclear fuel performance code, a new model, the FRAPCON Radial-Axial Soft Pellet (FRASP) model, was developed. This ...

  18. Sensitivity of economic performance of the nuclear fuel cycle to simulation modeling assumptions

    E-Print Network [OSTI]

    Bonnet, Nicéphore

    2007-01-01T23:59:59.000Z

    Comparing different nuclear fuel cycles and assessing their implications require a fuel cycle simulation model as complete and realistic as possible. In this thesis, methodological implications of modeling choices are ...

  19. Modeling piston skirt lubrication in internal combustion engines

    E-Print Network [OSTI]

    Bai, Dongfang, Ph. D. Massachusetts Institute of Technology

    2012-01-01T23:59:59.000Z

    Ever-increasing demand for reduction of the undesirable emissions from the internal combustion engines propels broader effort in auto industry to design more fuel efficient engines. One of the major focuses is the reduction ...

  20. The Global Nuclear Futures Model: A Dynamic Simulation Tool for Energy Strategies

    SciTech Connect (OSTI)

    Bixler, N.E. [Sandia National Laboratories, Albuquerque, NM 87185-0748 (United States)

    2002-07-01T23:59:59.000Z

    The Global Nuclear Futures Model (GNFM) is a dynamic simulation tool that provides an integrated framework to model key aspects of nuclear energy, nuclear materials storage and disposition, global nuclear materials management, and nuclear proliferation risk. It links nuclear energy and other energy shares dynamically to greenhouse gas emissions and twelve other measures of environmental impact. It presents historical data from 1990 to 2000 and extrapolates energy demand through the year 2050. More specifically, it contains separate modules for energy, the nuclear fuel cycle front end, the nuclear fuel cycle back end, defense nuclear materials, environmental impacts, and measures of the potential for nuclear proliferation. It is globally integrated but also breaks out five regions of the world so that environmental impacts and nuclear proliferation concerns can be evaluated on a regional basis. The five regions are the United States of America (USA), The Peoples Republic of China (China), the former Soviet Union (FSU), the OECD nations excluding the USA, and the rest of the world (ROW). (author)

  1. International Subcommittee Report

    Energy Savers [EERE]

    and overall U.S. international nuclear commercial leadership as part of the "Team USA" approach NEAC Meeting December 10, 2014 4 Recommendations by the NEAC International...

  2. Utility of Social Modeling in Assessment of a State’s Propensity for Nuclear Proliferation

    SciTech Connect (OSTI)

    Coles, Garill A.; Brothers, Alan J.; Whitney, Paul D.; Dalton, Angela C.; Olson, Jarrod; White, Amanda M.; Cooley, Scott K.; Youchak, Paul M.; Stafford, Samuel V.

    2011-06-01T23:59:59.000Z

    This report is the third and final report out of a set of three reports documenting research for the U.S. Department of Energy (DOE) National Security Administration (NASA) Office of Nonproliferation Research and Development NA-22 Simulations, Algorithms, and Modeling program that investigates how social modeling can be used to improve proliferation assessment for informing nuclear security, policy, safeguards, design of nuclear systems and research decisions. Social modeling has not to have been used to any significant extent in a proliferation studies. This report focuses on the utility of social modeling as applied to the assessment of a State's propensity to develop a nuclear weapons program.

  3. INTERNATIONAL JOURNAL OF c 2011 Institute for Scientific NUMERICAL ANALYSIS AND MODELING Computing and Information

    E-Print Network [OSTI]

    Bürger, Raimund

    -dimensional model of sedimentation of suspensions of small solid particles dispersed in a viscous fluid. This model accepted spatially one-dimensional sedimentation model [35] gives rise to one scalar, nonlinear hyperbolicINTERNATIONAL JOURNAL OF c 2011 Institute for Scientific NUMERICAL ANALYSIS AND MODELING Computing

  4. INTERNATIONAL JOURNAL OF c 2012 Institute for Scientific NUMERICAL ANALYSIS AND MODELING Computing and Information

    E-Print Network [OSTI]

    Bürger, Raimund

    -dimensional model of sedimentation of suspensions of small solid particles dispersed in a viscous fluid. This model accepted spatially one-dimensional sedimentation model [35] gives rise to one scalar, nonlinear hyperbolicINTERNATIONAL JOURNAL OF c 2012 Institute for Scientific NUMERICAL ANALYSIS AND MODELING Computing

  5. Validation of hadronic models using CALICE highly granular calorimeters, 15th International Conference on Calorimetry in High Energy Physics

    E-Print Network [OSTI]

    The CALICE Collaboration

    2015-01-01T23:59:59.000Z

    Validation of hadronic models using CALICE highly granular calorimeters, 15th International Conference on Calorimetry in High Energy Physics

  6. Koizumi says Japan still hoping to host international nuclear fusion ... http://asia.news.yahoo.com/050614/ap/d8an68i81.html 1 of 2 6/14/05 7:48 AM

    E-Print Network [OSTI]

    Koizumi says Japan still hoping to host international nuclear fusion ... http-- New Yahoo! Asia News Search Yahoo! News advertisement Tuesday June 14, 12:59 PM Koizumi says Japan still hoping to host international nuclear fusion reactor Contentious negotiations between Japan

  7. Health effects models for nuclear power plant accident consequence analysis: Modifications of models resulting from recent reports on health effects of ionizing radiation

    SciTech Connect (OSTI)

    Abrahamson, S. (Wisconsin Univ., Madison, WI (United States)); Bender, M.A. (Brookhaven National Lab., Upton, NY (United States)); Boecker, B.B.; Scott, B.R. (Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (United States). Inhalation Toxicology Research Inst.); Gilbert, E.S. (Pacific Northwest Lab., Richland, WA (United States))

    1991-08-01T23:59:59.000Z

    The Nuclear Regulatory Commission has sponsored several studies to identify and quantify the potential health effects of accidental releases of radionuclides from nuclear power plants. The most recent health effects models resulting from these efforts were published in two reports, NUREG/CR-4214, Rev. 1, Part 1 (1990) and Part 2 (1989). Several major health effects reports have been published recently that may impact the health effects models presented in these reports. This addendum to the Part 2 (1989) report, provides a review of the 1986 and 1988 reports by the United Nations Scientific Committee on the Effects of Atomic Radiation, the National Academy of Sciences/National Research Council BEAR 5 Committee report and Publication 60 of the International Commission on Radiological Protection as they relate to this report. The three main sections of this addendum discuss early occurring and continuing effects, late somatic effects, and genetic effects. The major changes to the NUREG/CR-4214 health effects models recommended in this addendum are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies like that on the Japanese A-bomb survivors. The results presented in this addendum should be used with the basic NUREG/CR-4214 reports listed above to obtain the most recent views on the potential health effects of radionuclides released accidentally from nuclear power plants. 48 refs., 4 figs., 24 tabs.

  8. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011) Rio de Janeiro, RJ, Brazil, May 8-12, 2011, on CD-ROM, Latin American Section (LAS) / American Nuclear Society (ANS)

    E-Print Network [OSTI]

    International Conference on Mathematics and Computational Methods Applied to Nuclear Science-dimensional transport simulations for ITER. Among these, we propose a new method which is computationally fast) methods are used within Monte Carlo (MC) transport codes to improve the computational efficiency

  9. Modeling of thermophoretic deposition of aerosols in nuclear reactor containments

    SciTech Connect (OSTI)

    Fernandes, A.; Loyalka, S.K. [Univ. of Missouri, Columbia, MO (United States)

    1996-12-01T23:59:59.000Z

    Aerosol released in postulated or real nuclear reactor accidents can deposit on containment surfaces via motion induced by temperature gradients in addition to the motion due to diffusion and gravity. The deposition due to temperature gradients is known as thermophoretic deposition, and it is currently modeled in codes such as CONTAIN in direct analogy with heat transfer, but there have been questions about such analogies. This paper focuses on a numerical solution of the particle continuity equation in laminar flow condition characteristics of natural convection. First, the thermophoretic deposition rate is calculated as a function of the Prandtl and Schmidt numbers, the thermophoretic coefficient K, and the temperature difference between the atmosphere and the wall. Then, the cases of diffusion alone and a boundary-layer approximation (due to Batchelor and Shen) to the full continuity equation are considered. It is noted that an analogy with heat transfer does not hold, but for the circumstances considered in this paper, the deposition rates from the diffusion solution and the boundary-layer approximation can be added to provide reasonably good agreement (maximum deviation 30%) with the full solution of the particle continuity equation. Finally, correlations useful for implementation in the reactor source term codes are provided.

  10. Helium Behavior in Oxide Nuclear Fuels: First Principles Modeling

    SciTech Connect (OSTI)

    D. Gryaznov; S. Rashkeev; E. A. Kotomin; E. Heifets; Y. Zhukovskii

    2010-10-01T23:59:59.000Z

    UO2 and (U, Pu)O2 solid solutions (the so-called MOX) nowadays are used as commercial nuclear fuels in many countries. One of the safety issues during the storage of these fuels is related to their self-irradiation that produces and accumulates point defects and helium therein. We present density functional theory (DFT) calculations for UO2, PuO2 and MOX containing He atoms in octahedral interstitial positions. In particular, we calculated basic MOX properties and He incorporation energies as functions of Pu concentration within the spin-polarized, generalized gradient approximation (GGA) DFT calculations. We also included the on-site electron correlation corrections using the Hubbard model (in the framework of the so-called DFT + U approach). We found that PuO2 remains semiconducting with He in the octahedral position while UO2 requires a specific lattice distortion. Both materials reveal a positive energy for He incorporation, which, therefore, is an exothermic process. The He incorporation energy increases with the Pu concentration in the MOX fuel.

  11. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 52 (2012) 013005 (11pp) doi:10.1088/0029-5515/52/1/013005

    E-Print Network [OSTI]

    Farge, Marie

    #12;IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 52 (2012-vaguelette decomposition. After validation of the new method using an academic test case and numerical data obtained, but the associated vessel erosion also impairs the awaited viability of long lasting discharges. It is thus

  12. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014002 (10pp) doi:10.1088/0029-5515/50/1/014002

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    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

  13. INSTITUTE OF PHYSICS PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 43 (2003) 16931709 PII: S0029-5515(03)67272-8

    E-Print Network [OSTI]

    Ghoniem, Nasr M.

    2003-01-01T23:59:59.000Z

    INSTITUTE OF PHYSICS PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 43 (2003) 1693­1709 PII: S0029-5515(03)67272-8 Fusion energy with lasers, direct drive targets.iop.org/NF/43/1693 Abstract A coordinated, focused effort is underway to develop Laser Inertial Fusion Energy

  14. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 49 (2009) 104010 (12pp) doi:10.1088/0029-5515/49/10/104010

    E-Print Network [OSTI]

    École Normale Supérieure

    2009-01-01T23:59:59.000Z

    IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 49 (2009) 104010. Zwingmann CEA, IRFM, F-13108 St Paul-lez-Durance, France 1 Associazione EURATOM-ENEA sulla Fusione, C;Nucl. Fusion 49 (2009) 104010 G. Giruzzi et al 9 LJAD, U.M.R. C.N.R.S. No 6621, Universit´e de Nice

  15. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014004 (14pp) doi:10.1088/0029-5515/50/1/014004

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014004.iop.org/NF/50/014004 Abstract Fusion energy research began in the early 1950s as scientists worked to harness at demonstrating fusion energy producing plasmas. PACS numbers: 52.55.-s, 52.57.-z, 28.52.-s, 89.30.Jj (Some

  16. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014006 (6pp) doi:10.1088/0029-5515/50/1/014006

    E-Print Network [OSTI]

    .57.-z, 89.30.Ji 1. Laser and laser fusion from past and present to future In 1917, Albert EinsteinIOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014006 energized implosion could be utilized for energy generation. Today, there are many facilities worldwide

  17. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 48 (2008) 084001 (13pp) doi:10.1088/0029-5515/48/8/084001

    E-Print Network [OSTI]

    Heidbrink, William W.

    2008-01-01T23:59:59.000Z

    IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 48 (2008) 084001] and created a vacuum leak in the tokamak fusion test reactor (TFTR) [4]. The damage was explained comparisons between theory and experiment [5­7], wave amplitudes an order of magnitude larger than

  18. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 52 (2012) 013001 (13pp) doi:10.1088/0029-5515/52/1/013001

    E-Print Network [OSTI]

    Budny, Robert

    2012-01-01T23:59:59.000Z

    IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 52 (2012) 013001 using the PTRANSP code. The baseline toroidal field (5.3 T), plasma current ramped to 15 MA and a flat are predicted assuming GLF23 and boundary parameters. Conservatively low temperatures ( 0.6 keV) and v 400 rad s

  19. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 47 (2007) S608S621 doi:10.1088/0029-5515/47/10/S10

    E-Print Network [OSTI]

    Martín-Solís, José Ramón

    2007-01-01T23:59:59.000Z

    IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 47 (2007) S608­S, EURATOM Association, 01-497, Warsaw, Poland E-mail: pericoli@frascati.enea.it Received 30 January 2007 of turbulence suppression and energy transport. At the highest densities the ion thermal conductivity remains

  20. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 095005 (15pp) doi:10.1088/0029-5515/50/9/095005

    E-Print Network [OSTI]

    Vlad, Gregorio

    2010-01-01T23:59:59.000Z

    IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 095005, Warsaw, Poland E-mail: Pizzuto@frascati.enea.it Received 5 January 2009, accepted for publication 15 June) in the energy range 0.5­1 MeV. The total power input will be in the 30­40 MW range under different plasma

  1. Modeling Gamma-Ray Burst X-Ray Flares within the Internal Shock Model

    E-Print Network [OSTI]

    Maxham, Amanda

    2009-01-01T23:59:59.000Z

    X-ray afterglow light curves have been collected for over 400 Swift gamma-ray bursts with nearly half of them having X-ray flares superimposed on the regular afterglow decay. Evidence suggests that gamma-ray prompt emission and X-ray flares share a common origin and that at least some flares can only be explained by long-lasting central engine activity. We have developed a shell model code to address the question of how X-ray flares are produced within the framework of the internal shock model. The shell model creates randomized GRB explosions from a central engine with multiple shells and follows those shells as they collide, merge and spread, producing prompt emission and X-ray flares. We pay special attention to the time history of central engine activity, internal shocks, and observed flares, but do not calculate the shock dynamics and radiation processes in detail. Using the empirical E_p - E_iso (Amati) relation with an assumed Band function spectrum for each collision and an empirical flare temporal pr...

  2. Use of international data sets to evaluate and validate pathway assessment models applicable to exposure and dose reconstruction at DOE facilities. Progress report, March--May 1994

    SciTech Connect (OSTI)

    Anspaugh, L.R.; Hendrickson, S.M. [eds.] [Lawrence Livermore National Lab., CA (United States); Hoffman, F.O. [Senes Oak Ridge, Inc., TN (United States). Center for Risk Analysis

    1994-06-01T23:59:59.000Z

    The project described in this report was the result of a Memorandum of Cooperation between the US and the former-USSR following the accident at the Chernobyl Nuclear Power Plant Unit 4. A joint program was established to improve the safety of nuclear power plants and to understand the implications of environmental releases. The task of Working Group 7 was ``to develop jointly methods to project rapidly the health effects of any future nuclear reactor accident.`` The current objective of this project is to evaluate and validate pathway-assessment models applicable to exposure and dose reconstruction at DOE facilities through use of international data sets. This project incorporates data used for the prediction of radionuclide transfer through agricultural and aquatic systems to humans. It also includes participation in two multinational studies, BIOMOVS (Biospheric Model Validation Study) with the Swedish National Institute for Radiation Protection and VAMP (Validation of Model Predictions) with the International Atomic Energy Agency, that address testing the performance of models of radionuclide transport through foodchains. In the future, this project will be considered separately from the Chernobyl Studies Project and the essential activities of former Task 7.1D will be folded within the broader umbrella of the BIOMOVS and VAMP projects. The Working Group Leader of Task 7.1D will continue to provide oversight for this project.

  3. Nuclear reactor with internal thimble-type delayed neutron detection system

    SciTech Connect (OSTI)

    Gross, K.C.; Poloncsik, J.; Lambert, J.D.B.

    1990-07-03T23:59:59.000Z

    This paper describes a liquid-metal cooled nuclear reactor. It comprises: a housing having a core containing nuclear material, a shell and tube heat exchanger positioned within the housing. The shell and tube heat exchanger have the tubes thereof arranged in parallel, a primary coolant within the shell and tube heat exchanger, means for detecting positioned within a tube in the shell and tube heat exchanger for generating a signal in response to a reaction detected by the means for detecting, the means for detecting including signal detectors D-1, D-2, and D-3 selectively spaced from one another along the coolant flow within the shell and tube heat exchanger so that the total time lapsed after the occurrence of the reaction and a delayed-neutron is detected is: TOTAL = T{sub h} + T{sub t} + T{sub d}. Where: T{sub h} = isotopic holdup time for the delayed-neutron traveling from the reaction spot to the coolant T{sub t} = transit time for the delayed-neutron traveling from the coolant to the heat exchanger inlet T{sub d} = constant transit time for the delayed-neutrons to reach each of the delayed-neutron detectors D-1, D-2, and D-3, which is dependent upon the position of the delayed-neutron detector; and a mechanism remotely connected to the signal detectors to record the reaction detected thereby.

  4. Business model transformation for the international division of a fortune 100 high technology company

    E-Print Network [OSTI]

    Mokhtari Dizaji, Reza, 1968-

    2008-01-01T23:59:59.000Z

    Raytheon Canada in Waterloo, Ontario offers a very interesting but challenging research case. As one of the international divisions of Raytheon Corporation, the company has a business model similar to its parent company. ...

  5. International Conference on Production Research PRODUCT INTERACTIONS MODELLING WITHIN THE SUPPLY CHAIN

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    products, processes and customers along the product lifecycle. These requirements generate19 th International Conference on Production Research PRODUCT INTERACTIONS MODELLING WITHIN concept in the supply chain. This approach considers a product as a service provider or a service

  6. International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009) Saratoga Springs, New York, May 3-7, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009)

    E-Print Network [OSTI]

    Vialle, Stéphane

    operator such as EDF, the time required to compute nuclear reactor core simulations is rather critical. Introduction As operator of nuclear power plants, EDF needs many nuclear reactor core simulationsInternational Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009

  7. New Olodels COnfirOl nuclear winter Everything from purely mathematical models to forest fire studies shows that

    E-Print Network [OSTI]

    Robock, Alan

    New Olodels COnfirOl nuclear winter Everything from purely mathematical models to forest fire conclusion is that nuclear war must be prevented- by Star Wars. by Alan Roback THE THEORY OF nuclear winter. The basic theory of nuclear winter has remained un- changed since it was first described by Paul Crutzen

  8. MODEL-DRIVEN ENGINEERING FOR IMPLEMENTING THE ISO 19100 SERIES OF INTERNATIONAL STANDARDS

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    MODEL-DRIVEN ENGINEERING FOR IMPLEMENTING THE ISO 19100 SERIES OF INTERNATIONAL STANDARDS CYRIL of the ISO 19100 series of standards with use of Model-Driven Engineering (MDE) techniques. We expose how MDE to use ISO 19109, 19110 and 19117 models in order to generate a rich client application. Our work takes

  9. Results from an International Simulation Study on Coupled Thermal, Hydrological, and Mechanical (THM) Processes near Geological Nuclear Waste Repositories

    E-Print Network [OSTI]

    Rutqvist, J.

    2008-01-01T23:59:59.000Z

    safety of a hypothetical nuclear waste repository – BMT1 ofAssociated with Nuclear Waste Repositories, Academic Press,safety of a hypothetical nuclear waste repository – BMT1 of

  10. TAMCN: a tool for aggregate modeling of civil nuclear materials 

    E-Print Network [OSTI]

    Watson, Aaron Michael

    2002-01-01T23:59:59.000Z

    and flow" structure of STELLA® to describe the discharge, storage, and reprocessing of spent nuclear fuel from commercial power reactors, and the creation, storage, and utilization of reactor-grade civil separated plutonium in these regions. This provides...

  11. Recent Developments of the Nuclear Reaction Model Code EMPIRE

    SciTech Connect (OSTI)

    Herman, M.; Oblozinsky, P. [National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973 (United States); Capote, R.; Trkov, A.; Zerkin, V. [International Atomic Energy Agency, Vienna (Austria); Sin, M. [University of Bucharest, Bucharest (Romania); Ventura, A. [Ente Nazionale Energie Alternative, Bologna (Italy)

    2005-05-24T23:59:59.000Z

    Recent extensions and improvements of the EMPIRE code system are outlined. They add to the code new capabilities such as fission of actinides, preequilibrium emission of clusters, photo-nuclear reactions, and reactions on excited targets. These features, along with improved ENDF formatting, exclusive spectra, and recoils make the forthcoming 2.19 release a complete tool for evaluation of nuclear data at incident energies above the resonance region.

  12. Transient modeling of thermionic space nuclear power systems

    E-Print Network [OSTI]

    Berge, Francoise M

    1991-01-01T23:59:59.000Z

    nuclear power system is based on static power conversion, heat transfer and waste heat rejection. The core is composed of annular Fuel rings. The thermionic power converters are located circumferentially around the core alternating with the radial... reflector segments. The radiator panels are attached to the axial rows of converters consti- tuting the power converter subassembly. A space nuclear power system can be described as an assembly of functional units such as the core, the heat removal system...

  13. Modeling Solute Thermokinetics in LiCI-KCI Molten Salt for Nuclear Waste Separation

    SciTech Connect (OSTI)

    Morgan, Dane; Eapen, Jacob

    2013-10-01T23:59:59.000Z

    Recovery of actinides is an integral part of a closed nuclear fuel cycle. Pyrometallurgical nuclear fuel recycling processes have been developed in the past for recovering actinides from spent metallic and nitride fuels. The process is essentially to dissolve the spent fuel in a molten salt and then extract just the actinides for reuse in a reactor. Extraction is typically done through electrorefining, which involves electrochemical reduction of the dissolved actinides and plating onto a cathode. Knowledge of a number of basic thermokinetic properties of salts and salt-fuel mixtures is necessary for optimizing present and developing new approaches for pyrometallurgical waste processing. The properties of salt-fuel mixtures are presently being studied, but there are so many solutes and varying concentrations that direct experimental investigation is prohibitively time consuming and expensive (particularly for radioactive elements like Pu). Therefore, there is a need to reduce the number of required experiments through modeling of salt and salt-fuel mixture properties. This project will develop first-principles-based molecular modeling and simulation approaches to predict fundamental thermokinetic properties of dissolved actinides and fission products in molten salts. The focus of the proposed work is on property changes with higher concentrations (up to 5 mol%) of dissolved fuel components, where there is still very limited experimental data. The properties predicted with the modeling will be density, which is used to assess the amount of dissolved material in the salt; diffusion coefficients, which can control rates of material transport during separation; and solute activity, which determines total solubility and reduction potentials used during electrorefining. The work will focus on La, Sr, and U, which are chosen to include the important distinct categories of lanthanides, alkali earths, and actinides, respectively. Studies will be performed using LiCl-KCl salt at the eutectic composition (58 mol% LiCl, 42 mol% KCl), which is used for treating spent EBR-II fuel. The same process being used for EBRII fuel is currently being studied for widespread international implementation. The methods will focus on first-principles and first- principles derived interatomic potential based simulations, primarily using molecular dynamics. Results will be validated against existing literature and parallel ongoing experimental efforts. The simulation results will be of value for interpreting experimental results, validating analytical models, and for optimizing waste separation by potentially developing new salt configurations and operating conditions.

  14. A comparison of the additional protocols of the five nuclear weapon states and the ensuing safeguards benefits to international nonproliferation efforts

    SciTech Connect (OSTI)

    Uribe, Eva C [Los Alamos National Laboratory; Sandoval, M Analisa [Los Alamos National Laboratory; Sandoval, Marisa N [Los Alamos National Laboratory; Boyer, Brian D [Los Alamos National Laboratory; Leitch, Rosalyn M [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    With the 6 January 2009 entry into force of the Additional Protocol by the United States of America, all five declared Nuclear Weapon States that are part of the Nonproliferation Treaty have signed, ratified, and put into force the Additional Protocol. This paper makes a comparison of the strengths and weaknesses of the five Additional Protocols in force by the five Nuclear Weapon States with respect to the benefits to international nonproliferation aims. This paper also documents the added safeguards burden to the five declared Nuclear Weapon States that these Additional Protocols put on the states with respect to access to their civilian nuclear programs and the hosting of complementary access activities as part of the Additional Protocol.

  15. The Internal-Collision-Induced Magnetic Reconnection and Turbulence (ICMART) Model of Gamma-Ray Bursts

    E-Print Network [OSTI]

    Zhang, Bing

    2010-01-01T23:59:59.000Z

    The recent Fermi observation of GRB 080916C shows that the bright photosphere emission associated with a putative fireball is missing, which suggests a Poynting-flux-dominated outflow. We propose a model of gamma-ray burst (GRB) prompt emission in the Poynting-flux-dominated regime, namely, the Internal-Collision-induced MAgnetic Reconnection and Turbulence (ICMART) model. It is envisaged that the GRB central engine launches an intermittent, magnetically-dominated wind, and that in the GRB emission region, the ejecta is still moderately magnetized. Similar to the internal shock (IS) model, the mini-shells interact internally at the traditional internal shock radius. Most of these early collision have little energy dissipation, but serve to distort the ordered magnetic field lines. At a certain point, the distortion of magnetic field configuration reaches the critical condition to allow fast reconnection seeds to occur, which induce relativistic MHD turbulence in the interaction regions. The turbulence further...

  16. Optimization Online - Augmented L1 and Nuclear-Norm Models with ...

    E-Print Network [OSTI]

    Ming-Jun Lai

    2012-01-22T23:59:59.000Z

    Jan 22, 2012 ... Augmented L1 and Nuclear-Norm Models with a Globally Linearly Convergent Algorithm. Ming-Jun Lai (mjlai ***at*** math.uga.edu) Wotao Yin ...

  17. Virtual enterprise model for the electronic components business in the Nuclear Weapons Complex

    SciTech Connect (OSTI)

    Ferguson, T.J.; Long, K.S.; Sayre, J.A. [Sandia National Labs., Albuquerque, NM (United States); Hull, A.L. [Sandia National Labs., Livermore, CA (United States); Carey, D.A.; Sim, J.R.; Smith, M.G. [Allied-Signal Aerospace Co., Kansas City, MO (United States). Kansas City Div.

    1994-08-01T23:59:59.000Z

    The electronic components business within the Nuclear Weapons Complex spans organizational and Department of Energy contractor boundaries. An assessment of the current processes indicates a need for fundamentally changing the way electronic components are developed, procured, and manufactured. A model is provided based on a virtual enterprise that recognizes distinctive competencies within the Nuclear Weapons Complex and at the vendors. The model incorporates changes that reduce component delivery cycle time and improve cost effectiveness while delivering components of the appropriate quality.

  18. Phase diagram for the asymmetric nuclear matter in the multifragmentation model

    E-Print Network [OSTI]

    G. Chaudhuri; S. Das Gupta

    2009-08-11T23:59:59.000Z

    We assume that, in equilibrium, nuclear matter at reduced density and moderate finite temperature, breaks up into many fragments. A strong support to this assumption is provided by date accumulated from intermediate energy heavy ion collisions. The break-up of hot and expanded nuclear matter according to rules of equilibrium statistical mechanics is the multifragmentation model. The model gives a first order phase transition. This is studied in detail here. Phase-equilibrium lines for different degrees of asymmetry are computed.

  19. Nuclear reactor with internal thimble-type delayed neutron detection system

    SciTech Connect (OSTI)

    Gross, Kenny C. (Lemont, IL); Poloncsik, John (Downers Grove, IL); Lambert, John D. B. (Wheaton, IL)

    1990-01-01T23:59:59.000Z

    This invention teaches improved apparatus for the method of detecting a breach in cladded fuel used in a nuclear reactor. The detector apparatus is located in the primary heat exchanger which conveys part of the reactor coolant past at least three separate delayed-neutron detectors mounted in this heat exchanger. The detectors are spaced apart such that the coolant flow time from the core to each detector is different, and these differences are known. The delayed-neutron activity at the detectors is a function of the delay time after the reaction in the fuel until the coolant carrying the delayed-neutron emitter passes the respective detector. This time delay is broken down into separate components including an isotopic holdup time required for the emitter to move through the fuel from the reaction to the coolant at the breach, and two transit times required for the emitter now in the coolant to flow from the breach to the detector loop and then via the loop to the detector. At least two of these time components are determined during calibrated operation of the reactor. Thereafter during normal reactor operation, repeated comparisons are made by the method of regression approximation of the third time component for the best-fit line correlating measured delayed-neutron activity against activity that is approximated according to specific equations. The equations use these time-delay components and known parameter values of the fuel and of the part and emitting daughter isotopes.

  20. Nonlinear adaptive internal model control using neural networks

    E-Print Network [OSTI]

    Gandhi, Amit Krushnavadan

    2001-01-01T23:59:59.000Z

    (NIMC) strategy based on neural network models is presented for SISO processes. The nonlinearities of the dynamical system are modelled by neural network architectures. Recurrent neural networks can be used for both the identification and control of nonlinear...

