Sample records for advanced nuclear transformation

  1. March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE

    Broader source: Energy.gov [DOE]

    The Global Nuclear Energy Partnership (GNEP) marks a major change in the direction of the DOE’s nuclear energy R&D program. It is a coherent plan to test technologies that promise to markedly...

  2. October 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE

    Broader source: Energy.gov [DOE]

    The Global Nuclear Energy Partnership (GNEP) program is still evolving. Since our report of March 22, 2006 the DOE has sought to gauge industry interest in participation in the program from its...

  3. Draft Advanced Nuclear Energy Projects Solicitation | Department...

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

    Draft Advanced Nuclear Energy Projects Solicitation Draft Advanced Nuclear Energy Projects Solicitation INFORMATIONAL MATERIALS DRAFT ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION...

  4. Draft Advanced Nuclear Energy Solicitation Public Meeting Presentation...

    Office of Environmental Management (EM)

    Draft Advanced Nuclear Energy Solicitation Public Meeting Presentation Draft Advanced Nuclear Energy Solicitation Public Meeting Presentation Draft Advanced Nuclear Solicitation...

  5. Advanced Nuclear Fuel Cycle Options

    SciTech Connect (OSTI)

    Roald Wigeland; Temitope Taiwo; Michael Todosow; William Halsey; Jess Gehin

    2010-06-01T23:59:59.000Z

    A systematic evaluation has been conducted of the potential for advanced nuclear fuel cycle strategies and options to address the issues ascribed to the use of nuclear power. Issues included nuclear waste management, proliferation risk, safety, security, economics and affordability, and sustainability. The two basic strategies, once-through and recycle, and the range of possibilities within each strategy, are considered for all aspects of the fuel cycle including options for nuclear material irradiation, separations if needed, and disposal. Options range from incremental changes to today’s implementation to revolutionary concepts that would require the development of advanced nuclear technologies.

  6. Advanced nuclear fuel

    ScienceCinema (OSTI)

    Terrani, Kurt

    2014-07-15T23:59:59.000Z

    Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

  7. Advanced nuclear fuel

    SciTech Connect (OSTI)

    Terrani, Kurt

    2014-07-14T23:59:59.000Z

    Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

  8. ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE

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

    of spallation neutron spectra up to 20-25 MeV for 600 MeV proton and 50 MeV electron beams. However, the neutron flux is small. Even though studies of ADS will continue as part...

  9. ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE

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

    to evaluate the physics, startup, and operation of a coupled accelerator and subcritical system. Activities to support development of a target for ADSs. Transmutation...

  10. Transformational advances in knowledge and technology come

    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 on Delicious Rank EERE:YearRound-Up from theDepartment of EnergyThe Sun andDepartmentTransformational advances in

  11. Advanced nuclear plant control complex

    DOE Patents [OSTI]

    Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

    1993-01-01T23:59:59.000Z

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

  12. Transforming the advanced lab: Part I -Learning goals Benjamin Zwickl

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    Transforming the advanced lab: Part I - Learning goals Benjamin Zwickl , Noah Finkelstein and H. J-division undergraduate level. As part of transforming our senior-level Optics and Modern Physics Lab at the University, 01.40.Fk, 01.50.Qb INTRODUCTION At the University of Colorado Boulder (CU), we are transforming our

  13. Energy Department Announces New Investments in Advanced Nuclear...

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

    Announces New Investments in Advanced Nuclear Power Reactors Energy Department Announces New Investments in Advanced Nuclear Power Reactors October 31, 2014 - 12:20pm Addthis NEWS...

  14. Energy Department Announces New Awards for Advanced Nuclear Energy...

    Energy Savers [EERE]

    Announces New Awards for Advanced Nuclear Energy Development Energy Department Announces New Awards for Advanced Nuclear Energy Development April 16, 2015 - 12:46pm Addthis NEWS...

  15. Sandia National Laboratories: Advanced Nuclear Energy

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0Energy Advanced Nuclear Energy The Advanced Nuclear EnergyNuclear

  16. Global Nuclear Energy Partnership Fact Sheet - Develop Advanced...

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

    Advanced Burner Reactors Global Nuclear Energy Partnership Fact Sheet - Develop Advanced Burner Reactors GNEP will develop and demonstrate Advanced Burner Reactors (ABRs) that...

  17. Sandia National Laboratories: Advanced Nuclear Energy

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0Energy Advanced Nuclear Energy The Advanced Nuclear Energy

  18. Advancing our Nuclear Collaboration with the Czech Republic ...

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

    our Nuclear Collaboration with the Czech Republic Advancing our Nuclear Collaboration with the Czech Republic September 28, 2011 - 5:36pm Addthis President Obama addresses a crowd...

  19. Computational Design of Advanced Nuclear Fuels

    SciTech Connect (OSTI)

    Savrasov, Sergey; Kotliar, Gabriel; Haule, Kristjan

    2014-06-03T23:59:59.000Z

    The objective of the project was to develop a method for theoretical understanding of nuclear fuel materials whose physical and thermophysical properties can be predicted from first principles using a novel dynamical mean field method for electronic structure calculations. We concentrated our study on uranium, plutonium, their oxides, nitrides, carbides, as well as some rare earth materials whose 4f eletrons provide a simplified framework for understanding complex behavior of the f electrons. We addressed the issues connected to the electronic structure, lattice instabilities, phonon and magnon dynamics as well as thermal conductivity. This allowed us to evaluate characteristics of advanced nuclear fuel systems using computer based simulations and avoid costly experiments.