  1. A Model-Based Signal Processing Approach to Nuclear Explosion Monitoring

    SciTech Connect (OSTI)

    Rodgers, A; Harris, D; Pasyanos, M

    2007-03-14T23:59:59.000Z

    This report describes research performed under Laboratory Research and Development Project 05-ERD-019, entitled ''A New Capability for Regional High-Frequency Seismic Wave Simulation in Realistic Three-Dimensional Earth Models to Improve Nuclear Explosion Monitoring''. A more appropriate title for this project is ''A Model-Based Signal Processing Approach to Nuclear Explosion Monitoring''. This project supported research for a radically new approach to nuclear explosion monitoring as well as allowed the development new capabilities in computational seismology that can contribute to NNSA/NA-22 Programs.

  2. A Comparison Between Model Reduction and Controller Reduction: Application to a PWR Nuclear Planty

    E-Print Network [OSTI]

    Gevers, Michel

    A Comparison Between Model Reduction and Controller Reduction: Application to a PWR Nuclear Planty model reduction with controller reduction for the same PWR system. We show that closed-loop techniques to the design of a low-order con- troller for a realistic model of order 42 of a Pressurized Water Reactor (PWR

  3. Nuclear lattice model and the electronic configuration of the chemical elements

    E-Print Network [OSTI]

    Jozsef Garai

    2015-07-07T23:59:59.000Z

    The fundamental organizing principle resulting in the periodic table is the nuclear charge. Arranging the chemical elements in an increasing atomic number order, a symmetry pattern known as the Periodic Table is detectable. The correlation between nuclear charge and the Periodic System of the Chemical Elements (PSCE) indicates that the symmetry emerges from the nucleus. Nuclear symmetry can only exist if the relative positions of the nucleons in the nucleus are invariant. Pauli exclusion principle can also be interpreted as the nucleons should occupy a lattice position. Based on symmetry and other indicatives face centered cubic arrangement have been proposed for the nuclear lattice. A lattice model, representing the protons and the neutrons by equal spheres and arranging them alternately in a face centered cubic structure forming a double tetrahedron, is able to reproduce all of the properties of the nucleus including the quantum numbers and the periodicity of the elements. Based on the geometry of the nuclear structure it is shown that when a new 'layer' of the nuclear structure starts then the distance between the first proton in the new layer and the charge center of the nucleus is smaller than the distance of the proton, which completed the preceding 'layer'. Thus a new valence electron shell should start to develop when the nuclear structure is expanded. The expansion of the double tetrahedron FCC nuclear lattice model offers a feasible physical explanation how the nucleus affects the electronic configuration of the chemical elements depicted by the periodic table.

  4. Isospin-dependent properties of asymmetric nuclear matter in relativistic mean field models RID A-2398-2009

    E-Print Network [OSTI]

    Chen, Lie-Wen; Ko, Che Ming; Li, Bao-An.

    2007-01-01T23:59:59.000Z

    -dependent bulk and single-particle properties of asymmetric nuclear matter. In particular, we have determined the density dependence of nuclear symmetry energy from these different relativistic mean-field models and compared the results with the constraints...

  5. Report of a workshop on nuclear power growth and nonproliferation held at the Woodrow Wilson international center for scholars, Washington, DC, April 21, 2010

    SciTech Connect (OSTI)

    Pilat, Joseph F [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    The workshop addressed the future of nuclear power and nonproliferation in light of global nuclear energy developments, changing US policy and growing concerns about nuclear proliferation and terrorism. The discussion reflected wide agreement on the need for nuclear power, the necessity of mitigating any proliferation and terrorism risks and support for international cooperation on solutions. There were considerable differences on the nature and extent of the risks of differing fuel cycle choices. There was some skepticism about the prospects for a global nuclear energy renaissance, but there was a recognition that nuclear power would expand somewhat in the decades ahead with some states expanding capacity dramatically (e.g., China) and at least a few new states developing nuclear power programs. It was also argued by some participants that under the right conditions, a genuine renaissance could occur some decades from now. The prospects for a dramatic growth in nuclear power will depend on the ability of governments and industry to address these concerns, including the effectiveness of, and the resources devoted to, plans to develop and implement technologies and approaches that strengthen nonproliferation, nuclear materials accountability and nuclear security Several participants noted that the United States will not be able to continue to lead global nonproliferation efforts and to shape the growth of nuclear power as well as the global environment and energy debates without a robust US nuclear energy program. Some participants argued that fully integrating nuclear energy growth and nonproliferation, proliferation resistance and physical protection objectives was possible. The growing consensus on these objectives and the growing concern about the potential impact of further proliferation on the industry was one reason for optimism. The Blue Ribbon commission led by Scowcroft and Hamilton was seen as going far beyond the need to find an alternative to Yucca Mountain, and the preeminent forum in the next years to address the back end of the fuel cycle and other issues. Some argued that addressing these issues is the critical missing element, or the final piece of the puzzle to ensure the benefits of nuclear power and to promote nonproliferation. In this context, many argued that R&D on closed as well as open fuel cycle options in order to ensure a suite of long-term options was essential.

  6. Nuclear Nonproliferation Programs | ORNL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Initiatives Nonproliferation Technology Nonproliferation Systems Safeguards and Security Technology International Safeguards Nuclear Material Detection and Characterization For...

  7. International Conference on Human Resource Development for Nuclear Power Programmes: Strategies for Education and Training, Networking and Knowledge Management

    SciTech Connect (OSTI)

    Pepper, S.

    2014-06-24T23:59:59.000Z

    The IAEA’s Junior Professional Officer (JPO) program provides the opportunity for early career professionals to obtain valuable work experience while helping the IAEA perform basic, yet essential work that would otherwise be performed by an experienced staff member. JPO assignments span the spectrum of IAEA tasks, including open source information collection and analysis, equipment evaluation, testing, and installation, statistical analysis of data, software and web development, entomology, performance strategy, project management, communications, and stable isotope analysis. JPOs are college graduates with degrees in science, engineering, or other disciplines relevant to the work of the IAEA, generally 32 years old or younger, and have approximately two years’ professional experience. They work with the IAEA in entry-level positions for one or two years under extrabudgetary funding provided by an IAEA Member State. Currently, ten Member States have JPO agreements with the IAEA. The United States initiated its JPO program in 2004 and has found that the program has advantages for both the IAEA and the United States. The IAEA is an excellent environment for introducing young scientists, engineers and other professionals to the practical application of their education, to international civil service, to the challenges facing the global nuclear industry, and to the industry’s practitioners. This paper will summarize the advantages of the JPO program to the IAEA and to the Member State.

  8. International Conference on Machine Control & Guidance 2008 1 Generation and Analysis of Digital Terrain Models with

    E-Print Network [OSTI]

    1st International Conference on Machine Control & Guidance 2008 1 Generation and Analysis of Digital Terrain Models with Parallel Guidance Systems for Precision Agriculture Görres GRENZDÖRFFER models at no or little additional cost. In the paper the achievable data accuracy under different

  9. Observer-Controllers for Output Regulation: the Internal Model Principle Revisited

    E-Print Network [OSTI]

    Pao, Lucy Y.

    Observer-Controllers for Output Regulation: the Internal Model Principle Revisited Jason H. Laks rejection;tracking;model predictive control;output feedback control 1 Introduction Output regulation, the design of an output regulating observer-controller is less clear. This latter approach is based

  10. An XFEM Model for Carbon Sequestration Journal: International Journal for Numerical Methods in Engineering

    E-Print Network [OSTI]

    Gracie, Robert

    PeerReview Only An XFEM Model for Carbon Sequestration Journal: International Journal for Numerical method, Carbon Sequestration, Multiphase flow, XFEM, Multifield systems, Petrov-Galerkin httpScience (www.interscience.wiley.com). DOI: 10.1002/nme An XFEM Model for Carbon Sequestration Chris Ladubec

  11. The International Urban Energy Balance Models Comparison Project: First Results from Phase 1

    E-Print Network [OSTI]

    Ribes, Aurélien

    The International Urban Energy Balance Models Comparison Project: First Results from Phase 1 C. S and Kapodistrian University of Athens, Athens, Greece h University of Lo´ dz´, Lo´ dz´, Poland i Royal) ABSTRACT A large number of urban surface energy balance models now exist with different assumptions about

  12. International Conference of Modeling, Optimization and Simulation -MOSIM'12 June 06-08, 2012Bordeaux -France

    E-Print Network [OSTI]

    Boyer, Edmond

    with a different approach. KEYWORDS: artificial neural networks inversion; inverse problems; groundwater modeling; groundwater pollution source identification. 1 INTRODUCTION Only a small percentage of water present on Earth9th International Conference of Modeling, Optimization and Simulation - MOSIM'12 June 06-08, 2012

  13. Coupled neutronic and thermal-hydraulic code benchmark activities at the International Nuclear Safety Center.

    SciTech Connect (OSTI)

    Podlazov, L. N.

    1998-07-29T23:59:59.000Z

    Two realistic benchmark problems are defined and used to assess the performance of coupled thermal-hydraulic and neutronic codes used in simulating dynamic processes in VVER-1000 and RBMK reactor systems. One of the problems simulates a design basis accident involving the ejection of three control and protection system rods from a VVER-1000 reactor. The other is based on a postulated rod withdrawal from an operating RBMK reactor. Preliminary results calculated by various codes are compared. While these results show significant differences, the intercomparisons performed so far provide a basis for further evaluation of code limitations and modeling assumptions.

  14. Use of the nuclear model code GNASH to calculate cross section data at energies up to 100 MeV

    SciTech Connect (OSTI)

    Young, P.G.; Chadwick, M.B.; Bosoian, M.

    1992-12-01T23:59:59.000Z

    The nuclear theory code GNASH has been used to calculate nuclear data for incident neutrons, protons, and deuterons at energies up to 100 MeV. Several nuclear models and theories are important in the 10--100 MeV energy range, including Hauser-Feshbach statistical theory, spherical and deformed optical model, preequilibrium theory, nuclear level densities, fission theory, and direct reaction theory. In this paper we summarize general features of the models in GNASH and describe the methodology utilized to determine relevant model parameters. We illustrate the significance of several of the models and include comparisons with experimental data for certain target materials that are important in applications.

  15. Use of the nuclear model code GNASH to calculate cross section data at energies up to 100 MeV

    SciTech Connect (OSTI)

    Young, P.G.; Chadwick, M.B.; Bosoian, M.

    1992-01-01T23:59:59.000Z

    The nuclear theory code GNASH has been used to calculate nuclear data for incident neutrons, protons, and deuterons at energies up to 100 MeV. Several nuclear models and theories are important in the 10--100 MeV energy range, including Hauser-Feshbach statistical theory, spherical and deformed optical model, preequilibrium theory, nuclear level densities, fission theory, and direct reaction theory. In this paper we summarize general features of the models in GNASH and describe the methodology utilized to determine relevant model parameters. We illustrate the significance of several of the models and include comparisons with experimental data for certain target materials that are important in applications.

  16. Probing particle and nuclear physics models of neutrinoless double beta decay with different nuclei

    E-Print Network [OSTI]

    G. L. Fogli; E. Lisi; A. M. Rotunno

    2009-08-06T23:59:59.000Z

    Half-life estimates for neutrinoless double beta decay depend on particle physics models for lepton flavor violation, as well as on nuclear physics models for the structure and transitions of candidate nuclei. Different models considered in the literature can be contrasted - via prospective data - with a "standard" scenario characterized by light Majorana neutrino exchange and by the quasiparticle random phase approximation, for which the theoretical covariance matrix has been recently estimated. We show that, assuming future half-life data in four promising nuclei (Ge-76, Se-82, Te-130, and Xe-136), the standard scenario can be distinguished from a few nonstandard physics models, while being compatible with alternative state-of-the-art nuclear calculations (at 95% C.L.). Future signals in different nuclei may thus help to discriminate at least some decay mechanisms, without being spoiled by current nuclear uncertainties. Prospects for possible improvements are also discussed.

  17. Probing particle and nuclear physics models of neutrinoless double beta decay with different nuclei

    SciTech Connect (OSTI)

    Fogli, G. L.; Rotunno, A. M. [Dipartimento Interateneo di Fisica 'Michelangelo Merlin', Via Amendola 173, 70126 Bari (Italy); Istituto Nazionale di Fisica Nucleare, Sezione di Bari, Via Orabona 4, 70126 Bari (Italy); Lisi, E. [Istituto Nazionale di Fisica Nucleare, Sezione di Bari, Via Orabona 4, 70126 Bari (Italy)

    2009-07-01T23:59:59.000Z

    Half-life estimates for neutrinoless double beta decay depend on particle physics models for lepton-flavor violation, as well as on nuclear physics models for the structure and transitions of candidate nuclei. Different models considered in the literature can be contrasted - via prospective data - with a 'standard' scenario characterized by light Majorana neutrino exchange and by the quasiparticle random phase approximation, for which the theoretical covariance matrix has been recently estimated. We show that, assuming future half-life data in four promising nuclei ({sup 76}Ge, {sup 82}Se, {sup 130}Te, and {sup 136}Xe), the standard scenario can be distinguished from a few nonstandard physics models, while being compatible with alternative state-of-the-art nuclear calculations (at 95% C.L.). Future signals in different nuclei may thus help to discriminate at least some decay mechanisms, without being spoiled by current nuclear uncertainties. Prospects for possible improvements are also discussed.

  18. Modeling nuclear weak-interaction processes with relativistic energy density functionals

    E-Print Network [OSTI]

    Paar, N; Vale, D; Vretenar, D

    2015-01-01T23:59:59.000Z

    Relativistic energy density functionals have become a standard framework for nuclear structure studies of ground-state properties and collective excitations over the entire nuclide chart. We review recent developments in modeling nuclear weak-interaction processes: charge-exchange excitations and the role of isoscalar proton-neutron pairing, charged-current neutrino-nucleus reactions relevant for supernova evolution and neutrino detectors, and calculation of beta-decay rates for r-process nucleosynthesis.

  19. International Fuel Services and Commercial Engagement | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    International Fuel Services and Commercial Engagement International Fuel Services and Commercial Engagement The Office of International Nuclear Energy Policy and Cooperation...

  20. Survey of thermal-hydraulic models of commercial nuclear power plants

    SciTech Connect (OSTI)

    Determan, J.C.; Hendrix, C.E.

    1992-12-01T23:59:59.000Z

    A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC's current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model is described.

  1. Survey of thermal-hydraulic models of commercial nuclear power plants

    SciTech Connect (OSTI)

    Determan, J.C.; Hendrix, C.E.

    1992-12-01T23:59:59.000Z

    A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC`s current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model is described.

  2. Revised rail-stop exposure model for incident-free transport of nuclear waste

    SciTech Connect (OSTI)

    Ostmeyer, R.M.

    1986-02-01T23:59:59.000Z

    This report documents a model for estimating railstop doses that occur during incident-free transport of nuclear waste by rail. The model, which has been incorporated into the RADTRAN III risk assessment code, can be applied to general freight and dedicated train shipments of waste.

  3. International Conference "Computational Modeling and Simulation of Materials" Sicily 2004

    E-Print Network [OSTI]

    Webb, Roger P.

    how the deformation of a silicon surface caused by a high energy C60 impact can eject a large cages. But also the use of C60 ions in secondary mass spectrometry (SIMS) as a probing beam is showing in collaboration with the University of Karlsruhe, the simulation models have been verified for both low energy

  4. Development and validation of instantaneous risk model in nuclear power plant's risk monitor

    SciTech Connect (OSTI)

    Wang, J.; Li, Y.; Wang, F.; Wang, J.; Hu, L. [Inst. of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); School of Nuclear Science and Technology, Univ. of Science and Technology of China, Hefei, Anhui, 230031 (China)

    2012-07-01T23:59:59.000Z

    The instantaneous risk model is the fundament of calculation and analysis in a risk monitor. This study focused on the development and validation of an instantaneous risk model. Therefore the principles converting from the baseline risk model to the instantaneous risk model were studied and separated trains' failure modes modeling method was developed. The development and validation process in an operating nuclear power plant's risk monitor were also introduced. Correctness of instantaneous risk model and rationality of converting method were demonstrated by comparison with the result of baseline risk model. (authors)

  5. Progress toward bridging from atomistic to continuum modeling to predict nuclear waste glass dissolution.

    SciTech Connect (OSTI)

    Zapol, Peter (Argonne National Laboratory, Argonne, IL); Bourg, Ian (Lawrence Berkeley National Laboratories, Berkeley, CA); Criscenti, Louise Jacqueline; Steefel, Carl I. (Lawrence Berkeley National Laboratories, Berkeley, CA); Schultz, Peter Andrew

    2011-10-01T23:59:59.000Z

    This report summarizes research performed for the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Subcontinuum and Upscaling Task. The work conducted focused on developing a roadmap to include molecular scale, mechanistic information in continuum-scale models of nuclear waste glass dissolution. This information is derived from molecular-scale modeling efforts that are validated through comparison with experimental data. In addition to developing a master plan to incorporate a subcontinuum mechanistic understanding of glass dissolution into continuum models, methods were developed to generate constitutive dissolution rate expressions from quantum calculations, force field models were selected to generate multicomponent glass structures and gel layers, classical molecular modeling was used to study diffusion through nanopores analogous to those in the interfacial gel layer, and a micro-continuum model (K{mu}C) was developed to study coupled diffusion and reaction at the glass-gel-solution interface.

  6. Two novel procedures for aggregating randomized model ensemble outcomes for robust signal reconstruction in nuclear power plants monitoring systems

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    reconstruction in nuclear power plants monitoring systems P. Baraldi1 , E. Zio1,* , G. Gola2 , D. Roverso2 , M importance for the safe and reliable operation of nuclear power plants. Auto-associative regression models of nuclear power plants for it allows the timely detection of malfunctions and anomalies during operation

  7. ccsd-00001474,version2-6Sep2004 Model-independent tracking of criticality signals in nuclear multifragmentation data

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    ccsd-00001474,version2-6Sep2004 Model-independent tracking of criticality signals in nuclear-CNRS et Universit´e F-69622 Villeurbanne, France. 8 Institute of Nuclear Physics, Pl-31342 Krak´ow, Poland. 9 National Institute for Physics and Nuclear Engineering, RO-76900 Bucharest-Magurele, Romania

  8. Ocean Circulation Modeling for Aquatic Dispersion of Liquid Radioactive Effluents from Nuclear Power Plants

    SciTech Connect (OSTI)

    Chung, Y.G.; Lee, G.B.; Bang, S.Y. [Korea Electric Power Research Institute, 103-16 Munji-Dong, Yuseong-Gu, Daejeon 305-380 (Korea, Republic of); Choi, S.B.; Lee, S.U. [Korea Hydro and Nuclear Power Co., LTD, 167 Samseong-Dong, Gangnam-Gu, Seoul 135-791 (Korea, Republic of); Yoon, J.H. [Research Institute of Applied Physics, Kyushu University, 6-1 Kasuga-kouen, Kasuga, Fukuoka, 816-8580 (Japan); Nam, S.Y.; Lee, H.R. [GeoSystem Research Corporation, 306 Hanlim Human Town, 1-40 Geumjeong-Dong, Gunpo-City, Gyeonggi-Do 435-050 (Korea, Republic of)

    2006-07-01T23:59:59.000Z

    Recently, three-dimensional models have been used for aquatic dispersion of radioactive effluents in relation to nuclear power plant siting based on the Notice No. 2003-12 'Guideline for investigating and assessing hydrological and aquatic characteristics of nuclear facility site' of the Ministry of Science and Technology (MOST) in Korea. Several nuclear power plants have been under construction or planed, which are Shin-Kori Unit 1 and 2, Shin-Wolsong Unit 1 and 2, and Shin-Ulchin Unit 1 and 2. For assessing the aquatic dispersion of radionuclides released from the above nuclear power plants, it is necessary to know the coastal currents around sites which are affected by circulation of East Sea. In this study, a three dimensional hydrodynamic model for the circulation of the East Sea of Korea has been developed as the first phase, which is based on the RIAMOM (Research Institute of Applied Mechanics' Ocean Model, Kyushu University, Japan). The model uses the primitive equation with hydrostatic approximation, and uses Arakawa-B grid system horizontally and Z coordinate vertically. Model domain is 126.5 deg. E to 142.5 deg. E of east longitude and 33 deg. N and 52 deg. N of the north latitude. The space of the horizontal grid was 1/12 deg. to longitude and latitude direction and vertical level was divided to 20. This model uses Generalized Arakawa Scheme, Slant Advection, and Mode-Splitting Method. The input data were from JODC (Japan Oceanographic Data Center), KNFRDI (Korea National Fisheries Research and Development Institute), and ECMWF (European Center for Medium-Range Weather Forecasts). The modeling results are in fairly good agreement with schematic patterns of the surface circulation in the East Sea/Japan Sea. The local current model and aquatic dispersion model of the coastal region will be developed as the second phase. The oceanic dispersion experiments will be also carried out by using ARGO Drifter around a nuclear power plant site. (authors)

  9. International Environmental Modelling and Software Society (iEMSs) 2010 International Congress on Environmental Modelling and Software

    E-Print Network [OSTI]

    Boyer, Edmond

    ://www.iemss.org/iemss2010/index.php?n=Main.Proceedings Modelling and control of a hybrid renewable energy system to supply University, Tétouan, Morocco Abstract: Renewable energy sources are an "indigenous" environmental option. Hybrid plants can help in improving the economic and environmental sustainability of renewable energy

  10. International Environmental Modelling and Software Society (iEMSs) 2010 International Congress on Environmental Modelling and Software

    E-Print Network [OSTI]

    Boyer, Edmond

    of the rain- fall/pollutant relationship at the catchment scale for intelligent environmental decision support for such relationship grows with the size of drainage networks in urban catchments or with the water pollu- tion models fail to describe correctly the dynamic changes of the system for different rainfall events (e

  11. Nano-Continuum Modeling of a Nuclear Glass Specimen Altered for 25 Years

    SciTech Connect (OSTI)

    Steefel, Carl

    2014-01-06T23:59:59.000Z

    The purpose of this contribution is to report on preliminary nano-continuum scale modeling of nuclear waste glass corrosion. The focus of the modeling is an experiment involving a French glass SON68 specimen leached for 25 years in a granitic environment. In this report, we focus on capturing the nano-scale concentration profiles. We use a high resolution continuum model with a constant grid spacing of 1 nanometer to investigate the glass corrosion mechanisms.

  12. Nuclear Attenuation of high energy two-hadron system in the string model

    E-Print Network [OSTI]

    Akopov, N; Akopov, Z

    2007-01-01T23:59:59.000Z

    Nuclear attenuation of the two-hadron system is considered in the string model. The two-scale model and its improved version with two different choices of constituent formation time and sets of parameters obtained earlier for the single hadron attenuation, are used to describe available experimental data for the $z$-dependence of subleading hadron, whereas satisfactory agreement with the experimental data has been observed. A model prediction for $\

  13. Nuclear Attenuation of high energy two-hadron system in the string model

    E-Print Network [OSTI]

    N. Akopov; L. Grigoryan; Z. Akopov

    2006-05-11T23:59:59.000Z

    Nuclear attenuation of the two-hadron system is considered in the string model. The two-scale model and its improved version with two different choices of constituent formation time and sets of parameters obtained earlier for the single hadron attenuation, are used to describe available experimental data for the $z$-dependence of subleading hadron, whereas satisfactory agreement with the experimental data has been observed. A model prediction for $\

  14. Modelling Geospatial Application Databases using UML-based Repositories Aligned with International Standards in Geomatics

    E-Print Network [OSTI]

    Modelling Geospatial Application Databases using UML-based Repositories Aligned with International Abstract: This paper presents the result of recent work on the use of geospatial repositories to store and database concepts, a geospatial repository can be defined as a collection of (meta) data structured

  15. Global Tracking of Uncertain Nonlinear Cascaded Systems with Adaptive Internal Model1

    E-Print Network [OSTI]

    Sontag, Eduardo

    robust output regulation problem by dynamic state feedback control for the case where the exosystem regulation with uncertain exosystem by dynamic state feedback control. We have succeeded in developingGlobal Tracking of Uncertain Nonlinear Cascaded Systems with Adaptive Internal Model1 Zhiyong Chen

  16. MODELLING OF CONCRETE STRUCTURES AFFECTED BY INTERNAL SWELLING REACTIONS: COUPLINGS BETWEEN

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Page 1 MODELLING OF CONCRETE STRUCTURES AFFECTED BY INTERNAL SWELLING REACTIONS: COUPLINGS BETWEEN of the affected concrete that generally leads to cracking and decrease of its mechanical properties of the concrete works and structural integrity. To manage with considered suffering structures, it is necessary

  17. A Model for Kinetically Controlled Internal Phase Segregation During Aerosol Coagulation

    E-Print Network [OSTI]

    A Model for Kinetically Controlled Internal Phase Segregation During Aerosol Coagulation H size distribution. The dynamical behavior of such a system is presented. 1 Introduction The evolution). The GDE has been employed to characterize the behavior in time and space of the particle size distribution

  18. Application of an exact model matching technique to coupled-core nuclear reactor control

    SciTech Connect (OSTI)

    Tzafestas, S.G.; Chrysochoides, N.G.; Rokkos, K.

    1984-08-01T23:59:59.000Z

    In this Note the control problem of linearized coupled-core multivariable nuclear reactors is treated by using a recent exact model matching technique in the frequency domain. The case of state feedback control is first considered and then the results are used where only the output variables of the reactor are available for feedback. A numerical example of a three coupled-core nuclear reactor model with one delayed neutron group for each core and short neutron travel time between cores is included.

  19. Strategic Plan for Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)

    SciTech Connect (OSTI)

    Kimberlyn C. Mousseau

    2011-10-01T23:59:59.000Z

    The Nuclear Energy Computational Fluid Dynamics Advanced Modeling and Simulation (NE-CAMS) system is being developed at the Idaho National Laboratory (INL) in collaboration with Bettis Laboratory, Sandia National Laboratory (SNL), Argonne National Laboratory (ANL), Utah State University (USU), and other interested parties with the objective of developing and implementing a comprehensive and readily accessible data and information management system for computational fluid dynamics (CFD) verification and validation (V&V) in support of nuclear energy systems design and safety analysis. The two key objectives of the NE-CAMS effort are to identify, collect, assess, store and maintain high resolution and high quality experimental data and related expert knowledge (metadata) for use in CFD V&V assessments specific to the nuclear energy field and to establish a working relationship with the U.S. Nuclear Regulatory Commission (NRC) to develop a CFD V&V database, including benchmark cases, that addresses and supports the associated NRC regulations and policies on the use of CFD analysis. In particular, the NE-CAMS system will support the Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program, which aims to develop and deploy advanced modeling and simulation methods and computational tools for reliable numerical simulation of nuclear reactor systems for design and safety analysis. Primary NE-CAMS Elements There are four primary elements of the NE-CAMS knowledge base designed to support computer modeling and simulation in the nuclear energy arena as listed below. Element 1. The database will contain experimental data that can be used for CFD validation that is relevant to nuclear reactor and plant processes, particularly those important to the nuclear industry and the NRC. Element 2. Qualification standards for data evaluation and classification will be incorporated and applied such that validation data sets will result in well-defined, well-characterized data. Element 3. Standards will be established for the design and operation of experiments for the generation of new validation data sets that are to be submitted to NE-CAMS that addresses the completeness and characterization of the dataset. Element 4. Standards will be developed for performing verification and validation (V&V) to establish confidence levels in CFD analyses of nuclear reactor processes; such processes will be acceptable and recognized by both CFD experts and the NRC.

  20. Monitoring international nuclear activity

    E-Print Network [OSTI]

    Firestone, R.B.

    2006-01-01T23:59:59.000Z

    a database will allow existing FBI and LLNL collaborators tothis information to the FBI and LLNL. Intelligence is

  1. World nuclear fuel cycle requirements 1991

    SciTech Connect (OSTI)

    Not Available

    1991-10-10T23:59:59.000Z

    The nuclear fuel cycle consists of mining and milling uranium ore, processing the uranium into a form suitable for generating electricity, burning'' the fuel in nuclear reactors, and managing the resulting spent nuclear fuel. This report presents projections of domestic and foreign requirements for natural uranium and enrichment services as well as projections of discharges of spent nuclear fuel. These fuel cycle requirements are based on the forecasts of future commercial nuclear power capacity and generation published in a recent Energy Information Administration (EIA) report. Also included in this report are projections of the amount of spent fuel discharged at the end of each fuel cycle for each nuclear generating unit in the United States. The International Nuclear Model is used for calculating the projected nuclear fuel cycle requirements. 14 figs., 38 tabs.

  2. On the internal consistency of holographic dark energy models

    SciTech Connect (OSTI)

    Horvat, R, E-mail: horvat@lei3.irb.hr [Rudjer Boskovic Institute, POB 180, 10002 Zagreb (Croatia)] [Rudjer Boskovic Institute, POB 180, 10002 Zagreb (Croatia)

    2008-10-15T23:59:59.000Z

    Holographic dark energy (HDE) models, underpinned by an effective quantum field theory (QFT) with a manifest UV/IR connection, have become convincing candidates for providing an explanation of the dark energy in the universe. On the other hand, the maximum number of quantum states that a conventional QFT for a box of size L is capable of describing relates to those boxes which are on the brink of experiencing a sudden collapse to a black hole. Another restriction on the underlying QFT is that the UV cut-off, which cannot be chosen independently of the IR cut-off and therefore becomes a function of time in a cosmological setting, should stay the largest energy scale even in the standard cosmological epochs preceding a dark energy dominated one. We show that, irrespective of whether one deals with the saturated form of HDE or takes a certain degree of non-saturation in the past, the above restrictions cannot be met in a radiation dominated universe, an epoch in the history of the universe which is expected to be perfectly describable within conventional QFT.

  3. Fundamental problems of modeling the dynamics of internal gravity waves with applications to the Arctic Basin

    E-Print Network [OSTI]

    Vitaly V. Bulatov; Yuriy V. Vladimirov

    2012-06-26T23:59:59.000Z

    In this paper, we consider fundamental problems of the dynamics of internal gravity waves. We present analytical and numerical algorithms for calculating the wave fields for a set of values of the parameters, as observed in the ocean. We show that our mathematical models can describe the wave dynamics of the Arctic Basin, taking into account the actual physical characteristics of sea water, topography of its floor, etc. The numerical and analytical results show that the internal gravity waves have a significant effect on underwater sea objects in the Arctic Basin.

  4. International Perspective on Fukushima Accident

    Broader source: Energy.gov [DOE]

    Presenter: Miroslav Lipár, Head, Operational Safety Section, Department of Nuclear Safety and Security, International Atomic Energy Agency

  5. Modeling engine oil vaporization and transport of the oil vapor in the piston ring pack on internal combustion engines

    E-Print Network [OSTI]

    Cho, Yeunwoo, 1973-

    2004-01-01T23:59:59.000Z

    A model was developed to study engine oil vaporization and oil vapor transport in the piston ring pack of internal combustion engines. With the assumption that the multi-grade oil can be modeled as a compound of several ...

  6. Statistical Thermal Models in High-Energy Nuclear Physics

    E-Print Network [OSTI]

    Ludwik Turko

    2009-01-15T23:59:59.000Z

    An examination of thermal models leads to the important signature of the expected critical behavior of the hadronic matter. A presentation is mainly devoted to the final volume effects. Canonical suppression factor are calculated.

  7. Nuclear Reactor/Hydrogen Process Interface Including the HyPEP Model

    SciTech Connect (OSTI)

    Steven R. Sherman

    2007-05-01T23:59:59.000Z

    The Nuclear Reactor/Hydrogen Plant interface is the intermediate heat transport loop that will connect a very high temperature gas-cooled nuclear reactor (VHTR) to a thermochemical, high-temperature electrolysis, or hybrid hydrogen production plant. A prototype plant called the Next Generation Nuclear Plant (NGNP) is planned for construction and operation at the Idaho National Laboratory in the 2018-2021 timeframe, and will involve a VHTR, a high-temperature interface, and a hydrogen production plant. The interface is responsible for transporting high-temperature thermal energy from the nuclear reactor to the hydrogen production plant while protecting the nuclear plant from operational disturbances at the hydrogen plant. Development of the interface is occurring under the DOE Nuclear Hydrogen Initiative (NHI) and involves the study, design, and development of high-temperature heat exchangers, heat transport systems, materials, safety, and integrated system models. Research and development work on the system interface began in 2004 and is expected to continue at least until the start of construction of an engineering-scale demonstration plant.

  8. Modelling the Electron Beam Welding of Nuclear Reactor Pressure Vessel Steel

    E-Print Network [OSTI]

    Cambridge, University of

    Modelling the Electron Beam Welding of Nuclear Reactor Pressure Vessel Steel Christopher J. Duffy fabrication of thick-section steel for critical components such as reactor pressure vessels. Electron beam weld tests performed by Rolls-Royce and The Welding Institute of SA 508 Grade 3 and SA 508 Grade 4N

  9. A Network Model and Computational Approach Mo Supply Chain for Nuclear Medicine

    E-Print Network [OSTI]

    Nagurney, Anna

    A Network Model and Computational Approach for the 99 Mo Supply Chain for Nuclear Medicine Ladimer S. Nagurney1 and Anna Nagurney2 1Department of Electrical and Computer Engineering University University of Massachusetts - Amherst, Massachusetts 01003 Fall 2011 Joint Meeting Of The New England

  10. Perspective on Advances in Resonance-Region Nuclear Modeling and Opportunities for Future Research

    SciTech Connect (OSTI)

    Dunn, Michael E [ORNL; Larson, Nancy M [ORNL; Derrien, Herve [ORNL; Leal, Luiz C [ORNL

    2007-01-01T23:59:59.000Z

    The advent of high-fidelity radiation-transport modeling capabilities, coupled with the need to analyze complex nuclear systems, has served to emphasize the importance of high-precision cross section data, including the associated covariance information. Due to the complex nature of resonance-region interactions, cross section data cannot be calculated directly from theory; rather, high-precision resonance-region cross section measurements must be made at facilities such as the Oak Ridge Electron Linear Accelerator (ORELA) at Oak Ridge National Laboratory (ORNL), Geel Electron Linear Accelerator (GELINA), Rensselaer Polytechnic Institute (RPI). To extract accurate cross section data from these measurements, detailed nuclear modeling of the measured data is performed to parameterize the cross section behavior in the resonance range. The objective of this paper is to highlight recent advances in resonance-region nuclear modeling with particular emphasis on the covariance analysis capabilities. Opportunities for future research are identified in an effort to stimulate further advances in the state of the art nuclear modeling capabilities.

  11. Proceedings of the 1993 international conference on nuclear waste management and environmental remediation. Volume 3: Environmental remediation and environmental management issues

    SciTech Connect (OSTI)

    Baschwitz, R.; Kohout, R.; Marek, J.; Richter, P.I.; Slate, S.C. [eds.

    1993-12-31T23:59:59.000Z

    This conference was held in 1993 in Prague, Czech Republic to provide a forum for exchange of state-of-the-art information on radioactive waste management. Papers are divided into the following sections: Low/Intermediate level waste disposal from an international viewpoint; Solid waste volume reduction, treatment and packaging experience; Design of integrated systems for management of nuclear wastes; Mixed waste (hazardous and radioactive) treatment and disposal; Advanced low/intermediate level waste conditioning technologies including incineration; National programs for low/intermediate waste management; Low/Intermediate waste characterization, assay, and tracking systems; Disposal site characterization and performance assessment; Radioactive waste management and practices in developing countries; Waste management from unconventional (e.g. VVER) nuclear power reactors; Waste minimization, avoidance and recycling in nuclear power plants; Liquid waste treatment processes and experience; Low/Intermediate waste storage facilities--design and experience; Low/Intermediate waste forms and acceptance criteria for disposal; Management of non-standard or accident waste; and Quality assurance and control in nuclear waste management. Individual papers have been processed separately for inclusion in the appropriate data bases.

  12. Strategic Plan for Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)

    SciTech Connect (OSTI)

    Rich Johnson; Kimberlyn C. Mousseau; Hyung Lee

    2011-09-01T23:59:59.000Z

    NE-KAMS knowledge base will assist computational analysts, physics model developers, experimentalists, nuclear reactor designers, and federal regulators by: (1) Establishing accepted standards, requirements and best practices for V&V and UQ of computational models and simulations, (2) Establishing accepted standards and procedures for qualifying and classifying experimental and numerical benchmark data, (3) Providing readily accessible databases for nuclear energy related experimental and numerical benchmark data that can be used in V&V assessments and computational methods development, (4) Providing a searchable knowledge base of information, documents and data on V&V and UQ, and (5) Providing web-enabled applications, tools and utilities for V&V and UQ activities, data assessment and processing, and information and data searches. From its inception, NE-KAMS will directly support nuclear energy research, development and demonstration programs within the U.S. Department of Energy (DOE), including the Consortium for Advanced Simulation of Light Water Reactors (CASL), the Nuclear Energy Advanced Modeling and Simulation (NEAMS), the Light Water Reactor Sustainability (LWRS), the Small Modular Reactors (SMR), and the Next Generation Nuclear Power Plant (NGNP) programs. These programs all involve computational modeling and simulation (M&S) of nuclear reactor systems, components and processes, and it is envisioned that NE-KAMS will help to coordinate and facilitate collaboration and sharing of resources and expertise for V&V and UQ across these programs. In addition, from the outset, NE-KAMS will support the use of computational M&S in the nuclear industry by developing guidelines and recommended practices aimed at quantifying the uncertainty and assessing the applicability of existing analysis models and methods. The NE-KAMS effort will initially focus on supporting the use of computational fluid dynamics (CFD) and thermal hydraulics (T/H) analysis for M&S of nuclear reactor systems, components and processes, and will later expand to include materials, fuel system performance and other areas of M&S as time and funding allow.

  13. Transient modeling of thermionic space nuclear power systems 

    E-Print Network [OSTI]

    Berge, Francoise M

    1991-01-01T23:59:59.000Z

    be activated or disabled. The reactor kinetics model itself can be disabled so that only the thermal-hydraulic model is solved. Five types of reactivity feed- back mechanisms are implemented in CENTAR: programmed reactivity, fuel tempera- ture feedback... do not include the reactivity control. The power can be controlled as a function of the transient time. The pump head, on the other hand, can be specified to be constant and/or controlled as a function of the transient time and/or any temperature...

  14. International Atomic Energy Agency specialists meeting on experience in ageing, maintenance, and modernization of instrumentation and control systems for improving nuclear power plant availability

    SciTech Connect (OSTI)

    Not Available

    1993-10-01T23:59:59.000Z

    This report presents the proceedings of the Specialist`s Meeting on Experience in Aging, Maintenance and Modernization of Instrumentation and Control Systems for Improving Nuclear Power Plant Availability that was held at the Ramada Inn in Rockville, Maryland on May 5--7, 1993. The Meeting was presented in cooperation with the Electric Power Research Institute, Oak Ridge National Laboratory and the International Atomic Energy Agency. There were approximately 65 participants from 13 countries at the Meeting. Individual reports have been cataloged separately.

  15. Report on the American Nuclear Society International Topical Meeting: {open_quotes}The safety, status, and future of non-commercial reactors and irradiation Facilities{close_quotes}

    SciTech Connect (OSTI)

    Silver, E.G. [Oak Ridge National Laboratory, TN (United States)

    1991-01-01T23:59:59.000Z

    The American Nuclear Society`s International Topical Meeting, The Safety, Status, and Future of Non-Commercial Reactors and Irradiation Facilities, also known as SAFOR 90, was held in Boise, Idaho, September 30 to October 4, 1990. In 19 half-day sessions, 102 papers were presented which covered operating research reactors, production reactors, the use of reactors for training and research, probabilistic risk assessments applied to research reactors, plans for new facilities, and new fuels and reactor types. A special session on space reactor safety was also presented. 11 refs., 1 tab.

  16. Interfaces between transport and geologic disposal systems for high-level radioactive wastes and spent nuclear fuel: A new international guidance document

    SciTech Connect (OSTI)

    Pope, R.B. [Oak Ridge National Lab., TN (United States); Baekelandt, L. [Organisme National des Dechets Radioactifs et des Matieres Fissiles, Brussels (Belgium); Hoorelbeke, J.M. [CEA Agence Nationale pour la Gestion des Dechets Radioactifes (ANDRA), 75 - Paris (France); Han, K.W.; Pollog, T. [International Atomic Energy Agency, Vienna (Austria); Blackman, D. [Department of Transport, London (United Kingdom); Villagran, J.E. [Villagran Nuclear Consulting Services, Toronto, ON (Canada)

    1994-04-01T23:59:59.000Z

    An International Atomic Energy Agency (IAEA) Technical Document (TECDOC) has been developed and will be published by the IAEA. The TECDOC addresses the interfaces between the transport and geologic disposal systems for, high-level waste (HLW) and spent nuclear fuel (SNF). The document is intended to define and assist in discussing, at both the domestic and the international level, regulatory, technical, administrative, and institutional interfaces associated with HLW and SNF transport and disposal systems; it identifies and discusses the interfaces and interface requirements between the HLW and SNF, the waste transport system used for carriage of the waste to the disposal facility, and the HLW/SNF disposal facility. It provides definitions and explanations of terms; discusses systems, interfaces and interface requirements; addresses alternative strategies (single-purpose packages and multipurpose packages) and how interfaces are affected by the strategies; and provides a tabular summary of the requirements.

  17. A Statistical Model for Generating a Population of Unclassified Objects and Radiation Signatures Spanning Nuclear Threats

    SciTech Connect (OSTI)

    Nelson, K; Sokkappa, P

    2008-10-29T23:59:59.000Z

    This report describes an approach for generating a simulated population of plausible nuclear threat radiation signatures spanning a range of variability that could be encountered by radiation detection systems. In this approach, we develop a statistical model for generating random instances of smuggled nuclear material. The model is based on physics principles and bounding cases rather than on intelligence information or actual threat device designs. For this initial stage of work, we focus on random models using fissile material and do not address scenarios using non-fissile materials. The model has several uses. It may be used as a component in a radiation detection system performance simulation to generate threat samples for injection studies. It may also be used to generate a threat population to be used for training classification algorithms. In addition, we intend to use this model to generate an unclassified 'benchmark' threat population that can be openly shared with other organizations, including vendors, for use in radiation detection systems performance studies and algorithm development and evaluation activities. We assume that a quantity of fissile material is being smuggled into the country for final assembly and that shielding may have been placed around the fissile material. In terms of radiation signature, a nuclear weapon is basically a quantity of fissile material surrounded by various layers of shielding. Thus, our model of smuggled material is expected to span the space of potential nuclear weapon signatures as well. For computational efficiency, we use a generic 1-dimensional spherical model consisting of a fissile material core surrounded by various layers of shielding. The shielding layers and their configuration are defined such that the model can represent the potential range of attenuation and scattering that might occur. The materials in each layer and the associated parameters are selected from probability distributions that span the range of possibilities. Once an object is generated, its radiation signature is calculated using a 1-dimensional deterministic transport code. Objects that do not make sense based on physics principles or other constraints are rejected. Thus, the model can be used to generate a population of spectral signatures that spans a large space, including smuggled nuclear material and nuclear weapons.

  18. The $E_{\\rm p}$ - $E_{\\rm iso}$ relation and the internal shock model

    E-Print Network [OSTI]

    Mochkovitch, R

    2014-01-01T23:59:59.000Z

    The validity of the $E_{\\rm p}$ - $E_{\\rm iso}$ correlation in gamma-ray bursts and the possibility of explaining the prompt emission with internal shocks are highly debated questions. We study whether the $E_{\\rm p}$ - $E_{\\rm iso}$ correlation can be reproduced if internal shocks are indeed responsible for the prompt emission, or conversely, if the correlation can be used to constrain the internal shock scenario. We developed a toy model where internal shocks are limited to the collision of only two shells. Synthetic burst populations were constructed for various distributions of the model parameters, such as the injected power in the relativistic outflow, the average Lorentz factor, and its typical contrast between the shells. These parameters can be independent or linked by various relations. Synthetic $E_{\\rm p}$ - $E_{\\rm iso}$ diagrams are obtained in the different cases and compared with the observed correlation. The reference observed correlation is the one defined by the BAT6 sample, a sample of Swi...

  19. Model calculations of nuclear data for biologically-important elements

    SciTech Connect (OSTI)

    Chadwick, M.B.; Blann, M.; Reffo, G. [Lawrence Livermore National Lab., CA (United States); Young, P.G. [Los Alamos National Lab., NM (United States)

    1994-05-01T23:59:59.000Z

    We describe calculations of neutron-induced reactions on carbon and oxygen for incident energies up to 70 MeV, the relevant clinical energy in radiation neutron therapy. Our calculations using the FKK-GNASH, GNASH, and ALICE codes are compared with experimental measurements, and their usefulness for modeling reactions on biologically-important elements is assessed.

  20. An international land-biosphere model benchmarking activity for the IPCC Fifth Assessment Report (AR5)

    SciTech Connect (OSTI)

    Hoffman, Forrest M [ORNL; Randerson, James T [ORNL; Thornton, Peter E [ORNL; Bonan, Gordon [National Center for Atmospheric Research (NCAR); Erickson III, David J [ORNL; Fung, Inez [University of California, Berkeley

    2009-12-01T23:59:59.000Z

    The need to capture important climate feedbacks in general circulation models (GCMs) has resulted in efforts to include atmospheric chemistry and land and ocean biogeochemistry into the next generation of production climate models, called Earth System Models (ESMs). While many terrestrial and ocean carbon models have been coupled to GCMs, recent work has shown that such models can yield a wide range of results (Friedlingstein et al., 2006). This work suggests that a more rigorous set of global offline and partially coupled experiments, along with detailed analyses of processes and comparisons with measurements, are needed. The Carbon-Land Model Intercomparison Project (C-LAMP) was designed to meet this need by providing a simulation protocol and model performance metrics based upon comparisons against best-available satellite- and ground-based measurements (Hoffman et al., 2007). Recently, a similar effort in Europe, called the International Land Model Benchmark (ILAMB) Project, was begun to assess the performance of European land surface models. These two projects will now serve as prototypes for a proposed international land-biosphere model benchmarking activity for those models participating in the IPCC Fifth Assessment Report (AR5). Initially used for model validation for terrestrial biogeochemistry models in the NCAR Community Land Model (CLM), C-LAMP incorporates a simulation protocol for both offline and partially coupled simulations using a prescribed historical trajectory of atmospheric CO2 concentrations. Models are confronted with data through comparisons against AmeriFlux site measurements, MODIS satellite observations, NOAA Globalview flask records, TRANSCOM inversions, and Free Air CO2 Enrichment (FACE) site measurements. Both sets of experiments have been performed using two different terrestrial biogeochemistry modules coupled to the CLM version 3 in the Community Climate System Model version 3 (CCSM3): the CASA model of Fung, et al., and the carbon-nitrogen (CN) model of Thornton. Comparisons of the CLM3 offline results against observational datasets have been performed and are described in Randerson et al. (2009). CLM version 4 has been evaluated using C-LAMP, showing improvement in many of the metrics. Efforts are now underway to initiate a Nitrogen-Land Model Intercomparison Project (N-LAMP) to better constrain the effects of the nitrogen cycle in biosphere models. Presented will be new results from C-LAMP for CLM4, initial N-LAMP developments, and the proposed land-biosphere model benchmarking activity.

  1. Trip report: European Communities 1989 International Conference on Decommissioning of Nuclear Installations, Brussels, Belgium, October 24-27, 1989

    SciTech Connect (OSTI)

    Rankin, W.N.

    1989-01-01T23:59:59.000Z

    The European community is conducting research on the decommissioning of nuclear installations. The prime objective is to develop effective techniques to ensure the protection of man and his environment against the potential hazards of nuclear installations that have been shut down. The results of the 1979--1983 research program were presented in a conference held in Luxembourg. This program was primarily concerned with decommissioning nuclear power plants. The 1984--1988 program was extended to all types of nuclear installations. Fuel fabrication, enrichment and reprocessing plants, and research and development facilities having fulfilled their useful purposes are also awaiting decommissioning. This Program has produced numerous scientific and technical achievements. Great progress has in particular been achieved in the reduction of metal waste arising from decommissioning, due to advances in areas such as the development of aggressive decontamination procedures and of techniques for melting and recycling low-level radioactive waste metal.

  2. Cardiovascular Engineering: An International Journal, Vol. 4, No. 1, March 2004 ( C 2004) Modeling Cerebral Blood Flow Control During Posture

    E-Print Network [OSTI]

    Olufsen, Mette Sofie

    of our mathematical model and control mechanisms development, we will show vali- dation results of our flow regulation; lumped parameter model; model validation. INTRODUCTION The understanding of shortCardiovascular Engineering: An International Journal, Vol. 4, No. 1, March 2004 ( C 2004) Modeling

  3. Internal efficiency of InGaN light-emitting diodes: Beyond a quasiequilibrium model

    SciTech Connect (OSTI)

    Chow, Weng W.; Crawford, Mary H.; Tsao, Jeffrey Y.; Kneissl, Michael

    2010-01-01T23:59:59.000Z

    We propose a model to better investigate InGaN light-emitting diode (LED) internal efficiency by extending beyond the usual total carrier density rate equation approach. To illustrate its capability, the model is applied to study intrinsic performance differences between violet and green LEDs. The simulations show performance differences, at different current densities and temperatures, arising from variations in spontaneous emission and heat loss rates. By tracking the momentum-resolved carrier populations, these rate changes are, in turn, traced to differences in bandstructure and plasma heating. The latter leads to carrier distributions that deviate from the quasiequilibrium ones at lattice temperature.

  4. Modeling to Support Groundwater Contaminant Boundaries for the Shoal Underground Nuclear Test

    SciTech Connect (OSTI)

    K. Pohlmann; G. Pohll; J. Chapman; A. Hassan; R. Carroll; C. Shirley

    2004-03-01T23:59:59.000Z

    Groundwater flow and radionuclide transport at the Shoal underground nuclear test are characterized using three-dimensional numerical models, based on site-specific hydrologic data. The objective of this modeling is to provide the flow and transport models needed to develop a contaminant boundary defining the extent of radionuclide-contaminated groundwater at the site throughout 1,000 years at a prescribed level of confidence. This boundary will then be used to manage the Project Shoal Area for the protection of the public and the environment.

  5. Modeling to Support Groundwater Contaminant Boundaries for the Shoal Underground Nuclear Test

    SciTech Connect (OSTI)

    K. Pohlmann; G. Pohll; J. Chapman; A. Hassan; R. Carroll; C. Shirley

    2004-03-01T23:59:59.000Z

    The purpose of this work is to characterize groundwater flow and contaminant transport at the Shoal underground nuclear test through numerical modeling using site-specific hydrologic data. The ultimate objective is the development of a contaminant boundary, a model-predicted perimeter defining the extent of radionuclide-contaminated groundwater from the underground test throughout 1,000 years at a prescribed level of confidence. This boundary will be developed using the numerical models described here, after they are approved for that purpose by DOE and NDEP.

  6. NUCLEAR CHEMISTRY DIV. ANNUAL REPORT 1980-81

    E-Print Network [OSTI]

    Cerny, J.

    2010-01-01T23:59:59.000Z

    15th Bormio Winter Meeting on Nuclear Physics," Bormio,International Winter Meeting on Nuclear Physics," Bormio,

  7. Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS) Code Verification and Validation Data Standards and Requirements: Fluid Dynamics Version 1.0

    SciTech Connect (OSTI)

    Greg Weirs; Hyung Lee

    2011-09-01T23:59:59.000Z

    V&V and UQ are the primary means to assess the accuracy and reliability of M&S and, hence, to establish confidence in M&S. Though other industries are establishing standards and requirements for the performance of V&V and UQ, at present, the nuclear industry has not established such standards or requirements. However, the nuclear industry is beginning to recognize that such standards are needed and that the resources needed to support V&V and UQ will be very significant. In fact, no single organization has sufficient resources or expertise required to organize, conduct and maintain a comprehensive V&V and UQ program. What is needed is a systematic and standardized approach to establish and provide V&V and UQ resources at a national or even international level, with a consortium of partners from government, academia and industry. Specifically, what is needed is a structured and cost-effective knowledge base that collects, evaluates and stores verification and validation data, and shows how it can be used to perform V&V and UQ, leveraging collaboration and sharing of resources to support existing engineering and licensing procedures as well as science-based V&V and UQ processes. The Nuclear Energy Knowledge base for Advanced Modeling and Simulation (NE-KAMS) is being developed at the Idaho National Laboratory in conjunction with Bettis Laboratory, Sandia National Laboratories, Argonne National Laboratory, Utah State University and others with the objective of establishing a comprehensive and web-accessible knowledge base to provide V&V and UQ resources for M&S for nuclear reactor design, analysis and licensing. The knowledge base will serve as an important resource for technical exchange and collaboration that will enable credible and reliable computational models and simulations for application to nuclear power. NE-KAMS will serve as a valuable resource for the nuclear industry, academia, the national laboratories, the U.S. Nuclear Regulatory Commission (NRC) and the public and will help ensure the safe, economical and reliable operation of existing and future nuclear reactors.

  8. Impact of rainstorm and runoff modeling on predicted consequences of atmospheric releases from nuclear reactor accidents

    SciTech Connect (OSTI)

    Ritchie, L.T.; Brown, W.D.; Wayland, J.R.

    1980-05-01T23:59:59.000Z

    A general temperate latitude cyclonic rainstorm model is presented which describes the effects of washout and runoff on consequences of atmospheric releases of radioactive material from potential nuclear reactor accidents. The model treats the temporal and spatial variability of precipitation processes. Predicted air and ground concentrations of radioactive material and resultant health consequences for the new model are compared to those of the original WASH-1400 model under invariant meteorological conditions and for realistic weather events using observed meteorological sequences. For a specific accident under a particular set of meteorological conditions, the new model can give significantly different results from those predicted by the WASH-1400 model, but the aggregate consequences produced for a large number of meteorological conditions are similar.

  9. Modeling of reciprocating internal combustion engines for power generation and heat recovery

    SciTech Connect (OSTI)

    Yun, Kyung Tae; Cho, Heejin; Luck, Rogelio; Mago, Pedro J.

    2013-02-01T23:59:59.000Z

    This paper presents a power generation and heat recovery model for reciprocating internal combustion engines (ICEs). The purpose of the proposed model is to provide realistic estimates of performance/efficiency maps for both electrical power output and useful thermal output for various capacities of engines for use in a preliminary CHP design/simulation process. The proposed model will serve as an alternative to constant engine efficiencies or empirical efficiency curves commonly used in the current literature for simulations of CHP systems. The engine performance/efficiency calculation algorithm has been coded to a publicly distributed FORTRAN Dynamic Link Library (DLL), and a user friendly tool has been developed using Visual Basic programming. Simulation results using the proposed model are validated against manufacturer’s technical data.

  10. Distinguished rheological models in the framework of a thermodynamical internal variable theory

    E-Print Network [OSTI]

    Asszonyi, Cs; Ván, P

    2014-01-01T23:59:59.000Z

    We present and analyze a thermodynamical theory of rheology with single internal variable. The universality of the model is ensured as long as the mesoscopic and/or microscopic background processes satisfy the applied thermodynamical principles, which are the second law, the basic balances and the existence of an additional-tensorial-state variable. The resulting model, which we suggest to call the Kluitenberg-Verh\\'as body, is the Poynting-Thomson-Zener body with an additional inertial element, or, in other words, is the extension of Jeffreys model to solids. We argue that this Kluitenberg-Verh\\'as body is the natural thermodynamical building block of rheology. An important feature of the presented methodology is that nontrivial inequality-type restrictions arise for the four parameters of the model. We compare these conditions and other aspects to those of other known thermodynamical approaches, like Extended Irreversible Thermodynamics or the original theory of Kluitenberg.

  11. Catalysinganenergyrevolution Nuclear Failures

    E-Print Network [OSTI]

    Laughlin, Robert B.

    extraction, fuel manufacture and management of spent fuel and waste. Currently, CEA is a large FrenchCatalysinganenergyrevolution France's Nuclear Failures The great illusion of nuclear energy greenpeace.org #12;Contents 2 Greenpeace International France's Nuclear Failures The French nuclear industry

  12. NARAC Modeling During the Response to the Fukushima Dai-ichi Nuclear Power Plant Emergency

    SciTech Connect (OSTI)

    Sugiyama, G; Nasstrom, J S; Probanz, B; Foster, K T; Simpson, M; Vogt, P; Aluzzi, F; Dillon, M; Homann, S

    2012-02-14T23:59:59.000Z

    This paper summarizes the activities of the National Atmospheric Release Advisory Center (NARAC) during the Fukushima Dai-ichi nuclear power plant crisis. NARAC provided a wide range of products and analyses as part of its support including: (1) Daily Japanese weather forecasts and hypothetical release (generic source term) dispersion predictions to provide situational awareness and inform planning for U.S. measurement data collection and field operations; (2) Estimates of potential dose in Japan for hypothetical scenarios developed by the Nuclear Regulatory Commission (NRC) to inform federal government considerations of possible actions that might be needed to protect U.S. citizens in Japan; (3) Estimates of possible plume arrival times and dose for U.S. locations; and (4) Plume model refinement and source estimation based on meteorological analyses and available field data. The Department of Energy/National Nuclear Security Administration (DOE/NNSA) deployed personnel to Japan and stood up 'home team' assets across the DOE complex to aid in assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. The DOE Nuclear Incident Team (NIT) coordinated response activities, while DOE personnel provided predictive modeling, air and ground monitoring, sample collection, laboratory analysis, and data assessment and interpretation. DOE deployed the Aerial Measuring System (AMS), Radiological Assistance Program (RAP) personnel, and the Consequence Management Response Team (CMRT) to Japan. DOE/NNSA home team assets included the Consequence Management Home Team (CMHT); National Atmospheric Release Advisory Center (NARAC); Radiation Emergency Assistance Center/Training Site (REAC/TS); and Radiological Triage. NARAC was activated by the DOE/NNSA on March 11, shortly after the Tohoku earthquake and tsunami occurred. The center remained on active operations through late May when DOE ended its deployment to Japan. Over 32 NARAC staff members, supplemented by other LLNL scientists, invested over 5000 person-hours of time and generated over 300 analyses and predictions.