  20. Nuclear Advances | Y-12 National Security Complex

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurity ComplexNormanNovemberAdvances Nuclear

  1. Advanced nuclear plant control room complex

    DOE Patents [OSTI]

    Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

    1993-01-01T23:59:59.000Z

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

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

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

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

  3. Generation IV Advanced Nuclear Energy Systems By Jacques Bouchard...

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

    Generation IV Advanced Nuclear Energy Systems By Jacques Bouchard, French Commissariat a l'Energie Atomique, France and Ralph Bennett, Idaho National Laboratory. Generation IV...

  4. KRNFYSIK, FRDJUPNINGSKURS FKF 021 Nuclear Physics, Advanced Course I

    E-Print Network [OSTI]

    K�RNFYSIK, F�RDJUPNINGSKURS FKF 021 Nuclear Physics, Advanced Course I Antal poäng: 5.0. Valfri för. Partikelfysik. Laborationerna är obligatoriska. Litteratur Krane, K.S.: Introductory Nuclear Physics

  5. KRNFYSIK, FRDJUPNINGSKURS FKF021 Nuclear Physics, Advanced Course I

    E-Print Network [OSTI]

    K�RNFYSIK, F�RDJUPNINGSKURS FKF021 Nuclear Physics, Advanced Course I Poäng: 5.0 Betygskala: TH. Partikelfysik. Laborationerna är obligatoriska. Litteratur: Krane, K.S.: Introductory Nuclear Physics

  6. Advancing Global Nuclear Security | Department of Energy

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

    OF THE NUCLEAR ENERGY AND NUCLEAR SECURITY WORKING GROUP OF THE BILATERAL U.S. - RUSSIA PRESIDENTIAL COMMISSION Secretary Moniz's Remarks at the 2014 IAEA General Conference...

  7. Department of Energy Issues Final $12.5 Billion Advanced Nuclear...

    Energy Savers [EERE]

    Final 12.5 Billion Advanced Nuclear Energy Loan Guarantee Solicitation Department of Energy Issues Final 12.5 Billion Advanced Nuclear Energy Loan Guarantee Solicitation December...

  8. Department of Advanced Energy Nuclear Fusion Research Education Program

    E-Print Network [OSTI]

    Yamamoto, Hirosuke

    23 Department of Advanced Energy Nuclear Fusion Research Education Program 22 8 24) (1) (2) (3) (4) (5) (6) (7) (8) #12;- 7 - 23 Guide to Nuclear Fusion Research Education@criepi.denken.or.jp tel: 046-856-2121 12 http://www. k.u-tokyo.ac.jp/fusion-pro/ #12;- 3 - (1) TOEFL TOEIC

  9. Department of Advanced Energy Nuclear Fusion Research Education Program

    E-Print Network [OSTI]

    Yamamoto, Hirosuke

    24 Department of Advanced Energy Nuclear Fusion Research Education Program 23 8 23 to Nuclear Fusion Research Education Program 277-8561 5-1-5 1 04-7136-4092 http://www.k.u-tokyo.ac.jp/fusion: nemoto@criepi.denken.or.jp tel: 046-856-2121 12 http://www. k.u-tokyo.ac.jp/fusion-pro/ #12

  10. Department of Advanced Energy Nuclear Fusion Research Education Program

    E-Print Network [OSTI]

    Yamamoto, Hirosuke

    25 Department of Advanced Energy Nuclear Fusion Research Education Program 24 8 21.Yasuhiro@jaxa.jp tel: 050-336-27836 mail: sakai@isas.jaxa.jp tel: 050-3362-5919 12 http://www. k.u-tokyo.ac.jp/fusion 15 (1) (2) (1) (2) (3) (4) (5) (6) (7) (8) (9) #12;- 8 - 25 Guide to Nuclear

  11. Department of Advanced Energy Nuclear Fusion Research Education Program

    E-Print Network [OSTI]

    Yamamoto, Hirosuke

    26 Department of Advanced Energy Nuclear Fusion Research Education Program 25 8 20) #12; 26 Guide to Nuclear Fusion Research Education Program 03-5841-6563 E-mail : ae: 050-336-27836 mail: sakai@isas.jaxa.jp tel: 050-3362-5919 , 7 12 http://www. k.u-tokyo.ac.jp/fusion

  12. Enterprise SRS: leveraging ongoing operations to advance nuclear fuel cycles research and development programs

    SciTech Connect (OSTI)

    Murray, A.M.; Marra, J.E.; Wilmarth, W.R. [Savannah River National Laboratory, Aiken, SC 29808 (United States); McGuire, P.W.; Wheeler, V.B. [Department of Energy-Savannah River Operations Office, Aiken SC 29808 (United States)

    2013-07-01T23:59:59.000Z

    The Savannah River Site (SRS) is re-purposing its vast array of assets (including H Canyon - a nuclear chemical separation plant) to solve issues regarding advanced nuclear fuel cycle technologies, nuclear materials processing, packaging, storage and disposition. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for 'all things nuclear' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into SRS facilities but also in other facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, a center for applied nuclear materials processing and engineering research has been established in SRS.

  13. Advances in instrumentation for nuclear astrophysics

    SciTech Connect (OSTI)

    Pain, S. D. [Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States)] [Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States)

    2014-04-15T23:59:59.000Z

    The study of the nuclear physics properties which govern energy generation and nucleosynthesis in the astrophysical phenomena we observe in the universe is crucial to understanding how these objects behave and how the chemical history of the universe evolved to its present state. The low cross sections and short nuclear lifetimes involved in many of these reactions make their experimental determination challenging, requiring developments in beams and instrumentation. A selection of developments in nuclear astrophysics instrumentation is discussed, using as examples projects involving the nuclear astrophysics group at Oak Ridge National Laboratory. These developments will be key to the instrumentation necessary to fully exploit nuclear astrophysics opportunities at the Facility for Rare Isotope Beams which is currently under construction.