  13. Workshop materials from the 2nd international training course on physical protection of nuclear facilities and materials, Module 13

    SciTech Connect (OSTI)

    Martin, F. P. [ed.

    1980-04-01T23:59:59.000Z

    This course is intended for representatives of countries where nuclear power is being developed and whose responsibilities include the preparation of regulation and the design and evaluation of physical protection systems. This is the second of two volumes; the first volume is SAND-79-1090. (DLC)

  14. Benchmarking GEANT4 nuclear models for hadron therapy with 95 MeV/nucleon carbon ions

    E-Print Network [OSTI]

    J. Dudouet; D. Cussol; D. Durand; M. Labalme

    2014-05-30T23:59:59.000Z

    In carbon-therapy, the interaction of the incoming beam with human tissues may lead to the production of a large amount of nuclear fragments and secondary light particles. An accurate estimation of the biological dose deposited into the tumor and the surrounding healthy tissues thus requires sophisticated simulation tools based on nuclear reaction models. The validity of such models requires intensive comparisons with as many sets of experimental data as possible. Up to now, a rather limited set of double di erential carbon fragmentation cross sections have been measured in the energy range used in hadrontherapy (up to 400 MeV/A). However, new data have been recently obtained at intermediate energy (95 MeV/A). The aim of this work is to compare the reaction models embedded in the GEANT4 Monte Carlo toolkit with these new data. The strengths and weaknesses of each tested model, i.e. G4BinaryLightIonReaction, G4QMDReaction and INCL++, coupled to two di fferent de-excitation models, i.e. the generalized evaporation model and the Fermi break-up are discussed.

  15. SOCIAL MODELING IN ASSESSEMENT OF A STATE’S PROPENSITY FOR NUCLEAR PROLIFERATION

    SciTech Connect (OSTI)

    Dalton, Angela C.; Whitney, Paul D.; Coles, Garill A.; Brothers, Alan J.

    2011-07-17T23:59:59.000Z

    This paper presents approach for assessing a State’s propensity for nuclear weapons proliferation using social modeling. We supported this modeling by first reviewing primarily literature by social scientists on factors related to the propensity of a State to proliferation and by leveraging existing relevant data compiled by social scientists. We performed a number of validation tests on our model including one that incorporates use of benchmark data defining the proliferation status of countries in the years between 1945 and 2000. We exercise the BN model against a number of country cases representing different perceived levels of proliferation risk. We also describe how the BN model could be further refined to be a proliferation assessment tool for decision making.

  16. Proceedings of the Numerical Modeling for Underground Nuclear Test Monitoring Symposium

    SciTech Connect (OSTI)

    Taylor, S.R.; Kamm, J.R. [eds.

    1993-11-01T23:59:59.000Z

    The purpose of the meeting was to discuss the state-of-the-art in numerical simulations of nuclear explosion phenomenology with applications to test ban monitoring. We focused on the uniqueness of model fits to data, the measurement and characterization of material response models, advanced modeling techniques, and applications of modeling to monitoring problems. The second goal of the symposium was to establish a dialogue between seismologists and explosion-source code calculators. The meeting was divided into five main sessions: explosion source phenomenology, material response modeling, numerical simulations, the seismic source, and phenomenology from near source to far field. We feel the symposium reached many of its goals. Individual papers submitted at the conference are indexed separately on the data base.

  17. A Theory of Impedance Control based on Internal Model Uncertainty Djordje Mitrovic, Stefan Klanke, Adrian Haith and Sethu Vijayakumar

    E-Print Network [OSTI]

    Vijayakumar, Sethu

    and principled theory of impedance control in the nervous system. Here we develop a powerful computational modelA Theory of Impedance Control based on Internal Model Uncertainty Djordje Mitrovic, Stefan Klanke-valid computational model of impedance control derived from first principles have been proposed so far. Many

  18. Quark-Meson Coupling Model, Nuclear Matter Constraints and Neutron Star Properties

    E-Print Network [OSTI]

    Whittenbury, D L; Thomas, A W; Tsushima, K; Stone, J R

    2013-01-01T23:59:59.000Z

    We explore the equation of state for nuclear matter in the quark-meson coupling model, including full Fock terms. The comparison with phenomenological constraints can be used to restrict the few additional parameters appearing in the Fock terms which are not present at Hartree level. Because the model is based upon the in-medium modification of the quark structure of the bound hadrons, it can be applied without additional parameters to include hyperons and to calculate the equation of state of dense matter in beta-equilibrium. This leads naturally to a study of the properties of neutron stars, including their maximum mass, their radii and density profiles.

  19. Validity of pair truncation of the nuclear shell model in {sup 46}Ca

    SciTech Connect (OSTI)

    Lei, Y.; Xu, Z. Y. [Department of Physics, Shanghai Jiao Tong University, Shanghai 200240 (China); Zhao, Y. M. [Department of Physics, Shanghai Jiao Tong University, Shanghai 200240 (China); Center of Theoretical Nuclear Physics, National Laboratory of Heavy Ion Accelerator, Lanzhou 730000 (China); CCAST, World Laboratory, Post Office Box 8730, Beijing 100080 (China); Arima, A. [Department of Physics, Shanghai Jiao Tong University, Shanghai 200240 (China); Science Museum, Japan Science Foundation, 2-1 Kitanomaru-koen, Chiyoda-ku, Tokyo 102-0091 (Japan)

    2009-12-15T23:59:59.000Z

    We study the validity of pair truncation of the nuclear shell model by using the semimagic nucleus {sup 46}Ca. We present low-lying states and their E2 transition rates based on both nucleon pair approximation (NPA) and exact shell-model (SM) calculations. We also calculate overlaps between wave functions of low-lying states calculated by using the NPA and those calculated by using the SM. Our calculated results show a remarkable agreement between the NPA results and the SM results, although the NPA is a drastic truncation of the SM.

  20. Calculating Nuclear Power Plant Vulnerability Using Integrated Geometry and Event/Fault-Tree Models

    SciTech Connect (OSTI)

    Peplow, Douglas E. [Oak Ridge National Laboratory (United States); Sulfredge, C. David [Oak Ridge National Laboratory (United States); Sanders, Robert L. [Oak Ridge National Laboratory (United States); Morris, Robert H. [Oak Ridge National Laboratory (United States); Hann, Todd A. [Defense Threat Reduction Agency (United States)

    2004-01-15T23:59:59.000Z

    Since the events of September 11, 2001, the vulnerability of nuclear power plants to terrorist attacks has become a national concern. The results of vulnerability analysis are greatly influenced by the computational approaches used. Standard approximations used in fault-tree analysis are not applicable for attacks, where high component failure probabilities are expected; two methods that do work with high failure probabilities are presented. Different blast modeling approaches can also affect the end results. Modeling the structural details of facility buildings and the geometric layout of components within the buildings is required to yield meaningful results.

  1. Parton distribution functions and nuclear EMC effect in a statistical model

    E-Print Network [OSTI]

    Lijing Shao; Yunhua Zhang; Bo-Qiang Ma

    2010-08-11T23:59:59.000Z

    A new and simple statistical approach is performed to calculate the parton distribution functions (PDFs) of the nucleon in terms of light-front kinematic variables. Analytic expressions of x-dependent PDFs are obtained in the whole x region. And thereafter, we treat the temperature T as a parameter of the atomic number A to explain the nuclear EMC effect in the region $x \\in [0.2, 0.7]$. We give the predictions of PDF ratios, and they are very different from those by other models, thus experiments aiming at measuring PDF ratios are suggested to provide a discrimination of different models.

  2. FRAMEWORK AND APPLICATION FOR MODELING CONTROL ROOM CREW PERFORMANCE AT NUCLEAR POWER PLANTS

    SciTech Connect (OSTI)

    Ronald L Boring; David I Gertman; Tuan Q Tran; Brian F Gore

    2008-09-01T23:59:59.000Z

    This paper summarizes an emerging project regarding the utilization of high-fidelity MIDAS simulations for visualizing and modeling control room crew performance at nuclear power plants. The key envisioned uses for MIDAS-based control room simulations are: (i) the estimation of human error associated with advanced control room equipment and configurations, (ii) the investigative determination of contributory cognitive factors for risk significant scenarios involving control room operating crews, and (iii) the certification of reduced staffing levels in advanced control rooms. It is proposed that MIDAS serves as a key component for the effective modeling of cognition, elements of situation awareness, and risk associated with human performance in next generation control rooms.

  3. REACTOR PHYSICS MODELING OF SPENT RESEARCH REACTOR FUEL FOR TECHNICAL NUCLEAR FORENSICS

    SciTech Connect (OSTI)

    Nichols, T.; Beals, D.; Sternat, M.

    2011-07-18T23:59:59.000Z

    Technical nuclear forensics (TNF) refers to the collection, analysis and evaluation of pre- and post-detonation radiological or nuclear materials, devices, and/or debris. TNF is an integral component, complementing traditional forensics and investigative work, to help enable the attribution of discovered radiological or nuclear material. Research is needed to improve the capabilities of TNF. One research area of interest is determining the isotopic signatures of research reactors. Research reactors are a potential source of both radiological and nuclear material. Research reactors are often the least safeguarded type of reactor; they vary greatly in size, fuel type, enrichment, power, and burn-up. Many research reactors are fueled with highly-enriched uranium (HEU), up to {approx}93% {sup 235}U, which could potentially be used as weapons material. All of them have significant amounts of radiological material with which a radioactive dispersal device (RDD) could be built. Therefore, the ability to attribute if material originated from or was produced in a specific research reactor is an important tool in providing for the security of the United States. Currently there are approximately 237 operating research reactors worldwide, another 12 are in temporary shutdown and 224 research reactors are reported as shut down. Little is currently known about the isotopic signatures of spent research reactor fuel. An effort is underway at Savannah River National Laboratory (SRNL) to analyze spent research reactor fuel to determine these signatures. Computer models, using reactor physics codes, are being compared to the measured analytes in the spent fuel. This allows for improving the reactor physics codes in modeling research reactors for the purpose of nuclear forensics. Currently the Oak Ridge Research reactor (ORR) is being modeled and fuel samples are being analyzed for comparison. Samples of an ORR spent fuel assembly were taken by SRNL for analytical and radiochemical analysis. The fuel assembly was modeled using MONTEBURNS(MCNP5/ ORIGEN2.2) and MCNPX/CINDER90. The results from the models have been compared to each other and to the measured data.

  4. The Social and Ethical Aspects of Nuclear Waste

    E-Print Network [OSTI]

    Marshall, Alan

    2005-01-01T23:59:59.000Z

    siting a high-level nuclear waste repository at Hanford,Eds. ), Public reactions to nuclear waste. Durham, NC: DukeInternational politics of nuclear waste. London: Macmillan.

  5. Dynamic Agent Based Modeling Using Bayesian Framework for Addressing Intelligence Adaptive Nuclear Nonproliferation Analysis 

    E-Print Network [OSTI]

    Elmore, Royal A

    2014-10-03T23:59:59.000Z

    International Safeguards Fellowship for financial support. Finally, thanks to my mother and father for their encouragement and to my wife for her patience and love. vi NOMENCLATURE ABM Agent Based Modeling API Application Programmer Interface BANE...-8. Uranium enrichment precursors and post material management ................ 62 Figure 3-9. A pre-BANE specific to general reprocessing section with evidence......... 63 Figure 3-10. Plutonium reprocessing options...

  6. RSMASS-D nuclear thermal propulsion and bimodal system mass models

    SciTech Connect (OSTI)

    King, D.B. [DSWA/FC, Thermionic Evaluation Facility 801 University Blvd. SE Albuquerque, New Mexico (United States); Marshall, A.C. [DSWA/FC, Thermionic Evaluation Facility 801 University Blvd. SE Albuquerque, New Mexico (United States)

    1997-01-01T23:59:59.000Z

    Two relatively simple models have been developed to estimate reactor, radiation shield, and balance of system masses for a particle bed reactor (PBR) nuclear thermal propulsion concept and a cermet-core power and propulsion (bimodal) concept. The approach was based on the methodology developed for the RSMASS-D models. The RSMASS-D approach for the reactor and shield sub-systems uses a combination of simple equations derived from reactor physics and other fundamental considerations along with tabulations of data from more detailed neutron and gamma transport theory computations. Relatively simple models are used to estimate the masses of other subsystem components of the nuclear propulsion and bimodal systems. Other subsystem components include instrumentation and control (I&C), boom, safety systems, radiator, thermoelectrics, heat pipes, and nozzle. The user of these models can vary basic design parameters within an allowed range to achieve a parameter choice which yields a minimum mass for the operational conditions of interest. Estimated system masses are presented for a range of reactor power levels for propulsion for the PBR propulsion concept and for both electrical power and propulsion for the cermet-core bimodal concept. The estimated reactor system masses agree with mass predictions from detailed calculations with xx percent for both models. {copyright} {ital 1997 American Institute of Physics.}

  7. RSMASS-D nuclear thermal propulsion and bimodal system mass models

    SciTech Connect (OSTI)

    King, Donald B.; Marshall, Albert C. [DSWA/FC, Thermionic Evaluation Facility 801 University Blvd. SE Albuquerque, New Mexico (United States); DSWA/FC, Thermionic Evaluation Facility 801 University Blvd. SE Albuquerque, New Mexico (United States)

    1997-01-10T23:59:59.000Z

    Two relatively simple models have been developed to estimate reactor, radiation shield, and balance of system masses for a particle bed reactor (PBR) nuclear thermal propulsion concept and a cermet-core power and propulsion (bimodal) concept. The approach was based on the methodology developed for the RSMASS-D models. The RSMASS-D approach for the reactor and shield sub-systems uses a combination of simple equations derived from reactor physics and other fundamental considerations along with tabulations of data from more detailed neutron and gamma transport theory computations. Relatively simple models are used to estimate the masses of other subsystem components of the nuclear propulsion and bimodal systems. Other subsystem components include instrumentation and control (I and C), boom, safety systems, radiator, thermoelectrics, heat pipes, and nozzle. The user of these models can vary basic design parameters within an allowed range to achieve a parameter choice which yields a minimum mass for the operational conditions of interest. Estimated system masses are presented for a range of reactor power levels for propulsion for the PBR propulsion concept and for both electrical power and propulsion for the cermet-core bimodal concept. The estimated reactor system masses agree with mass predictions from detailed calculations with xx percent for both models.

  8. Semantic modeling for theory clarification: The realist vs liberal international relations perspective

    SciTech Connect (OSTI)

    Bray, O.H. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); [Univ. of New Mexico, Albuquerque, NM (United States). Political Science Dept.

    1994-04-01T23:59:59.000Z

    This paper describes a natural language based, semantic information modeling methodology and explores its use and value in clarifying and comparing political science theories and frameworks. As an example, the paper uses this methodology to clarify and compare some of the basic concepts and relationships in the realist (e.g. Waltz) and the liberal (e.g. Rosenau) paradigms for international relations. The methodology can provide three types of benefits: (1) it can clarify and make explicit exactly what is meant by a concept; (2) it can often identify unanticipated implications and consequence of concepts and relationships; and (3) it can help in identifying and operationalizing testable hypotheses.

  9. Proceedings of the 2. MIT international conference on the next generation of nuclear power technology. Final report

    SciTech Connect (OSTI)

    NONE

    1993-12-31T23:59:59.000Z

    The goal of the conference was to try to attract a variety of points of view from well-informed people to debate issues concerning nuclear power. Hopefully from that process a better understanding of what one should be doing will emerge. In organizing the conference lessons learned from the previous one were applied. A continuous effort was made to see to it that the arguments for the alternatives to nuclear power were given abundant time for presentation. This is ultimately because nuclear power is going to have to compete with all of the energy technologies. Thus, in discussing energy strategy all of the alternatives must be considered in a reasonable fashion. The structure the conference used has seven sessions. The first six led up to the final session which was concerned with what the future nuclear power strategy should be. Each session focused upon a question concerning the future. None of these questions has a unique correct answer. Rather, topics are addressed where reasonable people can disagree. In order to state some of the important arguments for each session`s question, the combination of a keynote paper followed by a respondent was used. The respondent`s paper is not necessarily included to be a rebuttal to the keynote; but rather, it was recognized that two people will look at a complex question with different shadings. Through those two papers the intention was to get out the most important arguments affecting the question for the session. The purpose of the papers was to set the stage for about an hour of discussion. The real product of this conference was that discussion.

  10. THE STRUCTURAL CHEMISTRY OF MOLYBDENUM IN MODEL HIGH LEVEL NUCLEAR WASTE GLASSES, INVESTIGATED BY MO K-EDGE X-RAY ABSORPTION

    E-Print Network [OSTI]

    Sheffield, University of

    THE STRUCTURAL CHEMISTRY OF MOLYBDENUM IN MODEL HIGH LEVEL NUCLEAR WASTE GLASSES, INVESTIGATED of molybdenum in model UK high level nuclear waste glasses was investigated by X-ray Absorption Spectroscopy (XAS). Molybdenum K-edge XAS data were acquired from several inactive simulant high level nuclear waste

  11. Dynamic nuclear renography kinetic analysis: Four-compartment model for assessing kidney function

    SciTech Connect (OSTI)

    Raswan, T. R., E-mail: tara.raissa@gmail.com; Haryanto, F., E-mail: tara.raissa@gmail.com [Department of Physics, Nuclear Physics and Biophysics Research Group, Institut Teknologi Bandung, Bandung (Indonesia)

    2014-09-30T23:59:59.000Z

    Dynamic nuclear renography method produces TACs of kidneys and bladder. Multiple TACs data can be further analyzed to obtain the overview of urinary system's condition. Tracer kinetic analysis was performed using four-compartment models. The system's model consist of four irreversible compartment with four transport constants (k1, k2, k3 and k4). The mathematical expressions of tracer's distributions is fitted to experimental data (TACs) resulting in model constants. This transport constants represent the urinary system behavior, and later can be used for analyzing system's condition. Different intervals of kinetics parameter are clearly shown by abnormal system with respect to the normal one. Furthermore, the system with delayed uptake has 82% lower uptake parameters (k1 and k2) than normal one. Meanwhile, the system with prolonged clearance time has its kinetics parameters k3 or k4 lower than the others. This model is promising for quantitatively describe urinary system's function especially if supplied with more data.

  12. Gamma and neutron detection modeling in the nuclear detection figure of merit (NDFOM) portal

    SciTech Connect (OSTI)

    Stroud, Phillip D [Los Alamos National Laboratory; Saeger, Kevin J [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    The Nuclear Detection Figure Of Merit (NDFOM) portal is a database of objects and algorithms for evaluating the performance of radiation detectors to detect nuclear material. This paper describes the algorithms used to model the physics and mathematics of radiation detection. As a first-principles end-to-end analysis system, it starts with the representation of the gamma and neutron spectral fluxes, which are computed with the particle and radiation transport code MCNPX. The gamma spectra emitted by uranium, plutonium, and several other materials of interest are described. The impact of shielding and other intervening material is computed by the method of build-up factors. The interaction of radiation with the detector material is computed by a detector response function approach. The construction of detector response function matrices based on MCNPX simulation runs is described in detail. Neutron fluxes are represented in a three group formulation to treat differences in detector sensitivities to thermal, epithermal, and fast neutrons.

  13. Assessment of a pressurizer spray valve faulty opening transient at Asco Nuclear Power Plant with RELAP5/MOD2. International Agreement Report

    SciTech Connect (OSTI)

    Reventos, F.; Baptista, J.S.; Navas, A.P.; Moreno, P. [Asociacion Nuclear Asco, Barcelona (Spain)

    1993-12-01T23:59:59.000Z

    The Asociacion Nuclear Asco has prepared a model of Asco NPP using RELAP5/MOD2. This model, which include thermalhydraulics, kinetics and protection and controls, has been qualified in previous calculations of several actual plant transients. One of the transients of the qualification process is a ``Pressurizer spray valve faulty opening`` presented in this report. It consists in a primary coolant depressurization that causes the reactor trip by overtemperature and later on the actuation of the safety injection. The results are in close agreement with plant data.

  14. Source Term Estimation of Radioxenon Released from the Fukushima Dai-ichi Nuclear Reactors Using Measured Air Concentrations and Atmospheric Transport Modeling

    SciTech Connect (OSTI)

    Eslinger, Paul W. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Biegalski, S. [Univ. of Texas at Austin, TX (United States); Bowyer, Ted W. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Cooper, Matthew W. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Haas, Derek A. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Hayes, James C. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Hoffman, Ian [Radiation Protection Bureau, Health Canada, Ottawa, ON (Canada); Korpach, E. [Radiation Protection Bureau, Health Canada, Ottawa, ON (Canada); Yi, Jing [Radiation Protection Bureau, Health Canada, Ottawa, ON (Canada); Miley, Harry S. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Rishel, Jeremy P. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Ungar, R. Kurt [Radiation Protection Bureau, Health Canada, Ottawa, ON (Canada); White, Brian [Radiation Protection Bureau, Health Canada, Ottawa, ON (Canada); Woods, Vincent T. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

    2014-01-01T23:59:59.000Z

    Systems designed to monitor airborne radionuclides released from underground nuclear explosions detected radioactive fallout from the Fukushima Daiichi nuclear accident in March 2011. Atmospheric transport modeling (ATM) of plumes of noble gases and particulates were performed soon after the accident to determine plausible detection locations of any radioactive releases to the atmosphere. We combine sampling data from multiple International Modeling System (IMS) locations in a new way to estimate the magnitude and time sequence of the releases. Dilution factors from the modeled plume at five different detection locations were combined with 57 atmospheric concentration measurements of 133-Xe taken from March 18 to March 23 to estimate the source term. This approach estimates that 59% of the 1.24×1019 Bq of 133-Xe present in the reactors at the time of the earthquake was released to the atmosphere over a three day period. Source term estimates from combinations of detection sites have lower spread than estimates based on measurements at single detection sites. Sensitivity cases based on data from four or more detection locations bound the source term between 35% and 255% of available xenon inventory.

  15. Asymmetric nuclear matter in a parity doublet model with hidden local symmetry

    E-Print Network [OSTI]

    Yuichi Motohiro; Youngman Kim; Masayasu Harada

    2015-05-11T23:59:59.000Z

    We construct a model to describe dense hadronic matter at zero and finite temperature, based on the parity doublet model of DeTar and Kunihiro, with including the iso-singlet scalar meson $\\sigma$ as well as $\\rho$ and $\\omega$ mesons. We show that, by including a six-point interaction of $\\sigma$ meson, the model reasonably reproduces the properties of the normal nuclear matter with the chiral invariant nucleon mass $m_0$ in the range from $500~{\\rm MeV}$ to $900~{\\rm MeV}$. Furthermore, we study the phase diagram based on the model, which shows that the value of the chiral condensate drops at the liquid-gas phase transition point and at the chiral phase transition point. We also study asymmetric nuclear matter and find that the first order phase transition for the liquid-gas phase transition disappears in asymmetric matter and that the critical density for the chiral phase transition at non-zero density becomes smaller for larger asymmetry.

  16. Asymmetric nuclear matter in a parity doublet model with hidden local symmetry

    E-Print Network [OSTI]

    Motohiro, Yuichi; Harada, Masayasu

    2015-01-01T23:59:59.000Z

    We construct a model to describe dense hadronic matter at zero and finite temperature, based on the parity doublet model of DeTar and Kunihiro, with including the iso-singlet scalar meson $\\sigma$ as well as $\\rho$ and $\\omega$ mesons. We show that, by including a six-point interaction of $\\sigma$ meson, the model reasonably reproduces the properties of the normal nuclear matter with the chiral invariant nucleon mass $m_0$ in the range from $500~{\\rm MeV}$ to $900~{\\rm MeV}$. Furthermore, we study the phase diagram based on the model, which shows that the value of the chiral condensate drops at the liquid-gas phase transition point and at the chiral phase transition point. We also study asymmetric nuclear matter and find that the first order phase transition for the liquid-gas phase transition disappears in asymmetric matter and that the critical density for the chiral phase transition at non-zero density becomes smaller for larger asymmetry.

  17. High Level Requirements for the Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)

    SciTech Connect (OSTI)

    Rich Johnson; Hyung Lee; Kimberlyn C. Mousseau

    2011-09-01T23:59:59.000Z

    The US Department of Energy, Office of Nuclear Energy (DOE-NE), has been tasked with the important mission of ensuring that nuclear energy remains a compelling and viable energy source in the U.S. The motivations behind this mission include cost-effectively meeting the expected increases in the power needs of the country, reducing carbon emissions and reducing dependence on foreign energy sources. In the near term, to ensure that nuclear power remains a key element of U.S. energy strategy and portfolio, the DOE-NE will be working with the nuclear industry to support safe and efficient operations of existing nuclear power plants. In the long term, to meet the increasing energy needs of the U.S., the DOE-NE will be investing in research and development (R&D) and working in concert with the nuclear industry to build and deploy new, safer and more efficient nuclear power plants. The safe and efficient operations of existing nuclear power plants and designing, licensing and deploying new reactor designs, however, will require focused R&D programs as well as the extensive use and leveraging of advanced modeling and simulation (M&S). M&S will play a key role in ensuring safe and efficient operations of existing and new nuclear reactors. The DOE-NE has been actively developing and promoting the use of advanced M&S in reactor design and analysis through its R&D programs, e.g., the Nuclear Energy Advanced Modeling and Simulation (NEAMS) and Consortium for Advanced Simulation of Light Water Reactors (CASL) programs. Also, nuclear reactor vendors are already using CFD and CSM, for design, analysis, and licensing. However, these M&S tools cannot be used with confidence for nuclear reactor applications unless accompanied and supported by verification and validation (V&V) and uncertainty quantification (UQ) processes and procedures which provide quantitative measures of uncertainty for specific applications. The Nuclear Energy Knowledge base for Advanced Modeling and Simulation (NE-KAMS) is being developed at the Idaho National Laboratory in conjunction with Bettis Laboratory, Sandia National Laboratories, Argonne National Laboratory, Utah State University and others with the objective of establishing a comprehensive and web-accessible knowledge base that will provide technical services and resources for V&V and UQ of M&S in nuclear energy sciences and engineering. The knowledge base will serve as an important resource for technical exchange and collaboration that will enable credible and reliable computational models and simulations for application to nuclear reactor design, analysis and licensing. NE-KAMS will serve as a valuable resource for the nuclear industry, academia, the national laboratories, the U.S. Nuclear Regulatory Commission (NRC) and the public and will help ensure the safe, economical and reliable operation of existing and future nuclear reactors. From its inception, NE-KAMS will directly support nuclear energy research, development and demonstration programs within the U.S. Department of Energy (DOE), including the CASL, NEAMS, Light Water Reactor Sustainability (LWRS), Small Modular Reactors (SMR), and Next Generation Nuclear Power Plant (NGNP) programs. These programs all involve M&S of nuclear reactor systems, components and processes, and it is envisioned that NE-KAMS will help to coordinate and facilitate collaboration and sharing of resources and expertise for V&V and UQ across these programs.

  18. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA + MC 2013) La Cit des Sciences et de l'Industrie, Paris, France, October 27-31, 2013

    E-Print Network [OSTI]

    Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA are expected to operate at temperatures exceeding 350°C, and possibly approaching 750°C, there is a genuine recoil atom is transferred, through interatomic interactions, to the local environment of the recoil atom

  19. Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in UO2 +/- x: Implications for nuclear fuel performance modeling

    SciTech Connect (OSTI)

    Giovanni Pastore; Michael R. Tonks; Derek R. Gaston; Richard L. Williamson; David Andrs; Richard Martineau

    2014-03-01T23:59:59.000Z

    Based on density functional theory (DFT) and empirical potential calculations, the diffusivity of fission gas atoms (Xe) in UO2 nuclear fuel has been calculated for a range of non-stoichiometry (i.e. UO2x), under both out-of-pile (no irradiation) and in-pile (irradiation) conditions. This was achieved by first deriving expressions for the activation energy that account for the type of trap site that the fission gas atoms occupy, which includes the corresponding type of mobile cluster, the charge state of these defects and the chemistry acting as boundary condition. In the next step DFT calculations were used to estimate migration barriers and internal energy contributions to the thermodynamic properties and calculations based on empirical potentials were used to estimate defect formation and migration entropies (i.e. pre-exponentials). The diffusivities calculated for out-of-pile conditions as function of the UO2x nonstoichiometrywere used to validate the accuracy of the diffusion models and the DFT calculations against available experimental data. The Xe diffusivity is predicted to depend strongly on the UO2x non-stoichiometry due to a combination of changes in the preferred Xe trap site and in the concentration of uranium vacancies enabling Xe diffusion, which is consistent with experiments. After establishing the validity of the modeling approach, it was used for studying Xe diffusion under in-pile conditions, for which experimental data is very scarce. The radiation-enhanced Xe diffusivity is compared to existing empirical models. Finally, the predicted fission gas diffusion rates were implemented in the BISON fuel performance code and fission gas release from a Risø fuel rod irradiation experiment was simulated. 2014 Elsevier B.V. All rights

  20. PIA - Savannah River Nuclear Solutions Electronic Safeguards...

    Energy Savers [EERE]

    System (E3S) PIA - Savannah River Nuclear Solutions Electronic Safeguards Security System (E3S) More Documents & Publications PIA - 10th International Nuclear Graphite...