  14. Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development

    SciTech Connect (OSTI)

    Jon Carmack

    2014-01-01T23:59:59.000Z

    The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. The TRL process has been developed and successfully used by the Department of Defense (DOD) for development and deployment of new technology and systems for defense applications. In addition, NASA has also successfully used the TRL process to develop and deploy new systems for space applications. Advanced nuclear fuels and materials development is a critical technology needed for closing the nuclear fuel cycle. Because the deployment of a new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management and tracking tool. This report provides definition of the technology readiness level assessment process as defined for use in assessing nuclear fuel technology development for the Advanced Fuel Campaign (AFC).

  15. Advanced Nuclear Reactors | Department of Energy

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth (AOD)ProductssondeadjustsondeadjustAbout the BuildingInnovation Portal AdvancedMethods

  16. advanced hybrid nuclear: Topics by E-print Network

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

    hybrid nuclear First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Advanced Review proteinorganicinorganic...

  17. advanced nuclear thermal: Topics by E-print Network

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

    nuclear thermal First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 New Thermal Imaging Camera Advances UNL...

  18. E-Print Network 3.0 - advanced nuclear research Sample Search...

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

    research Search Powered by Explorit Topic List Advanced Search Sample search results for: advanced nuclear research Page: << < 1 2 3 4 5 > >> 1 Los Alamos National Laboratory DOE...

  19. Aging of safety class 1E transformers in safety systems of nuclear power plants

    SciTech Connect (OSTI)

    Roberts, E.W.; Edson, J.L.; Udy, A.C. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

    1996-02-01T23:59:59.000Z

    This report discusses aging effects on safety-related power transformers in nuclear power plants. It also evaluates maintenance, testing, and monitoring practices with respect to their effectiveness in detecting and mitigating the effects of aging. The study follows the US Nuclear Regulatory Commission`s (NRC`s) Nuclear Plant-Aging Research approach. It investigates the materials used in transformer construction, identifies stressors and aging mechanisms, presents operating and testing experience with aging effects, analyzes transformer failure events reported in various databases, and evaluates maintenance practices. Databases maintained by the nuclear industry were analyzed to evaluate the effects of aging on the operation of nuclear power plants.

  20. Integration of advanced nuclear materials separation processes

    SciTech Connect (OSTI)

    Jarvinen, G.D.; Worl, L.A.; Padilla, D.D.; Berg, J.M.; Neu, M.P.; Reilly, S.D.; Buelow, S.

    1998-12-31T23:59:59.000Z

    This is the final report of a two-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). This project has examined the fundamental chemistry of plutonium that affects the integration of hydrothermal technology into nuclear materials processing operations. Chemical reactions in high temperature water allow new avenues for waste treatment and radionuclide separation.Successful implementation of hydrothermal technology offers the potential to effective treat many types of radioactive waste, reduce the storage hazards and disposal costs, and minimize the generation of secondary waste streams. The focus has been on the chemistry of plutonium(VI) in solution with carbonate since these are expected to be important species in the effluent from hydrothermal oxidation of Pu-containing organic wastes. The authors investigated the structure, solubility, and stability of the key plutonium complexes. Installation and testing of flow and batch hydrothermal reactors in the Plutonium Facility was accomplished. Preliminary testing with Pu-contaminated organic solutions gave effluent solutions that readily met discard requirements. A new effort in FY 1998 will build on these promising initial results.

  1. October 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Careerlumens_placard-green.epsEnergy SecondEfficiency Improvements inWeatherizationis

  2. January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.ProgramJulietipDepartmentJuneWhen I think of wind5, 2013Jane A.Draft

  3. Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of

    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 on Delicious RankCombustion | Department ofT ib l L dDepartmentnews-flashesEnergy by BrianVerizonBLUE PLAINSthe

  4. Basic Research Needs for Advanced Nuclear Systems. Report of the Basic Energy Sciences Workshop on Basic Research Needs for Advanced Nuclear Energy Systems, July 31-August 3, 2006

    SciTech Connect (OSTI)

    Roberto, J.; Diaz de la Rubia, T.; Gibala, R.; Zinkle, S.; Miller, J.R.; Pimblott, S.; Burns, C.; Raymond, K.; Grimes, R.; Pasamehmetoglu, K.; Clark, S.; Ewing, R.; Wagner, A.; Yip, S.; Buchanan, M.; Crabtree, G.; Hemminger, J.; Poate, J.; Miller, J.C.; Edelstein, N.; Fitzsimmons, T.; Gruzalski, G.; Michaels, G.; Morss, L.; Peters, M.; Talamini, K.

    2006-10-01T23:59:59.000Z

    The global utilization of nuclear energy has come a long way from its humble beginnings in the first sustained nuclear reaction at the University of Chicago in 1942. Today, there are over 440 nuclear reactors in 31 countries producing approximately 16% of the electrical energy used worldwide. In the United States, 104 nuclear reactors currently provide 19% of electrical energy used nationally. The International Atomic Energy Agency projects significant growth in the utilization of nuclear power over the next several decades due to increasing demand for energy and environmental concerns related to emissions from fossil plants. There are 28 new nuclear plants currently under construction including 10 in China, 8 in India, and 4 in Russia. In the United States, there have been notifications to the Nuclear Regulatory Commission of intentions to apply for combined construction and operating licenses for 27 new units over the next decade. The projected growth in nuclear power has focused increasing attention on issues related to the permanent disposal of nuclear waste, the proliferation of nuclear weapons technologies and materials, and the sustainability of a once-through nuclear fuel cycle. In addition, the effective utilization of nuclear power will require continued improvements in nuclear technology, particularly related to safety and efficiency. In all of these areas, the performance of materials and chemical processes under extreme conditions is a limiting factor. The related basic research challenges represent some of the most demanding tests of our fundamental understanding of materials science and chemistry, and they provide significant opportunities for advancing basic science with broad impacts for nuclear reactor materials, fuels, waste forms, and separations techniques. Of particular importance is the role that new nanoscale characterization and computational tools can play in addressing these challenges. These tools, which include DOE synchrotron X-ray sources, neutron sources, nanoscale science research centers, and supercomputers, offer the opportunity to transform and accelerate the fundamental materials and chemical sciences that underpin technology development for advanced nuclear energy systems. The fundamental challenge is to understand and control chemical and physical phenomena in multi-component systems from femto-seconds to millennia, at temperatures to 1000?C, and for radiation doses to hundreds of displacements per atom (dpa). This is a scientific challenge of enormous proportions, with broad implications in the materials science and chemistry of complex systems. New understanding is required for microstructural evolution and phase stability under relevant chemical and physical conditions, chemistry and structural evolution at interfaces, chemical behavior of actinide and fission-product solutions, and nuclear and thermomechanical phenomena in fuels and waste forms. First-principles approaches are needed to describe f-electron systems, design molecules for separations, and explain materials failure mechanisms. Nanoscale synthesis and characterization methods are needed to understand and design materials and interfaces with radiation, temperature, and corrosion resistance. Dynamical measurements are required to understand fundamental physical and chemical phenomena. New multiscale approaches are needed to integrate this knowledge into accurate models of relevant phenomena and complex systems across multiple length and time scales.

  5. ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS

    SciTech Connect (OSTI)

    Marra, J.

    2010-09-29T23:59:59.000Z

    Rising global energy demands coupled with increased environmental concerns point to one solution; they must reduce their dependence on fossil fuels that emit greenhouse gases. As the global community faces the challenge of maintaining sovereign nation security, reducing greenhouse gases, and addressing climate change nuclear power will play a significant and likely growing role. In the US, nuclear energy already provides approximately one-fifth of the electricity used to power factories, offices, homes, and schools with 104 operating nuclear power plants, located at 65 sites in 31 states. Additionally, 19 utilities have applied to the US Nuclear Regulatory Commission (NRC) for construction and operating licenses for 26 new reactors at 17 sites. This planned growth of nuclear power is occurring worldwide and has been termed the 'nuclear renaissance.' As major industrial nations craft their energy future, there are several important factors that must be considered about nuclear energy: (1) it has been proven over the last 40 years to be safe, reliable and affordable (good for Economic Security); (2) its technology and fuel can be domestically produced or obtained from allied nations (good for Energy Security); and (3) it is nearly free of greenhouse gas emissions (good for Environmental Security). Already an important part of worldwide energy security via electricity generation, nuclear energy can also potentially play an important role in industrial processes and supporting the nation's transportation sector. Coal-to-liquid processes, the generation of hydrogen and supporting the growing potential for a greatly increased electric transportation system (i.e. cars and trains) mean that nuclear energy could see dramatic growth in the near future as we seek to meet our growing demand for energy in cleaner, more secure ways. In order to address some of the prominent issues associated with nuclear power generation (i.e., high capital costs, waste management, and proliferation), the worldwide community is working to develop and deploy new nuclear energy systems and advanced fuel cycles. These new nuclear systems address the key challenges and include: (1) extracting the full energy value of the nuclear fuel; (2) creating waste solutions with improved long term safety; (3) minimizing the potential for the misuse of the technology and materials for weapons; (4) continually improving the safety of nuclear energy systems; and (5) keeping the cost of energy affordable.

  6. Foundational development of an advanced nuclear reactor integrated safety code.

    SciTech Connect (OSTI)

    Clarno, Kevin (Oak Ridge National Laboratory, Oak Ridge, TN); Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth (Ktech Corporation, Albuquerque, NM); Hooper, Russell Warren; Humphries, Larry LaRon

    2010-02-01T23:59:59.000Z

    This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

  7. Graduate School of Advanced Science and Engineering Cooperative Major in Nuclear Energy

    E-Print Network [OSTI]

    Kaji, Hajime

    Graduate School of Advanced Science and Engineering Cooperative Major in Nuclear Energy Master in Nuclear Energy Summary of Research Instruction Research Instruction Application Code Name Major in Nuclear Energy Master's Program Doctoral Program Summary of Research Instruction

  8. Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.

    SciTech Connect (OSTI)

    Palmiotti, G.; Cahalan, J.; Pfeiffer, P.; Sofu, T.; Taiwo, T.; Wei,T.; Yacout, A.; Yang, W.; Siegel, A.; Insepov, Z.; Anitescu, M.; Hovland,P.; Pereira, C.; Regalbuto, M.; Copple, J.; Willamson, M.

    2006-12-11T23:59:59.000Z

    This report presents requirements for advanced simulation of nuclear reactor and chemical processing plants that are of interest to the Global Nuclear Energy Partnership (GNEP) initiative. Justification for advanced simulation and some examples of grand challenges that will benefit from it are provided. An integrated software tool that has its main components, whenever possible based on first principles, is proposed as possible future approach for dealing with the complex problems linked to the simulation of nuclear reactor and chemical processing plants. The main benefits that are associated with a better integrated simulation have been identified as: a reduction of design margins, a decrease of the number of experiments in support of the design process, a shortening of the developmental design cycle, and a better understanding of the physical phenomena and the related underlying fundamental processes. For each component of the proposed integrated software tool, background information, functional requirements, current tools and approach, and proposed future approaches have been provided. Whenever possible, current uncertainties have been quoted and existing limitations have been presented. Desired target accuracies with associated benefits to the different aspects of the nuclear reactor and chemical processing plants were also given. In many cases the possible gains associated with a better simulation have been identified, quantified, and translated into economical benefits.