  1. Achievements and deficiencies of nuclear models used for the design of spallation sources

    SciTech Connect (OSTI)

    Leray, S.; Boudard, A.; David, J. C.; Ducret, J. E.; Kezzar, K.; Le Gentil, E.; Lemaire, S.; Volant, C.; Yariv, Y. [CEA/Saclay, DAPNIA/SPhN, 91191 Gif-sur-Yvette, Cedex (France)

    2006-07-01T23:59:59.000Z

    High-energy transport codes are used in a large number of domains as spallation neutron sources or ADS design, space or medical applications. In these codes, nuclear models describing spallation reactions generate the necessary elementary cross-sections and characteristics of all the reaction products. During the last years, new high-quality experimental data have been collected leading to the development of more reliable spallation models, as the INCL4-ABLA combination of intranuclear cascade and de-excitation models, now available in MCNPX. However, remaining deficiencies have been identified, which can be of important consequences for applications, for instance in the prediction of damage. They generally originate from not well understood physics mechanisms. To solve these problems more constraining experiments are now being carried out, which allow a deeper understanding of the reaction mechanisms, in particular for the de-excitation stage. Recent improvements of INCL4 are presented. Impact for applications is discussed. (authors)

  2. A Computational Model of Limb Impedance Control Based on Principles of Internal Model Uncertainty

    E-Print Network [OSTI]

    Vijayakumar, Sethu

    of Informatics, University of Edinburgh, Edinburgh, United Kingdom, 2 ATR Computational Neuroscience Laboratories uncertainties, along with energy and accuracy demands. The insights from this computational model could be used. This is an effortless task, however if suddenly a seemingly random wind gust perturbs the umbrella, you will typically

  3. Building International Emergency Management Systems | National...

    National Nuclear Security Administration (NNSA)

    Building International Emergency Management Systems | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  4. SUMO, System performance assessment for a high-level nuclear waste repository: Mathematical models

    SciTech Connect (OSTI)

    Eslinger, P.W.; Miley, T.B.; Engel, D.W.; Chamberlain, P.J. II

    1992-09-01T23:59:59.000Z

    Following completion of the preliminary risk assessment of the potential Yucca Mountain Site by Pacific Northwest Laboratory (PNL) in 1988, the Office of Civilian Radioactive Waste Management (OCRWM) of the US Department of Energy (DOE) requested the Performance Assessment Scientific Support (PASS) Program at PNL to develop an integrated system model and computer code that provides performance and risk assessment analysis capabilities for a potential high-level nuclear waste repository. The system model that has been developed addresses the cumulative radionuclide release criteria established by the US Environmental Protection Agency (EPA) and estimates population risks in terms of dose to humans. The system model embodied in the SUMO (System Unsaturated Model) code will also allow benchmarking of other models being developed for the Yucca Mountain Project. The system model has three natural divisions: (1) source term, (2) far-field transport, and (3) dose to humans. This document gives a detailed description of the mathematics of each of these three divisions. Each of the governing equations employed is based on modeling assumptions that are widely accepted within the scientific community.

  5. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC).

    SciTech Connect (OSTI)

    Schultz, Peter Andrew

    2011-12-01T23:59:59.000Z

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V&V) is required throughout the system to establish evidence-based metrics for the level of confidence in M&S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V&V challenge at the subcontinuum scale, an approach to incorporate V&V concepts into subcontinuum scale modeling and simulation (M&S), and a plan to incrementally incorporate effective V&V into subcontinuum scale M&S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

  6. Model for the conversion of nuclear waste melter feed to glass

    SciTech Connect (OSTI)

    Pokorny, Richard; Hrma, Pavel R.

    2014-02-01T23:59:59.000Z

    The rate of batch-to-glass conversion is a primary concern for the vitrification of nuclear waste, as it directly influences the life cycle of the cleanup process. This study describes the development of an advanced model of the cold cap, which augments the previous model by further developments on the structure and the dynamics of the foam layer. The foam layer on the bottom of the cold cap consists of the primary foam, cavities, and the secondary foam, and forms an interface through which the heat is transferred to the cold cap. Other model enhancements include the behavior of intermediate crystalline phases and the dissolution of quartz particles. The model relates the melting rate to feed properties and melter conditions, such as the molten glass temperature, foaminess of the feed, or the heat fraction supplied to the cold cap from the plenum space. The model correctly predicts a 25% increase in melting rate when changing the alumina source in the melter feed from Al(OH)3 to AlO(OH). It is expected that this model will be incorporated in the full glass melter model as its integral component.

  7. A new coal-permeability model: Internal swelling stress and fracture-matrix interaction

    SciTech Connect (OSTI)

    Liu, H.H.; Rutqvist, J.

    2009-10-01T23:59:59.000Z

    We have developed a new coal-permeability model for uniaxial strain and constant confining stress conditions. The model is unique in that it explicitly considers fracture-matrix interaction during coal deformation processes and is based on a newly proposed internal-swelling stress concept. This concept is used to account for the impact of matrix swelling (or shrinkage) on fracture-aperture changes resulting from partial separation of matrix blocks by fractures that do not completely cut through the whole matrix. The proposed permeability model is evaluated with data from three Valencia Canyon coalbed wells in the San Juan Basin, where increased permeability has been observed during CH{sub 4} gas production, as well as with published data from laboratory tests. Model results are generally in good agreement with observed permeability changes. The importance of fracture-matrix interaction in determining coal permeability, demonstrated in this work using relatively simple stress conditions, underscores the need for a dual-continuum (fracture and matrix) mechanical approach to rigorously capture coal-deformation processes under complex stress conditions, as well as the coupled flow and transport processes in coal seams.

  8. Role of small lead-cooled fast reactors for international deployment in worldwide sustainable nuclear energy supply.

    SciTech Connect (OSTI)

    Sienicki, J. J.; Wade, D. C.; Moisseytsev, A.; Nuclear Engineering Division

    2008-01-01T23:59:59.000Z

    Most recently, the global nuclear energy partnership (GNEP) has identified, as one of its key objectives, the development and demonstration of concepts for small and medium-sized reactors (SMRs) that can be globally deployed while assuring a high level of proliferation resistance. Lead-cooled systems offer several key advantages in meeting these goals. The small lead-cooled fast reactor concept known as the small secure transportable autonomous reactor (SSTAR) has been under ongoing development as part of the US advanced nuclear energy systems programs. Meeting future worldwide projected energy demands during this century (e.g., 1000 to 2000 GWe by 2050) in a sustainable manner while maintaining CO2 emissions at or below today's level will require massive deployments of nuclear reactors in non-fuel cycle states as well as fuel cycle states. The projected energy demands of non-fuel cycle states will not be met solely through the deployment of Light Water Reactors (LWRs) in those states without using up the world's resources of fissile material (e.g., known plus speculative virgin uranium resources = 15 million tonnes). The present U.S. policy is focused upon domestic deployment of large-scale LWRs and sodium-cooled fast spectrum Advanced Burner Reactors (ABRs) working in a symbiotic relationship that burns existing fissile material while destroying the actinides which are generated. Other major nuclear nations are carrying out the development and deployment of SFR breeders as witness the planning for SFR breeder deployments in France, Japan, China, India, and Russia. Small (less that 300 MWe) and medium (300 to 700 MWe) size reactors are better suited to the growing economies and infrastructures of many non-fuel cycle states and developing nations. For those deployments, fast reactor converters which are fissile self-sufficient by creating as much fissile material as they consume are preferred to breeders that create more fissile material than they consume. Thus, there is a need for small and medium size fast reactors in non-fuel cycle states operating in a converter mode as well as large sodium-cooled fast breeders in fuel cycle states. Desired attributes for exportable small fast reactors include: proliferation resistance features such as restricted access to fuel; long core life further restricting access by reducing or eliminating the need for refueling; restricted potential to be misused in a breeding mode; fuel form that is unattractive in the safeguards sense; and a conversion ratio of unity to self-generate as much fissile material as is consumed. Desired attributes for exportable small reactor deployments in developing nations and remote sites also include: a small power level to match the smaller demand of towns or sites that are off-grid or on immature local grids; low enough cost to be economically competitive with alternative energy sources available to developing nation customers (e.g. diesel generators in remote locations); readily transported and assembled from transportable modules; simple to operate and highly reliable reducing plant operating staff requirements; as well as high reliability and passive safety reducing the number of accident initiators and need for safety systems as well as reducing the size of the exclusion and emergency planning zones. The Lead-Cooled Fast Reactor (LFR) has the desired attributes. An example of a small exportable LFR concept is the 20 MWe (45 MWt) Small Secure Transportable Autonomous Reactor (SSTAR) incorporating proliferation resistance, fissile selfsufficiency, autonomous load following, a high degree of passive safety, and supercritical carbon dioxide Brayton cycle energy conversion for high plant efficiency and improved economic competitiveness.

  9. Priorities for modeling biological processes in climates altered by nuclear war

    SciTech Connect (OSTI)

    Detling, J.K.; Kercher, J.R.; Post, W.M.; Cowles, S.W.; Harwell, M.A.

    1987-01-01T23:59:59.000Z

    This document describes research that has been accomplished or currently models the effects of reduced light and temperature on terrestrial systems. We shall divide the systems to be studied into cultivated lands and uncultivated lands. The cultivated class consists of monoculture systems in which the individual plants belong to the same age and size class. The systems in the uncultivated class consist of uneven age, multi-species assemblies of interacting plants and animals. The uncultivated class ranges from minimally managed systems, e.g., rangelands and some forests, to completely unmanaged wildlands. For the cultivated case, the variable of concern is the annual yield of the crop under consideration. The models should be able to estimate percent yield loss as a function of reductions of light and temperature. The models should be accurate for the range of environments predicted for the growing season immediately following or during which the hypothetical nuclear exchange occurs. The models should be able to estimate yield loss in any subsequent year for which climatic conditions still differ significantly from normal. For the uncultivated case, the modelling program needs to be able to predict the effects on individual plants much the same as in the cultivated case; but in addition, the modelling program will have the task of estimating the effect that these changes in individual organisms will have at higher levels of organization, i.e., on populations, communities, and regional distributions of species. 25 refs., 1 tab.

  10. Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI

    SciTech Connect (OSTI)

    Suffield, Sarah R.; Fort, James A.; Adkins, Harold E.; Cuta, Judith M.; Collins, Brian A.; Siciliano, Edward R.

    2012-10-01T23:59:59.000Z

    As part of the Used Fuel Disposition Campaign of the Department of Energy (DOE), visual inspections and temperature measurements were performed on two storage modules in the Calvert Cliffs Nuclear Power Station’s Independent Spent Fuel Storage Installation (ISFSI). Detailed thermal models models were developed to obtain realistic temperature predictions for actual storage systems, in contrast to conservative and bounding design basis calculations.

  11. Modeling the effects of maintenance on the degradation of a water-feeding turbo-pump of nuclear power plant

    E-Print Network [OSTI]

    Boyer, Edmond

    of the components, which derives from the particular `life' (failures, shocks, preventive maintenance actionsModeling the effects of maintenance on the degradation of a water-feeding turbo-pump of nuclear Abstract: This work addresses the modeling of the effects of maintenance on the degradation of an electric

  12. Speciation by monobrachial centric fusions: A test of the model using nuclear DNA sequences from the bat genus Rhogeessa

    E-Print Network [OSTI]

    Hillis, David

    Speciation by monobrachial centric fusions: A test of the model using nuclear DNA sequences from chromosomal rearrangements in a model termed speciation by monobrachial centric fusions. Recently a more comprehensive test of speciation by monobrachial centric fusions in Rhogeessa. Our analysis

  13. The modeling of the nuclear composition measurement performance of the Non-Imaging CHErenkov Array (NICHE)

    E-Print Network [OSTI]

    Krizmanic, John; Sokolsky, Pierre

    2013-01-01T23:59:59.000Z

    In its initial deployment, the Non-Imaging CHErenkov Array (NICHE)will measure the flux and nuclear composition of cosmic rays from below 10^16 eV to 10^18 eV by using measurements of the amplitude and time-spread of the air-shower Cherenkov signal to achieve a robust event-by-event measurement of Xmax and energy. NICHE will have sufficient area and angular acceptance to have significant overlap with TA/TALE, within which NICHE is located, to allow for energy cross-calibration. In order to quantify NICHE's ability to measure the cosmic ray nuclear composition, 4-component composition models were constructed based upon a poly-gonato model of J. Hoerandel using simulated Xmax distributions of the composite composition as a function of energy. These composition distributions were then unfolded into individual components via an analysis technique that included NICHE's simulated Xmax and energy resolution performance as a function of energy as well as the effects of finite event statistics. Details of the construc...

  14. Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

    SciTech Connect (OSTI)

    Michael V. Glazoff

    2013-08-01T23:59:59.000Z

    Zirconium-based alloys Zircaloy-2 and Zircaloy-4 are widely used in the nuclear industry as cladding materials for light water reactor (LWR) fuels. These materials display a very good combination of properties such as low neutron absorption, creep behavior, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion and/or oxidation, especially in the case of Zircaloy-4. However, over the last couple of years, in the post-Fukushima Daiichi world, energetic efforts have been undertaken to improve fuel clad oxidation resistance during off-normal temperature excursions. Efforts have also been made to improve upon the already achieved levels of mechanical behavior and reduce hydrogen uptake. In order to facilitate the development of such novel materials, it is very important to achieve not only engineering control, but also a scientific understanding of the underlying material degradation mechanisms, both in working conditions and in storage of used nuclear fuel. This report strives to contribute to these efforts by constructing the thermodynamic models of both alloys; constructing of the respective phase diagrams, and oxidation mechanisms. A special emphasis was placed upon the role of zirconium suboxides in hydrogen uptake reduction and the atomic mechanisms of oxidation. To that end, computational thermodynamics calculations were conducted concurrently with first-principles atomistic modeling.

  15. Environmental Aspects of Advanced Nuclear Fuel Cycles: Parametric Modeling and Preliminary Analysis 

    E-Print Network [OSTI]

    Yancey, Kristina D.

    2010-07-14T23:59:59.000Z

    and reprocessing spent fuel must be incorporated into the nuclear fuel cycle to achieve sustainability....

  16. Delineating role of ubiquitination on nuclear factor-kappa B pathway by a computational modeling approach

    SciTech Connect (OSTI)

    Lee, Jungsul; Choi, Kyungsun [Cell Signaling and BioImaging Laboratory, Department of Bio and Brain Engineering, KAIST, Daejeon 305-701 (Korea, Republic of)] [Cell Signaling and BioImaging Laboratory, Department of Bio and Brain Engineering, KAIST, Daejeon 305-701 (Korea, Republic of); Choi, Chulhee, E-mail: cchoi@kaist.ac.kr [Cell Signaling and BioImaging Laboratory, Department of Bio and Brain Engineering, KAIST, Daejeon 305-701 (Korea, Republic of) [Cell Signaling and BioImaging Laboratory, Department of Bio and Brain Engineering, KAIST, Daejeon 305-701 (Korea, Republic of); Graduate School of Medical Science and Engineering, KAIST, Daejeon 305-701 (Korea, Republic of); KI for Bio Century, KAIST, Daejeon 305-701 (Korea, Republic of)

    2010-01-01T23:59:59.000Z

    Mutant ubiquitin found in neurodegenerative diseases has been thought to hamper activation of transcription factor nuclear factor-kappa B (NF-{kappa}B) by inhibiting ubiquitin-proteasome system (UPS). It has been reported that ubiquitin also is involved in signal transduction in an UPS-independent manner. We used a modeling and simulation approach to delineate the roles of ubiquitin on NF-{kappa}B activation. Inhibition of proteasome complex increased maximal activation of IKK mainly by decreasing the UPS efficiency. On the contrary, mutant ubiquitin decreased maximal activity of IKK. Computational modeling showed that the inhibition effect of mutant ubiquitin is mainly attributed to decreased activity of UPS-independent function of ubiquitin. Collectively, our results suggest that mutant ubiquitin affects NF-{kappa}B activation in an UPS-independent manner.

  17. Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels

    SciTech Connect (OSTI)

    McDeavitt, Sean; Shao, Lin; Tsvetkov, Pavel; Wirth, Brian; Kennedy, Rory

    2014-04-07T23:59:59.000Z

    Advanced fast reactor systems being developed under the DOE's Advanced Fuel Cycle Initiative are designed to destroy TRU isotopes generated in existing and future nuclear energy systems. Over the past 40 years, multiple experiments and demonstrations have been completed using U-Zr, U-Pu-Zr, U-Mo and other metal alloys. As a result, multiple empirical and semi-empirical relationships have been established to develop empirical performance modeling codes. many mechamistic questions about fission as mobility, bubble coalescience, and gas release have been answered through industrial experience, reearch, and empirical understanding. The advent of modern computational materials science, however, opens new doors of development such that physics-based multi-scale models may be developed to enable a new generation of predictive fuel performance codes that are not limited by empiricism.

  18. A methodology for experimentally verifying simulation models for distribution transformer internal faults

    E-Print Network [OSTI]

    Palmer-Buckle, Peter

    1999-01-01T23:59:59.000Z

    Internal winding faults comprise 70-80% of modem transformer breakdown. In this era of deregulation, this phenomenon is likely to increase since loading transformers to their optimum capacity is becoming normal practice. These internal faults result...

  19. Proceedings of the Third International Conference on Modeling, Simulation and Applied Optimization Sharjah, U.A.E January 20-22, 2009

    E-Print Network [OSTI]

    Hossain, M. Enamul

    Proceedings of the Third International Conference on Modeling, Simulation and Applied Optimization effectively in hard rock are well known [3]. These difficulties are limited by the system stiffness

  20. FATE Unified Modeling Method for Spent Nuclear Fuel and Sludge Processing, Shipping and Storage - 13405

    SciTech Connect (OSTI)

    Plys, Martin; Burelbach, James; Lee, Sung Jin; Apthorpe, Robert [Fauske and Associates, LLC, 16W070 83rd St., Burr Ridge, IL, 60527 (United States)] [Fauske and Associates, LLC, 16W070 83rd St., Burr Ridge, IL, 60527 (United States)

    2013-07-01T23:59:59.000Z

    A unified modeling method applicable to the processing, shipping, and storage of spent nuclear fuel and sludge has been incrementally developed, validated, and applied over a period of about 15 years at the US DOE Hanford site. The software, FATE{sup TM}, provides a consistent framework for a wide dynamic range of common DOE and commercial fuel and waste applications. It has been used during the design phase, for safety and licensing calculations, and offers a graded approach to complex modeling problems encountered at DOE facilities and abroad (e.g., Sellafield). FATE has also been used for commercial power plant evaluations including reactor building fire modeling for fire PRA, evaluation of hydrogen release, transport, and flammability for post-Fukushima vulnerability assessment, and drying of commercial oxide fuel. FATE comprises an integrated set of models for fluid flow, aerosol and contamination release, transport, and deposition, thermal response including chemical reactions, and evaluation of fire and explosion hazards. It is one of few software tools that combine both source term and thermal-hydraulic capability. Practical examples are described below, with consideration of appropriate model complexity and validation. (authors)

  1. Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant

    SciTech Connect (OSTI)

    Blanchat, T.K.; Allen, M.D.; Pilch, M.M. [Sandia National Labs., Albuquerque, NM (United States); Nichols, R.T. [Ktech Corp., Albuquerque, NM (United States)

    1994-06-01T23:59:59.000Z

    The Containment Technology Test Facility (CTTF) and the Surtsey Test Facility at Sandia National Laboratories are used to perform scaled experiments that simulate High Pressure Melt Ejection accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effects of direct containment heating (DCH) phenomena on the containment load. High-temperature, chemically reactive melt (thermite) is ejected by high-pressure steam into a scale model of a reactor cavity. Debris is entrained by the steam blowdown into a containment model where specific phenomena, such as the effect of subcompartment structures, prototypic air/steam/hydrogen atmospheres, and hydrogen generation and combustion, can be studied. Four Integral Effects Tests (IETs) have been performed with scale models of the Surry NPP to investigate DCH phenomena. The 1/61{sup th} scale Integral Effects Tests (IET-9, IET-10, and IET-11) were conducted in CTRF, which is a 1/6{sup th} scale model of the Surry reactor containment building (RCB). The 1/10{sup th} scale IET test (IET-12) was performed in the Surtsey vessel, which had been configured as a 1/10{sup th} scale Surry RCB. Scale models were constructed in each of the facilities of the Surry structures, including the reactor pressure vessel, reactor support skirt, control rod drive missile shield, biological shield wall, cavity, instrument tunnel, residual heat removal platform and heat exchangers, seal table room and seal table, operating deck, and crane wall. This report describes these experiments and gives the results.

  2. Compressor and Turbine Models of Brayton Units for Space Nuclear Power Systems

    SciTech Connect (OSTI)

    Gallo, Bruno M.; El-Genk, Mohamed S.; Tournier, Jean-Michel [Institute for Space and Nuclear Power Studies, University of New Mexico, Albuquerque, NM, 87131 (United States); Chemical and Nuclear Engineering Department, University of New Mexico, Albuquerque, NM, 87131 (United States)

    2007-01-30T23:59:59.000Z

    Closed Brayton Cycles with centrifugal flow, single-shaft turbo-machines are being considered, with gas cooled nuclear reactors, to provide 10's to 100's of electrical power to support future space exploration missions and Lunar and Mars outposts. Such power system analysis is typically based on the cycle thermodynamics, for given operating pressures and temperatures and assumed polytropic efficiencies of the compressor and turbine of the Brayton energy conversion units. Thus the analysis results not suitable for modeling operation transients such as startup and changes in the electric load. To simulate these transients, accurate models of the turbine and compressor in the Brayton rotating unit, which calculate the changes in the compressor and turbine efficiencies with system operation are needed. This paper presents flow models that account for the design and dimensions of the compressor impeller and diffuser, and the turbine stator and rotor blades. These models calculate the various enthalpy losses and the polytropic efficiencies along with the pressure ratios of the turbine and compressor. The predictions of these models compare well with reported performance data of actual hardware. In addition, the results of a parametric analysis to map the operations of the compressor and turbine, as functions of the rotating shaft speed and inlet Mach number of the gas working fluid, are presented and discussed. The analysis used a binary mixture of He-Xe with a molecular weight of 40 g/mole as the working fluid.

  3. Energetics of internal tides around the Kerguelen Plateau from modeling and altimetry

    E-Print Network [OSTI]

    data, we estimate the M2 barotropic tidal power converted through the internal tide generation process, with a parameterization term to account for the internal wave drag energy dissipation, is used to examine areas of possible M2 internal tide generation in the Kerguelen Plateau region. Barotropic energy flux

  4. Confidentiality Agreement between the Nuclear Decommissioning...

    Office of Environmental Management (EM)

    Services Communication & Engagement International Programs Confidentiality Agreement between the Nuclear Decommissioning Authority and US Department of Energy...

  5. Validation and Calibration of Nuclear Thermal Hydraulics Multiscale Multiphysics Models - Subcooled Flow Boiling Study

    SciTech Connect (OSTI)

    Anh Bui; Nam Dinh; Brian Williams

    2013-09-01T23:59:59.000Z

    In addition to validation data plan, development of advanced techniques for calibration and validation of complex multiscale, multiphysics nuclear reactor simulation codes are a main objective of the CASL VUQ plan. Advanced modeling of LWR systems normally involves a range of physico-chemical models describing multiple interacting phenomena, such as thermal hydraulics, reactor physics, coolant chemistry, etc., which occur over a wide range of spatial and temporal scales. To a large extent, the accuracy of (and uncertainty in) overall model predictions is determined by the correctness of various sub-models, which are not conservation-laws based, but empirically derived from measurement data. Such sub-models normally require extensive calibration before the models can be applied to analysis of real reactor problems. This work demonstrates a case study of calibration of a common model of subcooled flow boiling, which is an important multiscale, multiphysics phenomenon in LWR thermal hydraulics. The calibration process is based on a new strategy of model-data integration, in which, all sub-models are simultaneously analyzed and calibrated using multiple sets of data of different types. Specifically, both data on large-scale distributions of void fraction and fluid temperature and data on small-scale physics of wall evaporation were simultaneously used in this work’s calibration. In a departure from traditional (or common-sense) practice of tuning/calibrating complex models, a modern calibration technique based on statistical modeling and Bayesian inference was employed, which allowed simultaneous calibration of multiple sub-models (and related parameters) using different datasets. Quality of data (relevancy, scalability, and uncertainty) could be taken into consideration in the calibration process. This work presents a step forward in the development and realization of the “CIPS Validation Data Plan” at the Consortium for Advanced Simulation of LWRs to enable quantitative assessment of the CASL modeling of Crud-Induced Power Shift (CIPS) phenomenon, in particular, and the CASL advanced predictive capabilities, in general. This report is prepared for the Department of Energy’s Consortium for Advanced Simulation of LWRs program’s VUQ Focus Area.

  6. Modeling of UF{sub 6} enrichment with gas centrifuges for nuclear safeguards activities

    SciTech Connect (OSTI)

    Mercurio, G.; Peerani, P.; Richir, P.; Janssens, W.; Eklund, G. [European Commission, Joint Research Centre, Institute for Transuranium Elements Via Fermi, 2749-TP181,20127 Ispra (Italy)

    2012-09-26T23:59:59.000Z

    The physical modeling of uranium isotopes ({sup 235}U, {sup 238}U) separation process by centrifugation of is a key aspect for predicting the nuclear fuel enrichment plant performances under surveillance by the Nuclear Safeguards Authorities. In this paper are illustrated some aspects of the modeling of fast centrifuges for UF{sub 6} gas enrichment and of a typical cascade enrichment plant with the Theoretical Centrifuge and Cascade Simulator (TCCS). The background theory for reproducing the flow field characteristics of a centrifuge is derived from the work of Cohen where the separation parameters are calculated using the solution of a differential enrichment equation. In our case we chose to solve the hydrodynamic equations for the motion of a compressible fluid in a centrifugal field using the Berman - Olander vertical velocity radial distribution and the solution was obtained using the Matlab software tool. The importance of a correct estimation of the centrifuge separation parameters at different flow regimes, lies in the possibility to estimate in a reliable way the U enrichment plant performances, once the separation external parameters are set (feed flow rate and feed, product and tails assays). Using the separation parameters of a single centrifuge allow to determine the performances of an entire cascade and, for this purpose; the software Simulink was used. The outputs of the calculation are the concentrations (assays) and the flow rates of the enriched (product) and depleted (tails) gas mixture. These models represent a valid additional tool, in order to verify the compliance of the U enrichment plant operator declarations with the 'on site' inspectors' measurements.

  7. Indoor Air Nuclear, Biological, and Chemical Health Modeling and Assessment System

    SciTech Connect (OSTI)

    Stenner, Robert D.; Hadley, Donald L.; Armstrong, Peter R.; Buck, John W.; Hoopes, Bonnie L.; Janus, Michael C.

    2001-03-01T23:59:59.000Z

    Indoor air quality effects on human health are of increasing concern to public health agencies and building owners. The prevention and treatment of 'sick building' syndrome and the spread of air-borne diseases in hospitals, for example, are well known priorities. However, increasing attention is being directed to the vulnerability of our public buildings/places, public security and national defense facilities to terrorist attack or the accidental release of air-borne biological pathogens, harmful chemicals, or radioactive contaminants. The Indoor Air Nuclear, Biological, and Chemical Health Modeling and Assessment System (IA-NBC-HMAS) was developed to serve as a health impact analysis tool for use in addressing these concerns. The overall goal was to develop a user-friendly fully functional prototype Health Modeling and Assessment system, which will operate under the PNNL FRAMES system for ease of use and to maximize its integration with other modeling and assessment capabilities accessible within the FRAMES system (e.g., ambient air fate and transport models, water borne fate and transport models, Physiologically Based Pharmacokinetic models, etc.). The prototype IA-NBC-HMAS is designed to serve as a functional Health Modeling and Assessment system that can be easily tailored to meet specific building analysis needs of a customer. The prototype system was developed and tested using an actual building (i.e., the Churchville Building located at the Aberdeen Proving Ground) and release scenario (i.e., the release and measurement of tracer materials within the building) to ensure realism and practicality in the design and development of the prototype system. A user-friendly "demo" accompanies this report to allow the reader the opportunity for a "hands on" review of the prototype system's capability.

  8. Nuclear inputs of key iron isotopes for core-collapse modeling and simulation

    E-Print Network [OSTI]

    Jameel-Un Nabi; Abdel Nasser Tawfik

    2014-08-20T23:59:59.000Z

    From the modeling and simulation results of presupernova evolution of massive stars, it was found that isotopes of iron, $^{54,55,56}$Fe, play a significant role inside the stellar cores, primarily decreasing the electron-to-baryon ratio ($Y_{e}$) mainly via electron capture processes thereby reducing the pressure support. The neutrinos produced, as a result of these capture processes, are transparent to the stellar matter and assist in cooling the core thereby reducing the entropy. The structure of the presupernova star is altered both by the changes in $Y_{e}$ and the entropy of the core material. Here we present the microscopic calculation of Gamow-Teller strength distributions for isotopes of iron. The calculation is also compared with other theoretical models and experimental data. Presented also are stellar electron capture rates and associated neutrino cooling rates, due to isotopes of iron, in a form suitable for simulation and modeling codes. It is hoped that the nuclear inputs presented here should assist core-collapse simulators in the process of fine-tuning of the $Y_{e}$ parameter during various phases of presupernova evolution of massive stars. A reliable and accurate time evolution of this parameter is a possible key to generate a successful explosion in modeling of core-collapse supernovae.

  9. Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors

    E-Print Network [OSTI]

    Galvez, Cristhian

    2011-01-01T23:59:59.000Z

    Advisory Committee and Generation IV International Forum.Nuclear Energy Agency The Generation IV International Forum.Technology Roadmap for Generation IV Nuclear Energy Systems.

  10. Risk aggregation in Solvency II: How to converge the approaches of the internal models and those of the standard formula?

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    of the standard formula? Laurent Devineau Université de Lyon, Université Lyon 1, Laboratoire de Science the Solvency II economic capital: the use of a standard formula or the use of an internal model (global demonstrate that the standard formula can be considered as a first order approximation of the result

  11. IEEE International Workshop on Analysis and Modeling of Faces and Gestures, 2003. Human Body Tracking with Auxiliary Measurements

    E-Print Network [OSTI]

    Cohen, Issac

    in interactive virtual environment, human computer interaction, motion capture for human animation and videoIEEE International Workshop on Analysis and Modeling of Faces and Gestures, 2003. Human Body-0273 {munlee|icohen}@usc.edu Abstract This paper presents two techniques for improving human body tracking

  12. 8th International Conference on Product Lifecycle Management 1 The Cone-BOM model for consistent and

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    8th International Conference on Product Lifecycle Management 1 The Cone-BOM model for consistent as one of the major open issues in the field of Product Lifecycle Management. Especially, the BOM representation', 8th Int. Conf. Product Lifecycle Management. 1 Introduction Product Lifecycle Management (PLM

  13. ANS 2006 WINTER MEETING & Nuclear Technology Expo

    E-Print Network [OSTI]

    Krings, Axel W.

    Development Workshop: Digital Instrumentation Upgrades 52 DOE Nuclear Criticality Safety Program 53ANS 2006 WINTER MEETING & Nuclear Technology Expo "Ensuringthe (TOFE) 5th International Topical Meeting on Nuclear Plant Instrumentation, Controls, and Human Machine

  14. A statistical view on nuclear mass formula based on liquid drop model

    E-Print Network [OSTI]

    Cenxi Yuan

    2014-07-15T23:59:59.000Z

    The statistical method can be used to verify whether a theory is improved or not. As an example, a statistical study is applied to the error of the nuclear binding energy between the observed values and the theoretical values from the mass formula based on the liquid drop model (LDM). A new shell correction term is introduced to the traditional LDM. With such improvement, the error shows smaller standard deviation, better normality, reduced systematic part, and less dependent on the shell effect. The inclusion of the shell effect can be concluded to be an improvement purely from a statistical view. The present eight-parameter mass formula including shell effect gives standard deviation $\\sigma=1.4$ MeV for $2350$ observed binding energies from AME2012.

  15. Radiation Damage in Nuclear Fuel for Advanced Burner Reactors: Modeling and Experimental Validation

    SciTech Connect (OSTI)

    Jensen, Niels Gronbech; Asta, Mark; Ozolins, Nigel Browning'Vidvuds; de Walle, Axel van; Wolverton, Christopher

    2011-12-29T23:59:59.000Z

    The consortium has completed its existence and we are here highlighting work and accomplishments. As outlined in the proposal, the objective of the work was to advance the theoretical understanding of advanced nuclear fuel materials (oxides) toward a comprehensive modeling strategy that incorporates the different relevant scales involved in radiation damage in oxide fuels. Approaching this we set out to investigate and develop a set of directions: 1) Fission fragment and ion trajectory studies through advanced molecular dynamics methods that allow for statistical multi-scale simulations. This work also includes an investigation of appropriate interatomic force fields useful for the energetic multi-scale phenomena of high energy collisions; 2) Studies of defect and gas bubble formation through electronic structure and Monte Carlo simulations; and 3) an experimental component for the characterization of materials such that comparisons can be obtained between theory and experiment.

  16. The Nuclear Energy Advanced Modeling and Simulation Enabling Computational Technologies FY09 Report

    SciTech Connect (OSTI)

    Diachin, L F; Garaizar, F X; Henson, V E; Pope, G

    2009-10-12T23:59:59.000Z

    In this document we report on the status of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Enabling Computational Technologies (ECT) effort. In particular, we provide the context for ECT In the broader NEAMS program and describe the three pillars of the ECT effort, namely, (1) tools and libraries, (2) software quality assurance, and (3) computational facility (computers, storage, etc) needs. We report on our FY09 deliverables to determine the needs of the integrated performance and safety codes (IPSCs) in these three areas and lay out the general plan for software quality assurance to meet the requirements of DOE and the DOE Advanced Fuel Cycle Initiative (AFCI). We conclude with a brief description of our interactions with the Idaho National Laboratory computer center to determine what is needed to expand their role as a NEAMS user facility.

  17. Nuclear Shell Model Analyses and Predictions of Double-Beta Decay Observables

    SciTech Connect (OSTI)

    Horoi, Mihai [Department of Physics, Central Michigan University, Mount Pleasant, Michigan, 48859 (United States)

    2010-11-24T23:59:59.000Z

    Recent results from neutrino oscillation experiments have convincingly demonstrated that neutrinos have mass and they can mix. The neutrinoless double beta decay is the most sensitive process to determine the absolute scale of the neutrino masses, and the only one that can distinguish whether neutrino is a Dirac or a Majorana particle. A key ingredient for extracting the absolute neutrino masses from neutrinoless double beta decay experiments is a precise knowledge of the nuclear matrix elements (NME) for this process. Newly developed shell model approaches for computing the NME and half-lifes for the two-neutrino and neutrinoless double beta decay modes using modern effective interactions are presented. The implications of the new results on the experimental limits of the effective neutrino mass are discussed by comparing the decays of {sup 48}Ca and {sup 76}Ge.

  18. Modeling the Production of Beta-Delayed Gamma Rays for the Detection of Special Nuclear Materials

    SciTech Connect (OSTI)

    Hall, J M; Pruet, J A; Brown, D A; Descalle, M; Hedstrom, G W; Prussin, S G

    2005-02-14T23:59:59.000Z

    The objective of this LDRD project was to develop one or more models for the production of {beta}-delayed {gamma} rays following neutron-induced fission of a special nuclear material (SNM) and to define a standardized formatting scheme which will allow them to be incorporated into some of the modern, general-purpose Monte Carlo transport codes currently being used to simulate inspection techniques proposed for detecting fissionable material hidden in sea-going cargo containers. In this report, we will describe a Monte Carlo model for {beta}-delayed {gamma}-ray emission following the fission of SNM that can accommodate arbitrary time-dependent fission rates and photon collection histories. The model involves direct sampling of the independent fission yield distributions of the system, the branching ratios for decay of individual fission products and spectral distributions representing photon emission from each fission product and for each decay mode. While computationally intensive, it will be shown that this model can provide reasonably detailed estimates of the spectra that would be recorded by an arbitrary spectrometer and may prove quite useful in assessing the quality of evaluated data libraries and identifying gaps in the libraries. The accuracy of the model will be illustrated by comparing calculated and experimental spectra from the decay of short-lived fission products following the reactions {sup 235}U(n{sub th}, f) and {sup 239}Pu(n{sub th}, f). For general-purpose transport calculations, where a detailed consideration of the large number of individual {gamma}-ray transitions in a spectrum may not be necessary, it will be shown that a simple parameterization of the {gamma}-ray source function can be defined which provides high-quality average spectral distributions that should suffice for calculations describing photons being transported through thick attenuating media. Finally, a proposal for ENDF-compatible formats that describe each of the models and allow for their straightforward use in Monte Carlo codes will be presented.

  19. Copyright 2006 by Rich Janow Page 1 A First-Principles Model for Estimating Atmospheric Nuclear

    E-Print Network [OSTI]

    Janow, Rich

    26, 2006 Page 2 REFERENCES 1. Glasstone, S. and P. Dolan, eds., 'The Effects of Nuclear Weapons', 3rd

  20. Ab Initio Enhanced calphad Modeling of Actinide-Rich Nuclear Fuels

    SciTech Connect (OSTI)

    Morgan, Dane [Univ. of Wisconsin, Madison, WI (United States); Yang, Yong Austin [Univ. of Wisconsin, Madison, WI (United States)

    2013-10-28T23:59:59.000Z

    The process of fuel recycling is central to the Advanced Fuel Cycle Initiative (AFCI), where plutonium and the minor actinides (MA) Am, Np, and Cm are extracted from spent fuel and fabricated into new fuel for a fast reactor. Metallic alloys of U-Pu-Zr-MA are leading candidates for fast reactor fuels and are the current basis for fast spectrum metal fuels in a fully recycled closed fuel cycle. Safe and optimal use of these fuels will require knowledge of their multicomponent phase stability and thermodynamics (Gibbs free energies). In additional to their use as nuclear fuels, U-Pu-Zr-MA contain elements and alloy phases that pose fundamental questions about electronic structure and energetics at the forefront of modern many-body electron theory. This project will validate state-of-the-art electronic structure approaches for these alloys and use the resulting energetics to model U-Pu-Zr-MA phase stability. In order to keep the work scope practical, researchers will focus on only U-Pu-Zr-{Np,Am}, leaving Cm for later study. The overall objectives of this project are to: Provide a thermodynamic model for U-Pu-Zr-MA for improving and controlling reactor fuels; and, Develop and validate an ab initio approach for predicting actinide alloy energetics for thermodynamic modeling.

  1. Aerosol particle transport modeling for preclosure safety studies of nuclear waste repositories

    SciTech Connect (OSTI)

    Gelbard, F. [Sandia National Labs., Albuquerque, NM (USA)

    1989-01-01T23:59:59.000Z

    An important concern for preclosure safety analysis of a nuclear waste repository is the potential release to the environment of respirable aerosol particles. Such particles, less than 10 {mu}m in aerodynamic diameter, may have significant adverse health effects if inhaled. To assess the potential health effects of these particles, it is not sufficient to determine the mass fraction of respirable aerosol. The chemical composition of the particles is also of importance since different radionuclides may pose vastly different health hazards. Thus, models are needed to determine under normal and accident conditions the particle size and the chemical composition distributions of aerosol particles as a function of time and of position in the repository. In this work a multicomponent sectional aerosol model is used to determine the aerosol particle size and composition distributions in the repository. A range of aerosol mass releases with varying mean particle sizes and chemical compositions is used to demonstrate the sensitivities and uncertainties of the model. Decontamination factors for some locations in the repository are presented. 8 refs., 1 tab.

  2. Observing and modeling nonlinear dynamics in an internal combustion engine Engineering Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-8088

    E-Print Network [OSTI]

    Tennessee, University of

    Observing and modeling nonlinear dynamics in an internal combustion engine C. S. Daw* Engineering motivated, nonlinear map as a model for cyclic combustion variation in spark-ignited internal combustion combustion engines can exhibit substantial cycle-to-cycle variation in combustion energy release

  3. Health effects model for nuclear power plant accident consequence analysis. Part I. Introduction, integration, and summary. Part II. Scientific basis for health effects models

    SciTech Connect (OSTI)

    Evans, J.S.; Moeller, D.W.; Cooper, D.W.

    1985-07-01T23:59:59.000Z

    Analysis of the radiological health effects of nuclear power plant accidents requires models for predicting early health effects, cancers and benign thyroid nodules, and genetic effects. Since the publication of the Reactor Safety Study, additional information on radiological health effects has become available. This report summarizes the efforts of a program designed to provide revised health effects models for nuclear power plant accident consequence modeling. The new models for early effects address four causes of mortality and nine categories of morbidity. The models for early effects are based upon two parameter Weibull functions. They permit evaluation of the influence of dose protraction and address the issue of variation in radiosensitivity among the population. The piecewise-linear dose-response models used in the Reactor Safety Study to predict cancers and thyroid nodules have been replaced by linear and linear-quadratic models. The new models reflect the most recently reported results of the follow-up of the survivors of the bombings of Hiroshima and Nagasaki and permit analysis of both morbidity and mortality. The new models for genetic effects allow prediction of genetic risks in each of the first five generations after an accident and include information on the relative severity of various classes of genetic effects. The uncertainty in modeloling radiological health risks is addressed by providing central, upper, and lower estimates of risks. An approach is outlined for summarizing the health consequences of nuclear power plant accidents. 298 refs., 9 figs., 49 tabs.

  4. Interim Management of Nuclear Materials

    Broader source: Energy.gov (indexed) [DOE]

    by the appropriate agency (DOE, the Department of Transportation, the Nuclear Regulatory Commission, or the International Atomic Energy Agency) for full containment of the...

  5. Safety Culture in Nuclear Installations

    Broader source: Energy.gov [DOE]

    IAEA-TECDOC-1329 Safety Culture in Nuclear Installations, Guidance for use in the Enhancement of Safety Culture, International Atomic Energy Agency IAEA, December 2002.

  6. Time-dependent Radiation Transfer in the Internal Shock Model Scenario for Blazar Jets

    E-Print Network [OSTI]

    Manasvita Joshi; Markus Boettcher

    2010-11-13T23:59:59.000Z

    We describe the time-dependent radiation transfer in blazar jets, within the internal shock model. We assume that the central engine, which consists of a black hole and an accretion disk, spews out relativistic shells of plasma with different velocity, mass, and energy. We consider a single inelastic collision between a faster (inner) and a slower (outer) moving shell. We study the dynamics of the collision and evaluate the subsequent emission of radiation via the synchrotron and synchrotron self Compton (SSC) processes after the interaction between the two shells has begun. The collision results in the formation of a forward shock (FS) and a reverse shock (RS) that convert the ordered bulk kinetic energy of the shells into magnetic field energy and accelerate the particles, which then radiate. We assume a cylindrical geometry for the emission region of the jet. We treat the self-consistent radiative transfer by taking into account the inhomogeneity in the photon density throughout the region. In this paper, we focus on understanding the effects of varying relevant input parameters on the simulated spectral energy distribution (SED) and spectral variability patterns.

  7. Radioxenon detections in the CTBT International Monitoring System likely related to the announced nuclear test in North Korea conducted on February 12, 2013

    SciTech Connect (OSTI)

    Ringbom, Anders; Axelssson, A.; Aldener, M.; Auer, M.; Bowyer, Ted W.; Fritioff, T.; Hoffman, Ian; Khrustalev, Kirill; Nikkinen, Mika; Popov, Vladimir Y.; Popov, Y.; Ungar, R. Kurt; Wotawa, G.

    2014-02-01T23:59:59.000Z

    Abstract: Observations of the radioxenon isotopes 133Xe and 131mXe collected at the IMS stations RN38 and RN58 on April 7-8, and April 12-13 2013, respectively, are unique with respect to the measurement history of these stations. Comparison of measured data with calculated isotopic ratios as well as analysis using atmospheric transport modeling indicate that it is likely that the xenon measured was created in the underground nuclear test conducted by North Korea on February 12, 2013, and released 7 weeks later. More than one release is required to explain all observations. The 131mXe source terms for each release were calculated to 7x1011 Bq, corresponding to about 1-10% of the total xenon inventory for a 10-kt explosion, depending on fractionation and release scenario. The observed ratios could not be used to obtain any information regarding the fissile material that was used in the test.

  8. Large scale nuclear sensor monitoring and diagnostics by means of an ensemble of regression models based on Evolving Clustering Methods

    E-Print Network [OSTI]

    Boyer, Edmond

    Large scale nuclear sensor monitoring and diagnostics by means of an ensemble of regression models , Enrico Ziob a Institute for Energy Technology, Halden, Norway b Polytechnic of Milan, Milan, Italy actions for safely steering critical situations and preventing accidents. To avoid misleading information

  9. Critical Infrastructure Interdependency Modeling: A Survey of U.S. and International Research

    SciTech Connect (OSTI)

    Not Available

    2006-08-01T23:59:59.000Z

    The Nation’s health, wealth, and security rely on the production and distribution of certain goods and services. The array of physical assets, processes, and organizations across which these goods and services move are called "critical infrastructures".1 This statement is as true in the U.S. as in any country in the world. Recent world events such as the 9-11 terrorist attacks, London bombings, and gulf coast hurricanes have highlighted the importance of stable electric, gas and oil, water, transportation, banking and finance, and control and communication infrastructure systems. Be it through direct connectivity, policies and procedures, or geospatial proximity, most critical infrastructure systems interact. These interactions often create complex relationships, dependencies, and interdependencies that cross infrastructure boundaries. The modeling and analysis of interdependencies between critical infrastructure elements is a relatively new and very important field of study. The U.S. Technical Support Working Group (TSWG) has sponsored this survey to identify and describe this current area of research including the current activities in this field being conducted both in the U.S. and internationally. The main objective of this study is to develop a single source reference of critical infrastructure interdependency modeling tools (CIIMT) that could be applied to allow users to objectively assess the capabilities of CIIMT. This information will provide guidance for directing research and development to address the gaps in development. The results will inform researchers of the TSWG Infrastructure Protection Subgroup of research and development efforts and allow a more focused approach to addressing the needs of CIIMT end-user needs. This report first presents the field of infrastructure interdependency analysis, describes the survey methodology, and presents the leading research efforts in both a cumulative table and through individual datasheets. Data was collected from open source material and when possible through direct contact with the individuals leading the research.

  10. International Conference 'Transport and Air Pollution' 2008, Graz EMISSION FACTOR MODELLING FOR LIGHT VEHICLES

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    - 1 - 16th International Conference 'Transport and Air Pollution' 2008, Graz EMISSION FACTOR in Europe: The European MEET (Methodologies for Estimating air pollutant Emissions from Transport) project. Transport and Air Pollution, Graz : Austria (2008)" #12;- 2 - 16th International Conference 'Transport

  11. A Heat Transfer Model for a Stratified Corium-Metal Pool in the Lower Plenum of a Nuclear Reactor

    SciTech Connect (OSTI)

    M. S. Sohal; L. J. Siefken

    1999-08-01T23:59:59.000Z

    This preliminary design report describes a model for heat transfer in a corium-metal stratified pool. It was decided to make use of the existing COUPLE model. Currently available correlations for natural convection heat transfer in a pool with and without internal heat generation were obtained. The appropriate correlations will be incorporated in the existing COUPLE model. Heat conduction and solidification modeling will be done with existing algorithms in the COUPLE. Assessment of the new model will be done by simple energy conservation problems.

  12. A Heat Transfer Model for a Stratified Corium-metal Pool in the Lower Plenum of a Nuclear Reactor

    SciTech Connect (OSTI)

    Sohal, Manohar Singh; Siefken, Larry James

    1999-08-01T23:59:59.000Z

    This preliminary design report describes a model for heat transfer in a corium-metal stratified pool. It was decided to make use of the existing COUPLE model. Currently available correlations for natural convection heat transfer in a pool with and without internal heat generation were obtained. The appropriate correlations will be incorporated in the existing COUPLE model. Heat conduction and solidification modeling will be done with existing algorithms in the COUPLE. Assessment of the new model will be done by simple energy conservation problems.

  13. INTERNATIONAL International Internship for

    E-Print Network [OSTI]

    Napier, Terrence

    OFFICE OF INTERNATIONAL AFFAIRS International Internship for Global Leadership Program Student Portugal ­ Laura Sieger Ukraine ­ Mary Brune 2012 Internship Locations #12;Dear Friends and Colleagues of Lehigh University: The International Internship for Global Leadership Program provides Lehigh students

  14. Odd-even staggering in nuclear binding and the liquid-drop model

    E-Print Network [OSTI]

    W. A. Friedman

    2009-11-03T23:59:59.000Z

    The trends with mass number are examined for the odd-even-staggering (OES) in nuclear binding of neutrons and protons through the conventional measures $\\Delta^{(3)}$. The large differences previously observed between these trends for even and odd values of these measures is found to arise, in part, from the slow variation of binding energies with mass and charge which provides a background contribution. This background is estimated with the liquid-drop model, and accounts for the greater difference found in proton removal relative to neutron removal. The differences which persist after backgrounds are removed can not be treated in the conventional liquid-drop model but require the addition of a new term. Such a term is investigated, and its effect on specific values of the OES is calcutated. The liquid-drop fitting is also applied to a set of separation energies constrained to match the specific set of nuclei used to determine the observed values for the odd $\\Delta^{(3)}$. The resulting fit for the pairing term is compared to the average value of even and odd measures. The effect on this value of the new liquid-drop term is observed, and the change in background when the new term is included is also used as an alternate method for determining the difference between trends of the even and odd values of the OES.

  15. Long-term global nuclear energy and fuel cycle strategies

    SciTech Connect (OSTI)

    Krakowski, R.A. [Los Alamos National Lab., NM (United States). Technology and Safety Assessment Div.

    1997-09-24T23:59:59.000Z

    The Global Nuclear Vision Project is examining, using scenario building techniques, a range of long-term nuclear energy futures. The exploration and assessment of optimal nuclear fuel-cycle and material strategies is an essential element of the study. To this end, an established global E{sup 3} (energy/economics/environmental) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Consistent nuclear energy scenarios are constructed using this multi-regional E{sup 3} model, wherein future demands for nuclear power are projected in price competition with other energy sources under a wide range of long-term demographic (population, workforce size and productivity), economic (price-, population-, and income-determined demand for energy services, price- and population-modified GNP, resource depletion, world-market fossil energy prices), policy (taxes, tariffs, sanctions), and top-level technological (energy intensity and end-use efficiency improvements) drivers. Using the framework provided by the global E{sup 3} model, the impacts of both external and internal drivers are investigated. The ability to connect external and internal drivers through this modeling framework allows the study of impacts and tradeoffs between fossil- versus nuclear-fuel burning, that includes interactions between cost, environmental, proliferation, resource, and policy issues.

  16. International Journal of Pharmaceutics 307 (2006) 225231 Interactions of oleic acid and model stratum

    E-Print Network [OSTI]

    Rowat, Amy C.

    2006-01-01T23:59:59.000Z

    deuterium nuclear magnetic resonance to monitor such multilamellar SC dispersions containing either, is not clear. Some have speculated that cis-unsaturated fatty acids such as OA `fluidize' SC lipids

  17. Preliminary results of a dynamic system model for a closed-loop Brayton cycle coupled to a nuclear reactor.

    SciTech Connect (OSTI)

    Wright, Steven Alan

    2003-06-01T23:59:59.000Z

    This paper describes preliminary results of a dynamic system model for a closed-loop Brayton-cycle that is coupled to a nuclear reactor. The current model assumes direct coupling between the reactor and the Brayton-cycle, however only minor additions are required to couple the Brayton-cycle through a heat exchanger to either a heat pipe reactor or a liquid metal cooled reactor. Few reactors have ever been coupled to closed Brayton-cycle systems. As such their behavior under dynamically varying loads, startup and shut down conditions, and requirements for safe and autonomous operation are largely unknown. Sandia National Laboratories has developed steady-state and dynamic models for closed-loop turbo-compressor systems (for space and terrestrial applications). These models are expected to provide a basic understanding of the dynamic behavior and stability of the coupled reactor and power generation loop. The model described in this paper is a lumped parameter model of the reactor, turbine, compressor, recuperator, radiator/waste-heat-rejection system and generator. More detailed models that remove the lumped parameter simplifications are also being developed but are not presented here. The initial results of the model indicate stable operation of the reactor-driven Brayton-cycle system and its ability to load-follow. However, the model also indicates some counter-intuitive behavior for the complete coupled system. This behavior will require the use of a reactor control system to select an appropriate reactor operating temperature that will optimize the performance of the complete spacecraft system. We expect this model and subsequent versions of it to provide crucial information in developing procedures for safe start up, shut down, safe-standby, and other autonomous operating modes. Ultimately, Sandia hopes to validate these models and to perform nuclear ground tests of reactor-driven closed Brayton-cycle systems in our nuclear research facilities.

  18. Internal dosimetry software comparison

    E-Print Network [OSTI]

    Fulmer, Judith Renee

    1992-01-01T23:59:59.000Z

    (ICRP) published in 1979 provided an improved approach for the assessment of internal dose. The ICRP recommendations were implemented in federal regulations promulgated by the Nuclear Regulatory Commission (NRC) in the Code of Federal Regulations (10... in the assessment of internal dose has led to the development of various computer software. In this study, several internal dosimetry codes were examined using a standard set of benchmark problems incorporating authentic exposure data. Personal computer...

  19. Development of a computational model for nuclear electric orbital transfer vehicles

    E-Print Network [OSTI]

    Lyon, William Fountain

    1989-01-01T23:59:59.000Z

    been initiated concerning the application of advanced propulsion concepts such as nuclear thermal, nuclear electric and space-based OTVs (Ramsthaler et a1. 1988). To that end, the objective of this project was to develop a simplified computational... the potential to provide much higher power levels at lower specific powers. One project currently under development is the SP-100 space nuclear power system. This pmject is the product of a triagency consortium of the Department of Energy (DOE...

  20. Liquid-gas phase transition in hot asymmetric nuclear matter with density-dependent relativistic mean-field models

    E-Print Network [OSTI]

    Guang-Hua Zhang; Wei-Zhou Jiang

    2013-02-14T23:59:59.000Z

    The liquid-gas phase transition in hot asymmetric nuclear matter is studied within density-dependent relativistic mean-field models where the density dependence is introduced according to the Brown-Rho scaling and constrained by available data at low densities and empirical properties of nuclear matter. The critical temperature of the liquid-gas phase transition is obtained to be 15.7 MeV in symmetric nuclear matter falling on the lower edge of the small experimental error bars. In hot asymmetric matter, the boundary of the phase-coexistence region is found to be sensitive to the density dependence of the symmetry energy. The critical pressure and the area of phase-coexistence region increases clearly with the softening of the symmetry energy. The critical temperature of hot asymmetric matter separating the gas phase from the LG coexistence phase is found to be higher for the softer symmetry energy.

  1. Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multimodal transportation network

    SciTech Connect (OSTI)

    Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, and focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

  2. Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multi-modal transportation network

    SciTech Connect (OSTI)

    Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

    2010-10-28T23:59:59.000Z

    Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, all focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

  3. Smoke inputs to climate models: optical properties and height distribution for nuclear winter studies

    SciTech Connect (OSTI)

    Penner, J.E.; Haselman, L.C. Jr.

    1985-04-01T23:59:59.000Z

    Smoke from fires produced in the aftermath of a major nuclear exchange has been predicted to cause large decreases in land surface temperatures. The extent of the decrease and even the sign of the temperature change depend on the optical characteristics of the smoke and how it is distributed with altitude. The height distribution of smoke over a fire is determined by the amount of buoyant energy produced by the fire and the amount of energy released by the latent heat of condensation of water vapor. The optical properties of the smoke depend on the size distribution of smoke particles which changes due to coagulation within the lofted plume. We present calculations demonstrating these processes and estimate their importance for the smoke source term input for climate models. For high initial smoke densities and for absorbing smoke ( m = 1.75 - 0.3i), coagulation of smoke particles within the smoke plume is predicted to first increase, then decrease, the size-integrated extinction cross section. However, at the smoke densities predicted in our model (assuming a 3% emission rate for smoke) and for our assumed initial size distribution, the attachment rates for brownian and turbulent collision processes are not fast enough to alter the smoke size distribution enough to significantly change the integrated extinction cross section. Early-time coagulation is, however, fast enough to allow further coagulation, on longer time scales, to act to decrease the extinction cross section. On these longer time scales appropriate to climate models, coagulation can decrease the extinction cross section by almost a factor of two before the smoke becomes well mixed around the globe. This process has been neglected in past climate effect evaluations, but could have a significant effect, since the extinction cross section enters as an exponential factor in calculating the light attenuation due to smoke. 10 refs., 20 figs.