  9. Economic Benefits of Advanced Materials in Nuclear Power Systems

    SciTech Connect (OSTI)

    Busby, Jeremy T [ORNL

    2009-01-01T23:59:59.000Z

    One of the key obstacles for the commercial deployment of advanced fast reactors (for either transuranic element burning or power generation) is the capital cost. There is a perception of higher capital cost for fast reactor systems than advanced light water reactors (ALWR). However, the cost estimates for a fast reactor come with a large uncertainty due to the fact that far fewer fast reactors have been built than LWR facilities. Furthermore, the large variability of industrial cost estimates complicates accurate comparisons. For example, under the Gen IV program, the Japanese Sodium Fast Reactor (JSFR) has a capital cost estimate that is lower than current LWR s, and considerably lower than that for the PRISM design (which is arguably among the most mature of today s fast reactor designs). Further reductions in capital cost must be made in US fast reactor systems to be considered economically viable. Three key approaches for cost reduction can be pursued. These include design simplifications, new technologies that allow reduced capital costs, and simulation techniques that help optimize system design. While it is plausible that improved materials will provide opportunities for both simplified design and reduced capital cost, the economic benefit of advanced materials has not been quantitatively analyzed. The objective of this work is to examine the potential impact of advanced materials on the capital investment costs of fast nuclear reactors.

  10. Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants

    E-Print Network [OSTI]

    Anitescu, Mihai

    Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants ANL-AFCI-168 of Nuclear Reactor and Chemical Separation Plants ANL-AFCI-168 by G. Palmiotti, J. Cahalan, P. Pfeiffer, T;2 ANL-AFCI-168 Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants G

  11. E-Print Network 3.0 - advanced light-water nuclear Sample Search...

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

    by Explorit Topic List Advanced Search Sample search results for: advanced light-water nuclear Page: << < 1 2 3 4 5 > >> 1 1 Managed by UT-Battelle for the U.S. Department...

  12. Indicator system for advanced nuclear plant control complex

    DOE Patents [OSTI]

    Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

    1993-01-01T23:59:59.000Z

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

  13. E-Print Network 3.0 - advanced nuclear analytical Sample Search...

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

    power Update of the mit 2003 Summary: Engineering Director, Center for Advanced Nuclear Energy Systems PROFESSOR ERNEST J.MONIZ Cecil and Ida Green... of spent nuclear fuel into...

  14. Impact of Nuclear Energy Futures on Advanced Fuel Cycle Options

    SciTech Connect (OSTI)

    Brent W. Dixon; Steven J. Piet

    2004-10-01T23:59:59.000Z

    The Nuclear Waste Policy Act requires the Secretary of Energy to inform Congress before 2010 on the need for a second geologic repository for spent nuclear fuel. By that time, the spent fuel discharged from current commercial reactors will exceed the statutory limit of the first repository (63,000 MTiHM commercial, 7,000 MT non-commercial). There are several approaches to eliminate the need for another repository in this century. This paper presents a high-level analysis of these spent fuel management options in the context of a full range of possible nuclear energy futures. The analysis indicates the best option to implement varies depending on the nuclear energy future selected. The first step in understanding the need for different spent fuel management approaches is to understand the size of potential spent fuel inventories. A full range of potential futures for domestic commercial nuclear energy is considered. These energy futures are as follows: 1. Existing License Completion - Based on existing spent fuel inventories plus extrapolation of future plant-by-plant discharges until the end of each operating license, including known license extensions. 2. Extended License Completion - Based on existing spent fuel inventories plus a plant-by-plant extrapolation of future discharges assuming on all operating plants having one 20-year extension. 3. Continuing Level Energy Generation - Based on extension of the current ~100 GWe installed commercial base and average spent fuel discharge of 2100 MT/yr through the year 2100. 4. Continuing Market Share Generation – Based on a 1.8% compounded growth of the electricity market through the year 2100, matched by growing nuclear capacity and associated spent fuel discharge. 5. Growing Market Share Generation - Extension of current nuclear capacity and associated spent fuel discharge through 2100 with 3.2% growth representing 1.5% market growth (all energy, not just electricity) and 1.7% share growth. Share growth results in tripling market share by 2100 from the current 8.4% to 25%, equivalent to continuing the average market growth of last 50 years for an additional 100 years. Five primary spent fuel management strategies are assessed against each of the energy futures to determine the number of geological repositories needed and how the first repository would be used. The geological repository site at Yucca Mountain, Nevada, has the physical potential to accommodate all the spent fuel that will be generated by the current fleet of domestic commercial nuclear reactors, even with license extensions. If new nuclear plants are built in the future as replacements or additions, the United States will need to adopt spent fuel treatment to extend the life of the repository. Should a significant number of new nuclear plants be built, advanced fuel recycling will be needed to fully manage the spent fuel within a single repository. The analysis also considers the timeframe for most efficient implementation of new spent fuel management strategies. The mix of unprocessed spent fuel and processed high level waste in Yucca Mountain varies with each future and strategy. Either recycling must start before there is too much unprocessed waste emplaced or unprocessed waste will have to be retrieved later with corresponding costs. For each case, the latest date to implement reprocessing without subsequent retrieval is determined.

  15. NUCLEAR DATA RESOURCES FOR ADVANCED ANALYSIS AND SIMULATION.

    SciTech Connect (OSTI)

    PRITYCHENKO, B.

    2006-06-05T23:59:59.000Z

    The mission of the National Nuclear Data Center (NNDC) includes collection, evaluation, and dissemination of nuclear physics data for basic nuclear research and applied nuclear technologies. In 2004, to answer the needs of nuclear data users, NNDC completed a project to modernize storage and management of its databases and began offering new nuclear data Web services. Examples of nuclear reaction, nuclear structure and decay database applications along with a number of nuclear science codes are also presented.