  4. August 24~28, 2014 International Convention Center (ICC) Jeju, Jeju Island, Korea

    E-Print Network [OSTI]

    Symposium on Future I&C for Nuclear Power Plants International Symposium on Symbiotic Nuclear Power Systems Plants International Symposium on Symbiotic Nuclear Power Systems ISOFIC/ISSNP 2014 #12;Foreword, Jeju Island, Korea International Symposium on Future I&C for Nuclear Power Plants International

  5. The U.S. national nuclear forensics library, nuclear materials information program, and data dictionary

    SciTech Connect (OSTI)

    Lamont, Stephen Philip [Los Alamos National Laboratory; Brisson, Marcia [DOE-IN; Curry, Michael [DEPT. OF STATE

    2011-02-17T23:59:59.000Z

    Nuclear forensics assessments to determine material process history requires careful comparison of sample data to both measured and modeled nuclear material characteristics. Developing centralized databases, or nuclear forensics libraries, to house this information is an important step to ensure all relevant data will be available for comparison during a nuclear forensics analysis and help expedite the assessment of material history. The approach most widely accepted by the international community at this time is the implementation of National Nuclear Forensics libraries, which would be developed and maintained by individual nations. This is an attractive alternative toan international database since it provides an understanding that each country has data on materials produced and stored within their borders, but eliminates the need to reveal any proprietary or sensitive information to other nations. To support the concept of National Nuclear Forensics libraries, the United States Department of Energy has developed a model library, based on a data dictionary, or set of parameters designed to capture all nuclear forensic relevant information about a nuclear material. Specifically, information includes material identification, collection background and current location, analytical laboratories where measurements were made, material packaging and container descriptions, physical characteristics including mass and dimensions, chemical and isotopic characteristics, particle morphology or metallurgical properties, process history including facilities, and measurement quality assurance information. While not necessarily required, it may also be valuable to store modeled data sets including reactor burn-up or enrichment cascade data for comparison. It is fully expected that only a subset of this information is available or relevant to many materials, and much of the data populating a National Nuclear Forensics library would be process analytical or material accountability measurement data as opposed to a complete forensic analysis of each material in the library.

  6. Computations and modeling of oil transport between piston lands and liner in internal combustion engines

    E-Print Network [OSTI]

    Fang, Tianshi

    2014-01-01T23:59:59.000Z

    The consumption of lubricating oil in internal combustion engines is a continuous interest for engine developers and remains to be one of the least understood areas. A better understanding on oil transport is critical to ...

  7. Modeling the lubrication of the piston ring pack in internal combustion engines using the deterministic method

    E-Print Network [OSTI]

    Chen, Haijie

    2011-01-01T23:59:59.000Z

    Piston ring packs are used in internal combustion engines to seal both the high pressure gas in the combustion chamber and the lubricant oil in the crank case. The interaction between the piston ring pack and the cylinder ...

  8. Numerical modeling of piston secondary motion and skirt lubrication in internal combustion engines

    E-Print Network [OSTI]

    McClure, Fiona

    2007-01-01T23:59:59.000Z

    Internal combustion engines dominate transportation of people and goods, contributing significantly to air pollution, and requiring large amounts of fossil fuels. With increasing public concern about the environment and ...

  9. TYBO/BENHAM: Model Analysis of Groundwater Flow and Radionuclide Migration from Underground Nuclear Tests in Southwestern Pahute Mesa, Nevada

    SciTech Connect (OSTI)

    Andrew Wolfsberg; Lee Glascoe; Guoping Lu; Alyssa; Olson; Peter Lichtner; Maureen McGraw; Terry Cherry; ,; Guy Roemer

    2002-09-01T23:59:59.000Z

    Recent field studies have led to the discovery of trace quantities of plutonium originating from the BENHAM underground nuclear test in two groundwater observation wells on Pahute Mesa at the Nevada Test Site. These observation wells are located 1.3 km from the BENHAM underground nuclear test and approximately 300 m from the TYBO underground nuclear test. In addition to plutonium, several other conservative (e.g. tritium) and reactive (e.g. cesium) radionuclides were found in both observation wells. The highest radionuclide concentrations were found in a well sampling a welded tuff aquifer more than 500m above the BENHAM emplacement depth. These measurements have prompted additional investigations to ascertain the mechanisms, processes, and conditions affecting subsurface radionuclide transport in Pahute Mesa groundwater. This report describes an integrated modeling approach used to simulate groundwater flow, radionuclide source release, and radionuclide transport near the BENHAM and TYBO underground nuclear tests on Pahute Mesa. The components of the model include a flow model at a scale large enough to encompass many wells for calibration, a source-term model capable of predicting radionuclide releases to aquifers following complex processes associated with nonisothermal flow and glass dissolution, and site-scale transport models that consider migration of solutes and colloids in fractured volcanic rock. Although multiple modeling components contribute to the methodology presented in this report, they are coupled and yield results consistent with laboratory and field observations. Additionally, sensitivity analyses are conducted to provide insight into the relative importance of uncertainty ranges in the transport parameters.

  10. A Multi-Stage Wear Model for Grid-to-Rod Fretting of Nuclear Fuel Rods

    SciTech Connect (OSTI)

    Blau, Peter Julian [ORNL] [ORNL

    2014-01-01T23:59:59.000Z

    The wear of fuel rod cladding against the supporting structures in the cores of pressurized water nuclear reactors (PWRs) is an important and potentially costly tribological issue. Grid-to-rod fretting (GTRF), as it is known, involves not only time-varying contact conditions, but also elevated temperatures, flowing hot water, aqueous tribo-corrosion, and the embrittling effects of neutron fluences. The multi-stage, closed-form analytical model described in this paper relies on published out-of-reactor wear and corrosion data and a set of simplifying assumptions to portray the conversion of frictional work into wear depth. The cladding material of interest is a zirconium-based alloy called Zircaloy-4, and the grid support is made of a harder and more wear-resistant material. Focus is on the wear of the cladding. The model involves an incubation stage, a surface oxide wear stage, and a base alloy wear stage. The wear coefficient, which is a measure of the efficiency of conversion of frictional work into wear damage, can change to reflect the evolving metallurgical condition of the alloy. Wear coefficients for Zircaloy-4 and for a polyphase zirconia layer were back-calculated for a range of times required to wear to a critical depth. Inputs for the model, like the friction coefficient, are taken from the tribology literature in lieu of in-reactor tribological data. Concepts of classical fretting were used as a basis, but are modified to enable the model to accommodate the complexities of the PWR environment. Factors like grid spring relaxation, pre-oxidation of the cladding, multiple oxide phases, gap formation, impact, and hydrogen embrittlement are part of the problem definition but uncertainties in their relative roles limits the ability to validate the model. Sample calculations of wear depth versus time in the cladding illustrate how GTRF wear might occur in a discontinuous fashion during months-long reactor operating cycles. A means to account for grid/rod gaps and repetitive impact effects on GTRF wear is proposed

  11. International | 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA groupTubahq.na.gov Office ofDepartmentAdministrationto SubmitIND| National

  12. international | 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. HirschOccurrencei-rapter | National| National

  13. International Collaborations on Engineered Barrier Systems: Experiment...

    Energy Savers [EERE]

    International Collaborations on Engineered Barrier Systems: Experimental and Modeling Investigations International Collaborations on Engineered Barrier Systems: Experimental and...

  14. Current Understanding and Remaining Challenges in Modeling Long-Term Degradation of Borosilicate Nuclear Waste Glasses

    SciTech Connect (OSTI)

    Vienna, John D. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Ryan, Joseph V. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Gin, Stephane [CEA Marcoule, DTCD SECM, Bagnols-sur-Ceze (France); Inagaki, Yaohiro [Dept. of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoda (Japan)

    2013-12-01T23:59:59.000Z

    Chemical durability is not a single material property that can be uniquely measured. Instead it is the response to a host of coupled material and environmental processes whose rates are estimated by a combination of theory, experiment, and modeling. High-level nuclear waste (HLW) glass is perhaps the most studied of any material yet there remain significant technical gaps regarding their chemical durability. The phenomena affecting the long-term performance of HLW glasses in their disposal environment include surface reactions, transport properties to and from the reacting glass surface, and ion exchange between the solid glass and the surrounding solution and alteration products. The rates of these processes are strongly influenced and are coupled through the solution chemistry, which is in turn influenced by the reacting glass and also by reaction with the near-field materials and precipitation of alteration products. Therefore, those processes must be understood sufficiently well to estimate or bound the performance of HLW glass in its disposal environment over geologic time-scales. This article summarizes the current state of understanding of surface reactions, transport properties, and ion exchange along with the near-field materials and alteration products influences on solution chemistry and glass reaction rates. Also summarized are the remaining technical gaps along with recommended approaches to fill those technical gaps.

  15. On the coefficients of the liquid drop model mass formulae and nuclear radii

    E-Print Network [OSTI]

    G. Royer

    2008-04-11T23:59:59.000Z

    The coefficients of different mass formulae derived from the liquid drop model and including or not the curvature energy, the diffuseness correction to the Coulomb energy, the charge exchange correction term, different forms of the Wigner term and different powers of the relative neutron excess $I=(N-Z)/A$ have been determined by a least square fitting procedure to 2027 experimental atomic masses. The Coulomb diffuseness correction $Z^2/A$ term or the charge exchange correction $Z^{4/3}/A^{1/3}$ term plays the main role to improve the accuracy of the mass formula. The Wigner term and the curvature energy can also be used separately for the same purpose. The introduction of an $|I|$ dependence in the surface and volume energies improves slightly the efficiency of the expansion and is more effective than an $I^4$ dependence. Different expressions reproducing the experimental nuclear charge radius are provided. The different fits lead to a surface energy coefficient of around 17-18 MeV and a relative equivalent rms charge radius r$_0$ of 1.22-1.23 fm.

  16. World Net Nuclear Electric Power Generation, 1980-2007 - Datasets...

    Open Energy Info (EERE)

    U.S. Energy Information ... World Net Nuclear Electric ... Dataset Activity Stream World Net Nuclear Electric Power Generation, 1980-2007 International data showing world net...

  17. Long-Term Planning for Nuclear Energy Systems Under Deep Uncertainty

    E-Print Network [OSTI]

    Kim, Lance Kyungwoo

    2011-01-01T23:59:59.000Z

    5.3.2 Nuclear Energy System Model . . . . . . . . . . .Brief History of Nuclear Energy . . . . . . . . Nuclear FuelModeling . . . . . . . . . . . . . 5.3 Nuclear Energy System

  18. A revised model of the kidney for medical internal radiation dose calculations

    E-Print Network [OSTI]

    Patel, Jyoti Shivabhai

    1988-01-01T23:59:59.000Z

    are frequently the organs receiving the highest level of radioactivity and, therefore, the largest radiation dose. Short lived radiopharmaceuticals, that are now injected in millicurie quantities in nuclear medicine for rapid-sequence imaging of the brain... radionuclides (Appendix B). 17 These include the following radionuclides presently used in nuclear medicine: P-32, Cr-51, Co-57, Ga-67, Tc-99m, In-ill, I-123, Xe-127, I-131, Xe-133, and T1-201. If the radionuclide emits penetrating radiation, the code...

  19. Jordan Boyd-Graber and David M. Blei. PUTOP: Turning Predominant Senses into a Topic Model for WSD. 4th International Workshop on Semantic Evaluations, 2007.

    E-Print Network [OSTI]

    Boyd-Graber, Jordan

    Jordan Boyd-Graber and David M. Blei. PUTOP: Turning Predominant Senses into a Topic Model for WSD. 4th International Workshop on Semantic Evaluations, 2007. @inproceedings{Boyd-Graber:Blei-2007, Author = {Jordan Boyd-Graber and David M. Blei}, Booktitle = {4th International Workshop on Semantic

  20. Three-dimensional numerical modeling of smoke injection from large fires in the early post-nuclear-exchange environment

    SciTech Connect (OSTI)

    Bradley, M.M.; Peterson, K.R.; Rodriguez, D.J.

    1988-11-17T23:59:59.000Z

    During the hours immediately following a nuclear exchange, large fires could inject enormous quantities of smoke into the atmosphere. This smoke, together with dust from surface bursts, would severely restrict visibilities and darken the skies over large areas for days. This, in turn, could impact surface and air operations and systems. These effects could be mitigated by various scavenging mechanisms within the convective clouds that form above the fires. In order to evaluate impacts of post-nuclear-exchange smoke injection, we are developing a three-dimensional numerical smoke plume model (OCTET) to simulate the dynamics and microphysical processes within smoke plumes and convective clouds above large fires. This model is based on the dynamic framework of the Klemp-Wilhelmson (1978) convective storm model and includes parameterizations of scavenging processes. In addition, we are combining results of laboratory research, field experiments, and detailed numerical modeling of cloud microphysical processes in order to better understand smoke scavenging mechanisms. In this brief demonstration of capabilities, we present results from the OCTET model and from a three-dimensional mesoscale model. The smoke plume and fire-induced cloud simulations demonstrate the effects of nucleation scavenging, seasonal variation of atmospheric stability, and various fuel sources. The mesoscale simulations (that use the plume model output as input) demonstrate the mesoscale transport and diffusion of smoke and predict optical depths over the hypothetical target area. No dust effects have been included in these simulations. 2 refs., 8 figs.

  1. TOWARD END-TO-END MODELING FOR NUCLEAR EXPLOSION MONITORING: SIMULATION OF UNDERGROUND NUCLEAR EXPLOSIONS AND EARTHQUAKES USING HYDRODYNAMIC AND ANELASTIC SIMULATIONS, HIGH-PERFORMANCE COMPUTING AND THREE-DIMENSIONAL EARTH MODELS

    SciTech Connect (OSTI)

    Rodgers, A; Vorobiev, O; Petersson, A; Sjogreen, B

    2009-07-06T23:59:59.000Z

    This paper describes new research being performed to improve understanding of seismic waves generated by underground nuclear explosions (UNE) by using full waveform simulation, high-performance computing and three-dimensional (3D) earth models. The goal of this effort is to develop an end-to-end modeling capability to cover the range of wave propagation required for nuclear explosion monitoring (NEM) from the buried nuclear device to the seismic sensor. The goal of this work is to improve understanding of the physical basis and prediction capabilities of seismic observables for NEM including source and path-propagation effects. We are pursuing research along three main thrusts. Firstly, we are modeling the non-linear hydrodynamic response of geologic materials to underground explosions in order to better understand how source emplacement conditions impact the seismic waves that emerge from the source region and are ultimately observed hundreds or thousands of kilometers away. Empirical evidence shows that the amplitudes and frequency content of seismic waves at all distances are strongly impacted by the physical properties of the source region (e.g. density, strength, porosity). To model the near-source shock-wave motions of an UNE, we use GEODYN, an Eulerian Godunov (finite volume) code incorporating thermodynamically consistent non-linear constitutive relations, including cavity formation, yielding, porous compaction, tensile failure, bulking and damage. In order to propagate motions to seismic distances we are developing a one-way coupling method to pass motions to WPP (a Cartesian anelastic finite difference code). Preliminary investigations of UNE's in canonical materials (granite, tuff and alluvium) confirm that emplacement conditions have a strong effect on seismic amplitudes and the generation of shear waves. Specifically, we find that motions from an explosion in high-strength, low-porosity granite have high compressional wave amplitudes and weak shear waves, while an explosion in low strength, high-porosity alluvium results in much weaker compressional waves and low-frequency compressional and shear waves of nearly equal amplitude. Further work will attempt to model available near-field seismic data from explosions conducted at NTS, where we have accurate characterization of the sub-surface from the wealth of geological and geophysical data from the former nuclear test program. Secondly, we are modeling seismic wave propagation with free-surface topography in WPP. We have model the October 9, 2006 and May 25, 2009 North Korean nuclear tests to investigate the impact of rugged topography on seismic waves. Preliminary results indicate that the topographic relief causes complexity in the direct P-waves that leads to azimuthally dependent behavior and the topographic gradient to the northeast, east and southeast of the presumed test locations generate stronger shear-waves, although each test gives a different pattern. Thirdly, we are modeling intermediate period motions (10-50 seconds) from earthquakes and explosions at regional distances. For these simulations we run SPECFEM3D{_}GLOBE (a spherical geometry spectral element code). We modeled broadband waveforms from well-characterized and well-observed events in the Middle East and central Asia, as well as the North Korean nuclear tests. For the recent North Korean test we found that the one-dimensional iasp91 model predicts the observed waveforms quite well in the band 20-50 seconds, while waveform fits for available 3D earth models are generally poor, with some exceptions. Interestingly 3D models can predict energy on the transverse component for an isotropic source presumably due to surface wave mode conversion and/or multipathing.

  2. Instrumentation for Nuclear Applications

    SciTech Connect (OSTI)

    NONE

    1998-09-18T23:59:59.000Z

    The objective of this project was to develop and coordinate nuclear instrumentation standards with resulting economies for the nuclear and radiation fields. There was particular emphasis on coordination and management of the Nuclear Instrument Module (NIM) System, U.S. activity involving the CAMAC international standard dataway system, the FASTBUS modular high-speed data acquisition and control system and processing and management of national nuclear instrumentation and detector standards, as well as a modest amount of assistance and consultation services to the Pollutant Characterization and Safety Research Division of the Office of Health and Environmental Research. The principal accomplishments were the development and maintenance of the NIM instrumentation system that is the predominant instrumentation system in the nuclear and radiation fields worldwide, the CAMAC digital interface system in coordination with the ESONE Committee of European Laboratories, the FASTBUS high-speed system and numerous national and international nuclear instrumentation standards.

  3. Modeling a Helical-coil Steam Generator in RELAP5-3D for the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    Nathan V. Hoffer; Piyush Sabharwall; Nolan A. Anderson

    2011-01-01T23:59:59.000Z

    Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant are currently being evaluated. A helical-coil steam generator is one heat exchanger design under consideration. Safety is an integral part of the helical-coil steam generator evaluation. Transient analysis plays a key role in evaluation of the steam generators safety. Using RELAP5-3D to model the helical-coil steam generator, a loss of pressure in the primary side of the steam generator is simulated. This report details the development of the steam generator model, the loss of pressure transient, and the response of the steam generator primary and secondary systems to the loss of primary pressure. Back ground on High Temperature Gas-cooled reactors, steam generators, the Next Generation Nuclear Plant is provided to increase the readers understanding of the material presented.

  4. Advanced Modeling and Evaluation of the Response of Base-Isolated Nuclear Facility Structures to Vertical Earthquake Excitation

    E-Print Network [OSTI]

    Keldrauk, Eric Scott

    2012-01-01T23:59:59.000Z

    Structures . iii 3 Nuclear Power Plants 3.1 Nuclear FacilityKashiwazaki-Kariwa Nuclear Power Plant 3.3.1 2004 Ch¯ uetsuno seismically-isolated nuclear plant has been constructed

  5. The 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12) Sheraton Station Square, Pittsburgh, Pennsylvania, U.S.A. September 30-October 4, 2007

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    DOMAIN SIMULATIONS FOR THE TWO-PHASE FLOW ENERGY BALANCE OF THE CLOTAIRE STEAM GENERATOR MOCK-UP Michel computation of the energy balance equation of a nuclear component. Considering the steam generator Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Pittsburg, Pennsylvania : United States (2007

  6. The 11th International Topical Meeting on Nuclear Thermal-Hydraulics (NURETH-11) Popes' Palace Conference Center, Avignon, France, October 2-6, 2005

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Conference Center, Avignon, France, October 2-6, 2005 Paper: 193 ON THE SIMULATION OF NUCLEAR POWER PLANT the industrial simulation of two-phase flows in the nuclear power plant components as steam generators (SG-scale methods (Angot et al. , 1993), good convergence properties, easy simulation of moving boundaries (for

  7. Nuclear-deformation energies according to a liquid-drop model with a sharp surface

    SciTech Connect (OSTI)

    Blocki, J.; Swiatecki, W.J.

    1982-05-01T23:59:59.000Z

    We present an atlas of 665 deformation-energy maps and 150 maps of other properties of interest, relevant for nuclear systems idealized as uniformly charged drops endowed with a surface tension. The nuclear shapes are parametrized in terms of two spheres modified by a smoothly fitted quadratic surface of revolution and are specified by three variables: asymmetry, sphere separation, and a neck variable (that goes over into a fragment-deformation variable after scission). The maps and related tables should be useful for the study of macroscopic aspects of nuclear fission and of collisions between any two nuclei in the periodic table.

  8. Water resources: sustainable water supply management and basin wide modelling Internationally it has been recognized that the most important challenge to ensuring sustainable

    E-Print Network [OSTI]

    Barthelat, Francois

    Water resources: sustainable water supply management and basin wide modelling Internationally it has been recognized that the most important challenge to ensuring sustainable water use is implementing integrated water resources management (IWRM). It provides the best framework for balancing

  9. Electrochemical-thermal modeling and microscale phase change for passive internal thermal management of lithium ion batteries.

    SciTech Connect (OSTI)

    Fuller, Thomas F. (Georgia Institute of Technology, Atlanta, GA); Bandhauer, Todd (Georgia Institute of Technology, Atlanta, GA); Garimella, Srinivas (Georgia Institute of Technology, Atlanta, GA)

    2012-01-01T23:59:59.000Z

    A fully coupled electrochemical and thermal model for lithium-ion batteries is developed to investigate the impact of different thermal management strategies on battery performance. In contrast to previous modeling efforts focused either exclusively on particle electrochemistry on the one hand or overall vehicle simulations on the other, the present work predicts local electrochemical reaction rates using temperature-dependent data on commercially available batteries designed for high rates (C/LiFePO{sub 4}) in a computationally efficient manner. Simulation results show that conventional external cooling systems for these batteries, which have a low composite thermal conductivity ({approx}1 W/m-K), cause either large temperature rises or internal temperature gradients. Thus, a novel, passive internal cooling system that uses heat removal through liquid-vapor phase change is developed. Although there have been prior investigations of phase change at the microscales, fluid flow at the conditions expected here is not well understood. A first-principles based cooling system performance model is developed and validated experimentally, and is integrated into the coupled electrochemical-thermal model for assessment of performance improvement relative to conventional thermal management strategies. The proposed cooling system passively removes heat almost isothermally with negligible thermal resistances between the heat source and cooling fluid. Thus, the minimization of peak temperatures and gradients within batteries allow increased power and energy densities unencumbered by thermal limitations.

  10. International Conference of Modeling, Optimization and Simulation -MOSIM'12 June 6-8, 2012 -Bordeaux -France

    E-Print Network [OSTI]

    Boyer, Edmond

    sources for its function:(1) an internal com- bustion engine, a fuel cell with an hydrogen tank or a solar on the energy sources chosen: fuel cells have a slow respon- siveness due to the chemical reaction inside on Figure 1: a fuel cell stack

  11. Simulation and Optimization Models for Scheduling Multi-step Sequential Procedures in Nuclear Medicine

    E-Print Network [OSTI]

    Perez Roman, Eduardo

    2011-08-08T23:59:59.000Z

    The rise in demand for specialized medical services in the U.S has been recognized as one of the contributors to increased health care costs. Nuclear medicine is a specialized service that uses relatively new technologies and radiopharmaceuticals...

  12. Characterization of a synthetic peroxodiiron(III) protein model complex by nuclear resonance vibrational spectroscopy

    E-Print Network [OSTI]

    Do, Loi Hung

    The vibrational spectrum of an ?[superscript 1],?[superscript 1]-1,2-peroxodiiron(III) complex was measured by nuclear resonance vibrational spectroscopy and fit using an empirical force field analysis. Isotopic 18O2 ...

  13. Process Monitoring for Nuclear Safeguards

    SciTech Connect (OSTI)

    Ehinger, Michael H [ORNL] [ORNL; Pomeroy, George D [ORNL] [ORNL; Budlong-Sylvester, Kory W [ORNL] [ORNL

    2009-01-01T23:59:59.000Z

    Process Monitoring has long been used to evaluate industrial processes and operating conditions in nuclear and non-nuclear facilities. In nuclear applications there is a recognized need to demonstrate the safeguards benefits from using advanced process monitoring on spent fuel reprocessing technologies and associated facilities, as a complement to nuclear materials accounting. This can be accomplished by: defining credible diversion pathway scenarios as a sample problem; using advanced sensor and data analysis techniques to illustrate detection capabilities; and formulating 'event detection' methodologies as a means to quantify performance of the safeguards system. Over the past 30 years there have been rapid advances and improvement in the technology associated with monitoring and control of industrial processes. In the context of bulk handling facilities that process nuclear materials, modern technology can provide more timely information on the location and movement of nuclear material to help develop more effective safeguards. For international safeguards, inspection means verification of material balance data as reported by the operator through the State to the international inspectorate agency. This verification recognizes that the State may be in collusion with the operator to hide clandestine activities, potentially during abnormal process conditions with falsification of data to mask the removal. Records provided may show material is accounted for even though a removal occurred. Process monitoring can offer additional fidelity during a wide variety of operating conditions to help verify the declaration or identify possible diversions. The challenge is how to use modern technology for process monitoring and control in a proprietary operating environment subject to safeguards inspectorate or other regulatory oversight. Under the U.S. National Nuclear Security Administration's Next Generation Safeguards Initiative, a range of potential safeguards applications for process monitoring are under conceptual development and evaluation. This paper reports on a study of process monitoring for a sample problem involving spent fuel reprocessing with aqueous reprocessing technologies. This includes modeling the processes in the context of a nuclear material diversion scenario and measuring the associated process chemistry. A systems-centric model is applied using actual and simulated plant data, advanced sensors, anomaly detection methods, statistical analysis and data authentication methods, to help illustrate the benefits of process monitoring applications.

  14. Quantitative Methodology for Assessing State-Level Nuclear Security Measures 

    E-Print Network [OSTI]

    Myers, Christopher 1985-

    2012-11-29T23:59:59.000Z

    international agreements that are either binding or non-binding. Unlike the international safeguards regime, which is governed primarily by the Treaty on Non-Proliferation of Nuclear Weapons, there is no verification regime for nuclear security or even...

  15. Application of a 2-D particle tracking model to simulate entrainment of winter flounder larvae at the Millstone Nuclear Power Station

    E-Print Network [OSTI]

    Dimou, Nadia K.

    1989-01-01T23:59:59.000Z

    A 2-D random walk model, developed by Dimou (1989) as part of this research project, was used to simulate entrainment at the Millstone Nuclear Power Station of winter flounder larvae hatched within Niantic River.

  16. Sabotage at Nuclear Power Plants

    SciTech Connect (OSTI)

    Purvis, James W.

    1999-07-21T23:59:59.000Z

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented.

  17. International Partnership on Mitigation and Measuring, Reporting...

    Open Energy Info (EERE)

    Organization German Federal Ministry for the Environment, Nature Conservancy and Nuclear Safety (BMU), German Agency for International Cooperation (GIZ) Sector Climate Focus...

  18. Cognitive decision errors and organization vulnerabilities in nuclear power plant safety management: Modeling using the TOGA meta-theory framework

    SciTech Connect (OSTI)

    Cappelli, M. [UTFISST, ENEA Casaccia, via Anguillarese 301, Rome (Italy); Gadomski, A. M. [ECONA, Centro Interuniversitario Elaborazione Cognitiva Sistemi Naturali e Artificiali, via dei Marsi 47, Rome (Italy); Sepiellis, M. [UTFISST, ENEA Casaccia, via Anguillarese 301, Rome (Italy); Wronikowska, M. W. [UTFISST, ENEA Casaccia, via Anguillarese 301, Rome (Italy); Poznan School of Social Sciences (Poland)

    2012-07-01T23:59:59.000Z

    In the field of nuclear power plant (NPP) safety modeling, the perception of the role of socio-cognitive engineering (SCE) is continuously increasing. Today, the focus is especially on the identification of human and organization decisional errors caused by operators and managers under high-risk conditions, as evident by analyzing reports on nuclear incidents occurred in the past. At present, the engineering and social safety requirements need to enlarge their domain of interest in such a way to include all possible losses generating events that could be the consequences of an abnormal state of a NPP. Socio-cognitive modeling of Integrated Nuclear Safety Management (INSM) using the TOGA meta-theory has been discussed during the ICCAP 2011 Conference. In this paper, more detailed aspects of the cognitive decision-making and its possible human errors and organizational vulnerability are presented. The formal TOGA-based network model for cognitive decision-making enables to indicate and analyze nodes and arcs in which plant operators and managers errors may appear. The TOGA's multi-level IPK (Information, Preferences, Knowledge) model of abstract intelligent agents (AIAs) is applied. In the NPP context, super-safety approach is also discussed, by taking under consideration unexpected events and managing them from a systemic perspective. As the nature of human errors depends on the specific properties of the decision-maker and the decisional context of operation, a classification of decision-making using IPK is suggested. Several types of initial situations of decision-making useful for the diagnosis of NPP operators and managers errors are considered. The developed models can be used as a basis for applications to NPP educational or engineering simulators to be used for training the NPP executive staff. (authors)

  19. International Conference of Modeling, Optimization and Simulation -MOSIM'12 June 6-8, 2012 -Bordeaux -France

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    of models as tool for fault diagnosis systems. Nowadays, industrial robots living in stochastic environment

  20. Internal noise driven generalized Langevin equation from a nonlocal continuum model

    E-Print Network [OSTI]

    Saikat Sarkar; Shubhankar Roy Chowdhury; Debasish Roy; Ram Mohan Vasu

    2015-03-10T23:59:59.000Z

    Starting with a micropolar formulation, known to account for nonlocal microstructural effects at the continuum level, a generalized Langevin equation (GLE) for a particle, describing the predominant motion of a localized region through a single displacement degree-of-freedom (DOF), is derived. The GLE features a memory dependent multiplicative or internal noise, which appears upon recognising that the micro-rotation variables possess randomness owing to an uncertainty principle. Unlike its classical version, the new GLE qualitatively reproduces the experimentally measured fluctuations in the steady-state mean square displacement of scattering centers in a polyvinyl alcohol slab. The origin of the fluctuations is traced to nonlocal spatial interactions within the continuum. A constraint equation, similar to a fluctuation dissipation theorem (FDT), is shown to statistically relate the internal noise to the other parameters in the GLE.

  1. Pantex Occupational Health System (OHS), National Nuclear Security...

    Broader source: Energy.gov (indexed) [DOE]

    Employees' Occupational Illness Compensation Program Occupational Medical Surveillance System (OMSS) PIA, Idaho National Laboratory PIA - 10th International Nuclear Graphite...

  2. Joint IAEA/NNSA International Workshop Nuclear Forensics Methodologies for Practitioners 2013 Scenario Based Exercise – Version 4.0 Instructor’s Manual

    SciTech Connect (OSTI)

    Schwantes, Jon M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Douglas, Matthew [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Morley, Shannon M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Hill, David [Australian Nuclear Science and Technology Organization, New South Wales (Australia); Thompson, Paul [AWE, Aldermasten (United Kingtom); Santi, Peter [Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Gassman, Paul L. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Meier, David E. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Pierson, Richard M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Wallenius, Maria [European Commission, Inst. for Transuranium Elements, Karlsruhe, (Germany); Marks, Naomi [Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)

    2013-10-01T23:59:59.000Z

    [Participants will serve as border guards for Reimerland. They will be given brief instruction on the operation of hand?held RadioIsotope DetectorS (RIDS) and be provided an intelligence briefing that tells them to be on the lookout for suspicious activity at their post. Their instruction will include directing suspicious vehicles to a location for secondary screening. If, after secondary screening, suspicions of a criminal act involving nuclear and or radioactive materials remain, participants have been instructed to request assistance from the NLEA, who will then setup and manage a radiological crime scene. Participants will watch a demonstration of two vehicles containing radioactive materials driving through and setting off a portal monitor. The first vehicle, a semi?tractor trailer, sets off only a gamma alarm. After the driver provides a shipping manifest of fertilizer, participants, posing as border guards, are expected to waive this vehicle through inspection. The second vehicle, an SUV, set off both gamma and 2 neutron alarms. The alarming of the neutron monitor should prompt participants to set up a secondary inspection of the vehicle immediately. The driver of the vehicle indicates he is in legal possession of an industrial instrument containing an old 133Ba source that has decayed to a level no longer requiring official paperwork according to the IAEA and internationally accepted transportation regulations. Authorities have verified that the industrial source does fit the description of one that is sold commercially. However, upon setting up a secondary screening, participants will use hand?held detectors to locate several other radioactive sources emanating from a black duffle bag in the rear of the vehicle (Figure 1). Hand held detectors detect the presence of 133Ba, and Pu. Upon questioning, the driver only commits to having the 133Ba industrial source and cannot account for the detection of neutrons within his vehicle. Since neutron alarms also sounded, participants should indicate that a neutron alarm would be inconsistent with a 133Ba source alone and should therefore conclude further investigation is warranted. This will prompt participants to call in a response team from the NLEA to set up a radiological crime scene around the vehicle in question. The response team is able to shoot a 3?D X?ray radiograph of the duffle bag without moving it to ensure it is rendered safe and moveable without disturbing the contents in the field (Figure 2). At this point, the duffle bag is entered into inventory as evidence and a chain of custody form is initiated. Swipes are taken from the outer bag to confirm there is no dispersible contamination. The bag and its contents are considered valuable for the investigation by the lead investigator. He determines the duffle bag is safe to transport to RRL for evidence inventory and analysis. The duffle bag and its contents are packaged and sent off to the RRL.

  3. Management of National Nuclear Power Programs for assured safety

    SciTech Connect (OSTI)

    Connolly, T.J. (ed.)

    1985-01-01T23:59:59.000Z

    Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

  4. Natural Circulation in Water Cooled Nuclear Power Plants Phenomena, models, and methodology for system reliability assessments

    SciTech Connect (OSTI)

    Jose Reyes

    2005-02-14T23:59:59.000Z

    In recent years it has been recognized that the application of passive safety systems (i.e., those whose operation takes advantage of natural forces such as convection and gravity), can contribute to simplification and potentially to improved economics of new nuclear power plant designs. In 1991 the IAEA Conference on ''The Safety of Nuclear Power: Strategy for the Future'' noted that for new plants the use of passive safety features is a desirable method of achieving simplification and increasing the reliability of the performance of essential safety functions, and should be used wherever appropriate''.

  5. International Conference on Microwave and RF Heating MODELING OF A CYLINDRICAL APPLICATOR WITH THE

    E-Print Network [OSTI]

    Yakovlev, Vadim

    by comprehensive modeling specifying appropriate parameters of the excitation system and monitoring the electric ____________________________________________________________________________________________ 423 MODELING OF A CYLINDRICAL APPLICATOR WITH THE TM01l MODE AND A SPHERICAL LOAD Vyacheslav V Polytechnic Institute, Worcester, MA, USA ABSTRACT The paper presents the results of 3D FDTD modeling of a 915

  6. Utility of Social Modeling for Proliferation Assessment - Enhancing a Facility-Level Model for Proliferation Resistance Assessment of a Nuclear Enegry System

    SciTech Connect (OSTI)

    Coles, Garill A.; Brothers, Alan J.; Gastelum, Zoe N.; Olson, Jarrod; Thompson, Sandra E.

    2009-10-26T23:59:59.000Z

    The Utility of Social Modeling for Proliferation Assessment project (PL09-UtilSocial) investigates the use of social and cultural information to improve nuclear proliferation assessments, including nonproliferation assessments, Proliferation Resistance (PR) assessments, safeguards assessments, and other related studies. These assessments often use and create technical information about a host State and its posture towards proliferation, the vulnerability of a nuclear energy system (NES) to an undesired event, and the effectiveness of safeguards. This objective of this project is to find and integrate social and technical information by explicitly considering the role of cultural, social, and behavioral factors relevant to proliferation; and to describe and demonstrate if and how social science modeling has utility in proliferation assessment. This report describes a modeling approach and how it might be used to support a location-specific assessment of the PR assessment of a particular NES. The report demonstrates the use of social modeling to enhance an existing assessment process that relies on primarily technical factors. This effort builds on a literature review and preliminary assessment performed as the first stage of the project and compiled in PNNL-18438. [ T his report describes an effort to answer questions about whether it is possible to incorporate social modeling into a PR assessment in such a way that we can determine the effects of social factors on a primarily technical assessment. This report provides: 1. background information about relevant social factors literature; 2. background information about a particular PR assessment approach relevant to this particular demonstration; 3. a discussion of social modeling undertaken to find and characterize social factors that are relevant to the PR assessment of a nuclear facility in a specific location; 4. description of an enhancement concept that integrates social factors into an existing, technically based nuclear facility assessment; 5. a discussion of a way to engage with the owners of the PR assessment methodology to assess and improve the enhancement concept; 6. a discussion of implementation of the proposed approach, including a discussion of functionality and potential users; and 7. conclusions from the research. This report represents technical deliverables for the NA-22 Simulations, Algorithms, and Modeling program. Specifically this report is the Task 2 and 3 deliverables for project PL09-UtilSocial.

  7. Dynamic Agent Based Modeling Using Bayesian Framework for Addressing Intelligence Adaptive Nuclear Nonproliferation Analysis

    E-Print Network [OSTI]

    Elmore, Royal A

    2014-10-03T23:59:59.000Z

    ...................................................... 59 Figure 3-6. Nuclear fuel cycle with commercial emphasis ............................................ 60 Figure 3-7. Uranium enrichment methods ..................................................................... 61 xi Page Figure 3...-8. Uranium enrichment precursors and post material management ................ 62 Figure 3-9. A pre-BANE specific to general reprocessing section with evidence......... 63 Figure 3-10. Plutonium reprocessing options...

  8. Organizational learning at nuclear power plants

    E-Print Network [OSTI]

    Carroll, John S.

    1991-01-01T23:59:59.000Z

    The Nuclear Power Plant Advisory Panel on Organizational Learning provides channels of communications between the management and organization research projects of the MIT International Program for Enhanced Nuclear Power ...

  9. Alpha-Cluster Model, Charge Symmetry of Nuclear Force and Single Particle Bound State Potential in Symmetrical Nuclei

    E-Print Network [OSTI]

    G. K. Nie

    2011-06-21T23:59:59.000Z

    A phenomenological alpha-cluster model based on the charge symmetry of nuclear force allows one to estimate the last proton position radius (LPPR) in a symmetrical nucleus. The values of LPPR obtained for the symmetrical nuclei with 5=15 it is inappropriate to represent a single particle bound state by the Woods-Saxon potential. For the nuclei with 5<=Z<=14 the error of the spectroscopic factor obtained with standard parameters in DWBA analysis of pure peripheral one nucleon transfer reactions is estimated. It is shown that for some nuclei using the standard parameters brings an error more than 20%.

  10. Fluctuation level bursts in a model of internal transport barrier formation D. Lopez-Bruna, D. E. Newman, and B. A. Carreras

    E-Print Network [OSTI]

    Newman, David

    features of ITB models the phase transition character with a power threshold, barrier front propagation radial electric field.10,11 As happens with the edge transport barriers, the system reacts to the extraFluctuation level bursts in a model of internal transport barrier formation D. Lo´pez-Bruna, D. E

  11. From International Computer Performance and Dependability Symposium, Erlangen, Germany, April 1995, pp.285 294 MODELING RECYCLE: A CASE STUDY IN THE INDUSTRIAL USE OF

    E-Print Network [OSTI]

    Illinois at Urbana-Champaign, University of

    85721 Center for Reliable and High-Performance Computing Coordinated Science Laboratory UniversityFrom International Computer Performance and Dependability Symposium, Erlangen, Germany, April 1995, pp.285 294 MODELING RECYCLE: A CASE STUDY IN THE INDUSTRIAL USE OF MEASUREMENT AND MODELING Luai M

  12. A Validation Process for the Groundwater Flow and Transport Model of the Faultless Nuclear Test at Central Nevada Test Area

    SciTech Connect (OSTI)

    Ahmed Hassan

    2003-01-01T23:59:59.000Z

    Many sites of groundwater contamination rely heavily on complex numerical models of flow and transport to develop closure plans. This has created a need for tools and approaches that can be used to build confidence in model predictions and make it apparent to regulators, policy makers, and the public that these models are sufficient for decision making. This confidence building is a long-term iterative process and it is this process that should be termed ''model validation.'' Model validation is a process not an end result. That is, the process of model validation cannot always assure acceptable prediction or quality of the model. Rather, it provides safeguard against faulty models or inadequately developed and tested models. Therefore, development of a systematic approach for evaluating and validating subsurface predictive models and guiding field activities for data collection and long-term monitoring is strongly needed. This report presents a review of model validation studies that pertain to groundwater flow and transport modeling. Definitions, literature debates, previously proposed validation strategies, and conferences and symposia that focused on subsurface model validation are reviewed and discussed. The review is general in nature, but the focus of the discussion is on site-specific, predictive groundwater models that are used for making decisions regarding remediation activities and site closure. An attempt is made to compile most of the published studies on groundwater model validation and assemble what has been proposed or used for validating subsurface models. The aim is to provide a reasonable starting point to aid the development of the validation plan for the groundwater flow and transport model of the Faultless nuclear test conducted at the Central Nevada Test Area (CNTA). The review of previous studies on model validation shows that there does not exist a set of specific procedures and tests that can be easily adapted and applied to determine the validity of site-specific groundwater models. This is true for both deterministic and stochastic models, with the latter posing a more difficult and challenging problem when it comes to validation. This report then proposes a general validation approach for the CNTA model, which addresses some of the important issues recognized in previous validation studies, conferences, and symposia as crucial to the process. The proposed approach links model building, model calibration, model predictions, data collection, model evaluations, and model validation in an iterative loop. The approach focuses on use of collected validation data to reduce model uncertainty and narrow the range of possible outcomes of stochastic numerical models. It accounts for the stochastic nature of the numerical CNTA model, which used Monte Carlo simulation approach. The proposed methodology relies on the premise that absolute validity is not even a theoretical possibility and is not a regulatory requirement. Rather, it highlights the importance of testing as many aspects of the model as possible and using as many diverse statistical tools as possible for rigorous checking and confidence building in the model and its predictions. It is this confidence that will eventually allow for regulator and public acceptance of decisions based on the model predictions.

  13. international journal of numerical modelling : electronic networks, devices and fields, Vol. 10, 217229 (1997)

    E-Print Network [OSTI]

    Bornemann, Jens

    , 217­229 (1997) SPECTRAL-DOMAIN MODELLING OF SUPERCONDUCTING MICROSTRIP STRUCTURES smain amari with available data to document the validity of the approach. © 1997 by John Wiley & Sons, Ltd. Int. J. Numer. Model., 10, 217­229 (1997) No. of Figures: 9. No. of Tables: 0. No. of References: 18. 1. INTRODUCTION

  14. Use of international data sets to evaluate and validate pathway assessment models applicable to exposure and dose reconstruction at DOE facilities. Progress report, August 1993--January 1994

    SciTech Connect (OSTI)

    Hendrickson, S.M. [ed.] [Lawrence Livermore National Lab., CA (United States)] [ed.; Lawrence Livermore National Lab., CA (United States); Hoffman, F.O. [Senes Oak Ridge, Inc., TN (United States). Center for Risk Analysis] [Senes Oak Ridge, Inc., TN (United States). Center for Risk Analysis

    1994-03-01T23:59:59.000Z

    This project, ``Use of International Data Sets to Evaluate and Validate Pathway Assessment Models Applicable to Exposure and Dose Reconstruction at DOE Facilities,`` grew out of several activities being conducted by the Principal Investigator Dr. F Owen Hoffman. One activity was originally part of the Chernobyl Studies Project and began as Task 7.1D, ``Internal Dose From Direct Contamination of Terrestrial Food Sources.`` The objective of Task 7.1D was to (1) establish a collaborative US USSR effort to improve and validate our methods of forecasting doses and dose commitments from the direct contamination of food sources, and (2) perform experiments and validation studies to improve our ability to predict rapidly and accurately the long-term internal dose from the contamination of agricultural soil. The latter was to include the consideration of remedial measures to block contamination of food grown on contaminated soil. The current objective of this project is to evaluate and validate pathway-assessment models applicable to exposure and dose reconstruction at DOE facilities through use of international data sets. This project incorporates the activity of Task 7.1D into a multinational effort to evaluate data used for the prediction of radionuclide transfer through agricultural and aquatic systems to humans. It also includes participation in two multinational studies, BIOMOVS (BIOspheric MOdel Validation Study) with the Swedish National Institute for Radiation Protection and VAMP (VAlidation of Model Predictions) with the International Atomic Energy Agency, that address testing the performance of models of radionuclide transport through foodchains.

  15. International Policy International Development

    E-Print Network [OSTI]

    Watson, Andrew

    Research Strategy 2006-2009 International Policy Energy Adaptation International Development Coasts Change Research. Our strategy builds upon our previous work on integrated assessment, energy, adaptation of time. In this spirit, the Centre reconfirms its vision statement: "The Tyndall Centre is the UK network

  16. Numerical simulations of the internal shock model in magnetized relativistic jets of blazars

    E-Print Network [OSTI]

    Rueda-Becerril, Jesus M; Aloy, Miguel A

    2015-01-01T23:59:59.000Z

    The internal shocks scenario in relativistic jets is used to explain the variability of the blazar emission. Recent studies have shown that the magnetic field significantly alters the shell collision dynamics, producing a variety of spectral energy distributions and light-curves patterns. However, the role played by magnetization in such emission processes is still not entirely understood. In this work we numerically solve the magnetohydodynamic evolution of the magnetized shells collision, and determine the influence of the magnetization on the observed radiation. Our procedure consists in systematically varying the shell Lorentz factor, relative velocity, and viewing angle. The calculations needed to produce the whole broadband spectral energy distributions and light-curves are computationally expensive, and are achieved using a high-performance parallel code.

  17. Nuclear Safety Regulatory Framework

    Broader source: Energy.gov (indexed) [DOE]

    overall Nuclear Safety Policy & ESH Goals Safety Basis Review and Approval In the DOE governance model, contractors responsible for the facility develop the safety basis and...

  18. The need for a characteristics-based approach to radioactive waste classification as informed by advanced nuclear fuel cycles using the fuel-cycle integration and tradeoffs (FIT) model

    SciTech Connect (OSTI)

    Djokic, D. [Department of Nuclear Engineering, University of California, Berkeley, 3115B Etcheverry Hall, Berkeley, CA 94720-1730 (United States); Piet, S.; Pincock, L.; Soelberg, N. [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)

    2013-07-01T23:59:59.000Z

    This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. Because heat generation is generally the most important factor limiting geological repository areal loading, this analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. Waste streams generated in different fuel cycles and their possible classification based on the current U.S. framework and international standards are discussed. It is shown that the effects of separating waste streams are neglected under a source-based radioactive waste classification system. (authors)

  19. Nuclear spirals in galaxies

    E-Print Network [OSTI]

    Witold Maciejewski

    2006-11-08T23:59:59.000Z

    Recent high-resolution observations indicate that nuclear spirals are often present in the innermost few hundred parsecs of disc galaxies. My models show that nuclear spirals form naturally as a gas response to non-axisymmetry in the gravitational potential. Some nuclear spirals take the form of spiral shocks, resulting in streaming motions in the gas, and in inflow comparable to the accretion rates needed to power local Active Galactic Nuclei. Recently streaming motions of amplitude expected from the models have been observed in nuclear spirals, confirming the role of nuclear spirals in feeding of the central massive black holes.

  20. Long-Term Planning for Nuclear Energy Systems Under Deep Uncertainty

    E-Print Network [OSTI]

    Kim, Lance Kyungwoo

    2011-01-01T23:59:59.000Z

    5.3.2 Nuclear Energy System Model . . . . . . . . . . .scenarios of global nuclear energy demand . . . . . . . .Brief History of Nuclear Energy . . . . . . . . Nuclear Fuel

  1. Progress in Understanding the Nuclear Equation of State at the Quark Level

    SciTech Connect (OSTI)

    A.W. Thomas; P.A.M. Guichon

    2007-01-03T23:59:59.000Z

    At the present time there is a lively debate within the nuclear community concerning the relevance of quark degrees of freedom in understanding nuclear structure. We outline the key issues and review the impressive progress made recently within the framework of the quark-meson coupling model. In particular, we explain in quite general terms how the modification of the internal structure of hadrons in-medium leads naturally to three- and four-body forces, or equivalently, to density dependent effective interactions.

  2. Nuclear Engineering Nuclear Criticality Safety

    E-Print Network [OSTI]

    Kemner, Ken

    development, Nuclear Operations Division (NOD) waste management and storage activities and other laboratoryNuclear Engineering Nuclear Criticality Safety The Nuclear Engineering Division (NE) of Argonne National Laboratory is experienced in performing criticality safety and shielding evaluations for nuclear

  3. Nuclear Science References Database

    E-Print Network [OSTI]

    B. Pritychenko; E. B?ták; B. Singh; J. Totans

    2014-07-08T23:59:59.000Z

    The Nuclear Science References (NSR) database together with its associated Web interface, is the world's only comprehensive source of easily accessible low- and intermediate-energy nuclear physics bibliographic information for more than 210,000 articles since the beginning of nuclear science. The weekly-updated NSR database provides essential support for nuclear data evaluation, compilation and research activities. The principles of the database and Web application development and maintenance are described. Examples of nuclear structure, reaction and decay applications are specifically included. The complete NSR database is freely available at the websites of the National Nuclear Data Center http://www.nndc.bnl.gov/nsr and the International Atomic Energy Agency http://www-nds.iaea.org/nsr.

  4. A Model of Global Learning: How Students Change Through International High-Impact Experiences 

    E-Print Network [OSTI]

    Redwine, Tobin Dean

    2014-12-12T23:59:59.000Z

    is warranted. The purpose of this study was to develop a model to explain the viewpoints of student changes by students who participate in a study abroad experience. To meet that purpose, three objectives were utilized. First, a qualitative phenomenology...

  5. HEATMAP©CHP - The International Standard for Modeling Combined Heat and Power Systems

    E-Print Network [OSTI]

    Bloomquist, R. G.; O'Brien, R. G.

    , regional, or national planners in defining all aspects of developing, evaluating, and justifying a new CHP project or upgrading an existing thermal system for CHP. Program output may be used to evaluate existing system performance or model the effects...

  6. Effective flow surface of porous materials with two populations of voids under internal pressure: I. a GTN model

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    ). Such a microstructure is typical of the highly irradiated uranium dioxide (UO2), a nuclear fuel commonly used in nuclear several studies on the mechanical behavior of highly irradiated nuclear fuels at different scales (Vincent to the effective plastic flow surface of a bi-porous material saturated by a fluid. The material under

  7. FASTGRASS: A mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions

    SciTech Connect (OSTI)

    Rest, J.; Zawadzki, S.A. (Argonne National Lab., IL (United States))

    1992-09-01T23:59:59.000Z

    The primary physical/chemical models that form the basis of the FASTGRASS mechanistic computer model for calculating fission-product release from nuclear fuel are described. Calculated results are compared with test data and the major mechanisms affecting the transport of fission products during steady-state and accident conditions are identified.

  8. Nuclear scales

    SciTech Connect (OSTI)

    Friar, J.L.

    1998-12-01T23:59:59.000Z

    Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the {pi}-{gamma} force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effectively parameterized by moments of the interaction that are independent of the details of the force model, in analogy to chiral perturbation theory. Results of GFMC calculations in light nuclei are interpreted in terms of fundamental scales, which are in good agreement with expectations from chiral effective field theories. Problems with spin-orbit-type observables are noted.

  9. International waste management fact book

    SciTech Connect (OSTI)

    Amaya, J.P.; LaMarche, M.N.; Upton, J.F.

    1997-10-01T23:59:59.000Z

    Many countries around the world are faced with nuclear and environmental management problems similar to those being addressed by the US Department of Energy. The purpose of this Fact Book is to provide the latest information on US and international organizations, programs, activities and key personnel to promote mutual cooperation to solve these problems. Areas addressed include all aspects of closing the commercial and nuclear fuel cycle and managing the wastes and sites from defense-related, nuclear materials production programs.

  10. Internal Control Program

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2008-10-28T23:59:59.000Z

    To ensure sound internal controls and overall consistency in exercising the statutory authorities that vest in the Secretary, the Administrator, National Nuclear Security Administration (NNSA), and Department's Chief Financial Officer (CFO), and to implement the Federal Managers' Financial Integrity Act of 1982 and related central agency guidance. Cancels DOE O 413.1A.

  11. NNSA and IAEA Hold the 20th International Training Course on...

    National Nuclear Security Administration (NNSA)

    Hold the 20th International Training Course on Nuclear Material Accounting and Control | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission...

  12. Energy and Atomic Mass Dependence of Nuclear Stopping Power in Relativistic Heavy-Ion Collisions in Interacting Gluon Model

    E-Print Network [OSTI]

    Q. J. Liu; W. Q. Chao; G. Wilk

    1995-04-05T23:59:59.000Z

    We present a Monte-Carlo simulation of energy deposition process in relativistic heavy-ion collisions based on a new realization of the Interacting-Gluon-Model (IGM) for high energy $N-N$ collisions. In particular we show results for proton spectra from collisions of $E_{lab}=200 \\ GeV/N$ $^{32}$S beam incident on $^{32}$S target and analyze the energy and mass dependence of nuclear stopping power predicted by our model. Theoretical predictions for proton rapidity distributions of both $^{208}$Pb + $^{208}$Pb collisions at $E_{lab}=160 \\ GeV/N$ CERN SPS and $^{197}$Au + $^{197}$Au at $\\sqrt{s_{NN}}=200 \\ GeV$ BNL RHIC are given.

  13. Spent nuclear fuel as a waste form for geologic disposal: Assessment and recommendations on data and modeling needs

    SciTech Connect (OSTI)

    Van Luik, A.E.; Apted, M.J.; Bailey, W.J.; Haberman, J.H.; Shade, J.S.; Guenther, R.E.; Serne, R.J.; Gilbert, E.R.; Peters, R.; Williford, R.E.

    1987-09-01T23:59:59.000Z

    This study assesses the status of knowledge pertinent to evaluating the behavior of spent nuclear fuel as a waste form in geologic disposal systems and provides background information that can be used by the DOE to address the information needs that pertain to compliance with applicable standards and regulations. To achieve this objective, applicable federal regulations were reviewed, expected disposal environments were described, the status of spent-fuel modeling was summarized, and information regarding the characteristics and behavior of spent fuel was compiled. This compiled information was then evaluated from a performance modeling perspective to identify further information needs. A number of recommendations were made concerning information still needed to enhance understanding of spent-fuel behavior as a waste form in geologic repositories. 335 refs., 22 figs., 44 tabs.

  14. Discrete Element Model for Simulations of Early-Life Thermal Fracturing Behaviors in Ceramic Nuclear Fuel Pellets

    SciTech Connect (OSTI)

    Hai Huang; Ben Spencer; Jason Hales

    2014-10-01T23:59:59.000Z

    A discrete element Model (DEM) representation of coupled solid mechanics/fracturing and heat conduction processes has been developed and applied to explicitly simulate the random initiations and subsequent propagations of interacting thermal cracks in a ceramic nuclear fuel pellet during initial rise to power and during power cycles. The DEM model clearly predicts realistic early-life crack patterns including both radial cracks and circumferential cracks. Simulation results clearly demonstrate the formation of radial cracks during the initial power rise, and formation of circumferential cracks as the power is ramped down. In these simulations, additional early-life power cycles do not lead to the formation of new thermal cracks. They do, however clearly indicate changes in the apertures of thermal cracks during later power cycles due to thermal expansion and shrinkage. The number of radial cracks increases with increasing power, which is consistent with the experimental observations.

  15. NUCLEAR FLUID DYNAMICS VERSUS INTRANUCLEAR CASCADE--POSSIBLE EVIDENCE FOR COLLECTIVE FLOW IN CENTRAL HIGH ENERGY NUCLEAR COLLISIONS

    E-Print Network [OSTI]

    Stocker, H.

    2012-01-01T23:59:59.000Z

    Flow in Central High Energy Nuclear Collisions H. Stockera,theoretical models of high energy nuclear collisions andunder Contract High energy nuclear collisions offer a unique

  16. Environmental Aspects of Advanced Nuclear Fuel Cycles: Parametric Modeling and Preliminary Analysis

    E-Print Network [OSTI]

    Yancey, Kristina D.

    2010-07-14T23:59:59.000Z

    High-enriched uranium, or uranium that has an enrichment of more than 20% 235U HLW High Level Waste, the highly radioactive materials produced by nuclear reactors MWe Megawatt electric, the amount of power entering the electrical grid LEU Low-enriched... uranium, or uranium that has an enrichment of less than 20% 235U Sievert Unit describing biological effects of radiation such that 1 Sievert is equal to 1 Joule/kilogram, abbreviated Sv tHM tonne Heavy Metal tonne A measurement of mass such that 1...

  17. International Conference of Modeling, Optimization and Simulation -MOSIM'12 June 6-8, 2012 -Bordeaux -France

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    manufacturers. While many models of hybrid cars have been devel- oped and put on the market in the last few Environment for Assessing Power Management Strategies in Hybrid Motorcycles Alessandro Beghi, Fabio Maran of transportation systems is a world wide priority. Hybrid propulsion vehicles have proved to have a strong

  18. Turbulent models of ice giant internal dynamics: Dynamos, heat transfer, and zonal flows

    E-Print Network [OSTI]

    , atmospheric circulation patterns, and thermal emissions that are distinct from other planets in our Solar additional constraints and suggest that these plan- ets may be modeled as three nested regions: (i) an outermost molecular envelope largely composed of hydrogen and helium; (ii) a weakly conducting ionic ocean

  19. THE INTERNATIONAL JOURNAL OF ROBOTICS RESEARCH, VOL. , NO. , 1 Local model of interaction for haptic manipulation

    E-Print Network [OSTI]

    Constantinescu, Daniela

    to doctors who would learn brain surgery on computer models rather than on animal or human patients. Due for haptic manipulation of rigid virtual worlds Daniela Constantinescu, Septimiu E. Salcudean, Elizabeth A with convincing kinesthetic feed- back while they manipulate a virtual tool within a rigid multibody virtual world

  20. Collective enhancement of nuclear state densities by the shell model Monte Carlo approach

    E-Print Network [OSTI]

    C. Özen; Y. Alhassid; H. Nakada

    2015-01-22T23:59:59.000Z

    The shell model Monte Carlo (SMMC) approach allows for the microscopic calculation of statistical and collective properties of heavy nuclei using the framework of the configuration-interaction shell model in very large model spaces. We present recent applications of the SMMC method to the calculation of state densities and their collective enhancement factors in rare-earth nuclei.