  16. Enterprise SRS: Leveraging Ongoing Operations To Advance Nuclear Fuel Cycles Research And Development Programs

    SciTech Connect (OSTI)

    Murray, Alice M.; Marra, John E.; Wilmarth, William R.; Mcguire, Patrick W.; Wheeler, Vickie B.

    2013-07-03T23:59:59.000Z

    The Savannah River Site (SRS) is repurposing its vast array of assets to solve future national issues regarding environmental stewardship, national security, and clean energy. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for ''all things nuclear'' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, The Department of Energy, Savannah River Operations Office, Savannah River Nuclear Solutions, the Savannah River National Laboratory (SRNL) have established a center for applied nuclear materials processing and engineering research (hereafter referred to as the Center). The key proposition of this initiative is to bridge the gap between promising transformational nuclear fuel cycle processing discoveries and large commercial-scale-technology deployment by leveraging SRS assets as facilities for those critical engineering-scale demonstrations necessary to assure the successful deployment of new technologies. The Center will coordinate the demonstration of R&D technologies and serve as the interface between the engineering-scale demonstration and the R&D programs, essentially providing cradle-to-grave support to the research team during the demonstration. While the initial focus of the Center will be on the effective use of SRS assets for these demonstrations, the Center also will work with research teams to identify opportunities to perform research demonstrations at other facilities. Unique to this approach is the fact that these SRS assets will continue to accomplish DOE's critical nuclear material missions (e.g., processing in H-Canyon and plutonium storage in K-Area). Thus, the demonstration can be accomplished by leveraging the incremental cost of performing demonstrations without needing to cover the full operational cost of the facility. Current Center activities have been focused on integrating advanced safeguards monitoring technologies demonstrations into the SRS H-Canyon and advanced location technologies demonstrations into K-Area Materials Storage. These demonstrations are providing valuable information to researchers and customers as well as providing the Center with an improved protocol for demonstration management that can be exercised across the entire SRS (as well as to offsite venues) so that future demonstrations can be done more efficiently and provide an opportunity to utilize these unique assets for multiple purposes involving national laboratories, academia, and commercial entities. Key among the envisioned future demonstrations is the use of H-Canyon to demonstrate new nuclear materials separations technologies critical for advancing the mission needs DOE-Nuclear Energy (DOE-NE) to advance the research for next generation fuel cycle technologies. The concept is to install processing equipment on frames. The frames are then positioned into an H-Canyon cell and testing in a relevant radiological environment involving prototypic radioactive materials can be performed.

  17. Evaluation of advanced technologies for power transformers. Final report. Part I, November 1976-March 1979

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

    The high insulating strength of certain gases, such as sulfur hexafluoride, when used at high pressure, suggests that there may be advantages to compressed gases as the insulating fluid in power transformers. However, simply exchanging the oil for compressed gas in an otherwise conventional transformer design will not yield a significant overall advantage. Compressed gases present the engineer with properties which are quite different from mineral oil. If gases are to be used as the major insulating fluid in power transformers, then virtually all aspects of the insulation and cooling of the apparatus must be reconsidered, affording an opportunity to introduce new design concepts, new materials, and new construction techniques. In this program, the feasibility of using the following principal design concepts has been explored: sheet conductors for the windings; a system of sealed, self-contained, annular cooling ducts containing circulating cooling fluid to cool the windings; polymer film for turn-to-turn insulation; and compressed gas insulation. Experimental and analytical studies, described in this report, indicate that the sheet-wound, compressed-gas-insulated design should result in power transformers of significantly smaller size and weight when compared with oil-filled units of equivalent rating. These advanced technologies offer the opportunity for the design of more efficient power transformers.

  18. advanced nuclear reactor: Topics by E-print Network

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

    . . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

  19. advanced nuclear plant: Topics by E-print Network

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

    . . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

  20. advanced nuclear power: Topics by E-print Network

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

    . . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

  1. advanced nuclear plants: Topics by E-print Network

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

    . . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

  2. advanced nuclear reactors: Topics by E-print Network

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

    . . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

  3. 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...

  4. Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research

    SciTech Connect (OSTI)

    John Jackson; Todd Allen; Frances Marshall; Jim Cole

    2013-03-01T23:59:59.000Z

    The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue University’s Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called User’s Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. User’s week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

  5. Containment building : architecture between the city and advanced nuclear reactors

    E-Print Network [OSTI]

    Pauli, Lisa M

    2011-01-01T23:59:59.000Z

    Since the inception of nuclear energy research, the element thorium (Th) has been considered the superior fuel for nuclear reactions because of its potency, safety, abundance and reduced waste. Cold War agendas broke from ...

  6. Development and Analysis of Advanced High-Temperature Technology for Nuclear Heat Transport and Power Conversion

    SciTech Connect (OSTI)

    Per F. Peterson

    2010-03-01T23:59:59.000Z

    This project by the Thermal Hydraulics Research Laboratory at U.C. Berkeley Studied advanced high-temperature heat transport and power conversion technology, in support of the Nuclear Hydrogen Initiative and Generation IV.

  7. Developing improved nuclear magnetic resonance marginal oscillator spectrometers for advanced teaching laboratories

    E-Print Network [OSTI]

    Willingham, Frank Phillip

    1988-01-01T23:59:59.000Z

    DEVELOPING IMPROVED NUCLEAR MAGNETIC RESONANCE MARGINAL OSCILLATOR SPECTROMETERS FOR ADVANCED TEACHING LABORATORIES A Thesis by FRANK PHILLIP WILLINGHAM Submitted to the Office of Graduate Studies of Texas ASM University in partial... fulfillment of the requirements for the degree of MASTER OF SCIENCE D e cemb er 1988 Major Subject: Physics DEVELOPING IMPROVED NUCLEAR MAGNETIC RESONANCE MARGINAL OSCILLATOR SPECTROMETERS FOR ADVANCED TEACHING LABORATORIES A Thesis by FRANK PHILLIP...

  8. Energy Department Announces New Investments in Advanced Nuclear...

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

    said Energy Secretary Ernest Moniz. With support from the Energy Department, private industry and the Department's national laboratories have achieved significant advances that...

  9. Science based integrated approach to advanced nuclear fuel development - vision, approach, and overview

    SciTech Connect (OSTI)

    Unal, Cetin [Los Alamos National Laboratory; Pasamehmetoglu, Kemal [IDAHO NATIONAL LAB; Carmack, Jon [IDAHO NATIONAL LAB

    2010-01-01T23:59:59.000Z

    Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Rcactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems is critical. In order to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. The purpose of this paper is to identify the modeling and simulation approach in order to deliver predictive tools for advanced fuels development. The coordination between experimental nuclear fuel design, development technical experts, and computational fuel modeling and simulation technical experts is a critical aspect of the approach and naturally leads to an integrated, goal-oriented science-based R & D approach and strengthens both the experimental and computational efforts. The Advanced Fuels Campaign (AFC) and Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Integrated Performance and Safety Code (IPSC) are working together to determine experimental data and modeling needs. The primary objective of the NEAMS fuels IPSC project is to deliver a coupled, three-dimensional, predictive computational platform for modeling the fabrication and both normal and abnormal operation of nuclear fuel pins and assemblies, applicable to both existing and future reactor fuel designs. The science based program is pursuing the development of an integrated multi-scale and multi-physics modeling and simulation platform for nuclear fuels. This overview paper discusses the vision, goals and approaches how to develop and implement the new approach.

  10. Advanced Heat Exchanger Development for Molten Salts in Nuclear and Non Nuclear Systems

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Sabharwall, Piyush; Clark, Denis; Sridharan, Kumar; Zheng, Guiqiu; Anderson, Mark

    2014-12-01T23:59:59.000Z

    This study addresses present work concerned with advanced heat exchanger development for molten salt in nuclear and non nuclear thermal systems. The molten salt systems discussed herein use alloys, such as Hastelloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700°C. These alloys were diffusion welded, and the corresponding information is presented. Test specimens were prepared for exposing diffusion welds to molten salt environments. Hastelloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet material in Hastelloy N were corrosion tested in?58 mol% KF and 42 mol% ZrF4 at 650, 700, and 850°C for 200, 500, and 1,000 hours. Corrosion rates found were similar between welded and nonwelded materials, typically <10 mils per year. For materials of construction, nickel and alloys with dense nickel coatings are effectively inert to corrosion in fluorides, but not so in chlorides. Hence, additional testing of selected alloys for resistance to intergranular corrosion is needed, as is a determination of corrosion rate as a function of contaminant type and alloy composition with respect to chromium and carbon to better define the optimal chromium and carbon composition, independent of galvanic or differential solubility effects. Also presented is the division of the nuclear reactor and high temperature components per ASME standards, along with design requirements for a subcritical Rankine power cycle heat exchanger that has to overcome pressure difference of about 17 MPa.

  11. Advanced Heat Exchanger Development for Molten Salts in Nuclear and Non Nuclear Systems

    SciTech Connect (OSTI)

    Piyush Sabharwall; Denis Clark; Kumar Sridharan; Guiqiu Zheng; Mark Anderson

    2014-10-01T23:59:59.000Z

    This study addresses present work concerned with advanced heat exchanger development for molten salt in nuclear and non nuclear thermal systems. The molten salt systems discussed herein use alloys, such as Hastelloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700°C. These alloys were diffusion welded, and the corresponding information is presented. Test specimens were prepared for exposing diffusion welds to molten salt environments. Hastelloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet material in Hastelloy N were corrosion tested in?58 mol% KF and 42 mol% ZrF4 at 650, 700, and 850°C for 200, 500, and 1,000 hours. Corrosion rates found were similar between welded and nonwelded materials, typically <10 mils per year. For materials of construction, nickel and alloys with dense nickel coatings are effectively inert to corrosion in fluorides, but not so in chlorides. Hence, additional testing of selected alloys for resistance to intergranular corrosion is needed, as is a determination of corrosion rate as a function of contaminant type and alloy composition with respect to chromium and carbon to better define the optimal chromium and carbon composition, independent of galvanic or differential solubility effects. Also presented is the division of the nuclear reactor and high temperature components per ASME standards, along with design requirements for a subcritical Rankine power cycle heat exchanger that has to overcome pressure difference of about 17 MPa.

  12. Department of Mechanical and Nuclear Engineering Fall 2010 Advanced Cooled Compressor Diaphragms

    E-Print Network [OSTI]

    Demirel, Melik C.

    PENNSTATE Department of Mechanical and Nuclear Engineering Fall 2010 Advanced Cooled Compressor compressor that is cooled by circulating water through its diaphragm (isothermal compression instead in future efforts to make this advanced cooled compressor a reality in the CCS industry #12;

  13. Impact of Nuclear Energy Futures on Advanced Fuel Cycle Options

    SciTech Connect (OSTI)

    Dixon, B.W.; Piet, S.J.

    2004-10-03T23:59:59.000Z

    The Nuclear Waste Policy Act requires the Secretary of Energy to inform Congress before 2010 on the need for a second geologic repository for spent nuclear fuel. By that time, the spent fuel discharged from current commercial reactors will exceed the statutory limit of the first repository. There are several approaches to eliminate the need for another repository in this century. This paper presents a high-level analysis of these spent fuel management options in the context of a full range of possible nuclear energy futures. The analysis indicates the best option to implement varies depending on the nuclear energy future selected.

  14. advanced nuclear engineering: Topics by E-print Network

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

    engineering leaders from industry, government de Weck, Olivier L. 8 Nuclear Science & Engineering Plasma Physics and Fusion Websites Summary: Center Massachusetts Institute of...

  15. advanced nuclear fuels: Topics by E-print Network

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

    Fuel Cycles University of California eScholarship Repository Summary: uranium or thorium ores and production of nuclear fuel, anynuclear fuel strontium Sievert Trivalent...

  16. advanced nuclear fuel: Topics by E-print Network

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

    Fuel Cycles University of California eScholarship Repository Summary: uranium or thorium ores and production of nuclear fuel, anynuclear fuel strontium Sievert Trivalent...

  17. Restructuring the DOE Laboratory Complex to Advance Clean Energy, Environmental Sustainability, and a Global Future without Nuclear Weapons

    Broader source: Energy.gov [DOE]

    Restructuring the DOE Laboratory Complex to Advance Clean Energy, Environmental Sustainability, and a Global Future without Nuclear Weapons - December Commission meeting

  18. Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study

    SciTech Connect (OSTI)

    Kristine Barrett; Shannon Bragg-Sitton

    2012-09-01T23:59:59.000Z

    The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R&D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental improvements are required in the areas of nuclear fuel composition, cladding integrity, and the fuel/cladding interaction to allow power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an “accident tolerant” fuel system that would offer improved coping time under accident scenarios. With a development time of about 20 – 25 years, advanced fuel designs must be started today and proven in current reactors if future reactor designs are to be able to use them with confidence.

  19. advanced nuclear system: Topics by E-print Network

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

    nuclear system First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Design of radiation resistant metallic...

  20. advanced nuclear systems: Topics by E-print Network

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

    nuclear systems First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Design of radiation resistant metallic...

  1. Draft Advanced Nuclear Energy Projects Solicitation | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector General Office of Audit ServicesMirant Potomac River Compliance PlanMEMORANDUMDraft Advanced

  2. Advanced nuclear fuel cycles - Main challenges and strategic choices

    SciTech Connect (OSTI)

    Le Biez, V. [Corps des Mines, 35 bis rue Saint-Sabin, F-75011 Paris (France); Machiels, A.; Sowder, A. [Electric Power Research Institute, Inc. 3420, Hillview Avenue, Palo Alto, CA 94304 (United States)

    2013-07-01T23:59:59.000Z

    A graphical conceptual model of the uranium fuel cycles has been developed to capture the present, anticipated, and potential (future) nuclear fuel cycle elements. The once-through cycle and plutonium recycle in fast reactors represent two basic approaches that bound classical options for nuclear fuel cycles. Chief among these other options are mono-recycling of plutonium in thermal reactors and recycling of minor actinides in fast reactors. Mono-recycling of plutonium in thermal reactors offers modest savings in natural uranium, provides an alternative approach for present-day interim management of used fuel, and offers a potential bridging technology to development and deployment of future fuel cycles. In addition to breeder reactors' obvious fuel sustainability advantages, recycling of minor actinides in fast reactors offers an attractive concept for long-term management of the wastes, but its ultimate value is uncertain in view of the added complexity in doing so,. Ultimately, there are no simple choices for nuclear fuel cycle options, as the selection of a fuel cycle option must reflect strategic criteria and priorities that vary with national policy and market perspectives. For example, fuel cycle decision-making driven primarily by national strategic interests will likely favor energy security or proliferation resistance issues, whereas decisions driven primarily by commercial or market influences will focus on economic competitiveness.

  3. Energy Department Invests $67 Million to Advanced Nuclear Technology |

    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 on Delicious Rank EERE:Year in Review: TopEnergyIDIQBusiness CompetitionDepartment of Energy 7 Million to Advanced

  4. Advanced Nuclear Fuel | Y-12 National Security Complex

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth (AOD)ProductssondeadjustsondeadjustAbout the BuildingInnovation Portal AdvancedMethods forDevelopment

  5. Advanced Resin Cleaning System (ARCS) at Grand Gulf Nuclear Station

    SciTech Connect (OSTI)

    Asay, R.H.; Earls, J.E.; Naughton, M.D. [Centec 21, Inc., Santa Clara, CA (United States)

    1996-10-01T23:59:59.000Z

    Steam generation system in-core components can undergo serious material degradation by a variety of corrosion-related phenomena. These phenomena are largely controlled by boiler water (i.e. reactor water) chemistry which is strongly impacted by the performance of the condensate system mixed bed ion exchange units. In Boiling Water Reactors (BWR), the mixed bed ion exchange units not only provide protection from ionic contaminants, but also remove insoluble corrosion products by filtration/adsorption. These insoluble corrosion products removed by the ion exchange units must then be periodically cleaned from the resin bed by some process external to the BWR primary water loop. A unique resin cleaning process called the {open_quotes}Advanced Resin Cleaning System{close_quotes} (ARCS) was developed in the late 1980`s by members of CENTEC-XXI, located in Santa Clara, CA. This system, which has been successfully operated for several years at a Pressurized Water Reactor is highly efficient for removal of both insoluble corrosion products and anion/cation resin fines, and generates significantly less waste water than other cleaning methods. The ARCS was considered the most attractive method for meeting the demanding and costly resin cleaning needs of a BWR. A {open_quotes}Tailored Collaboration{close_quotes} project was initiated between EPRI, Entergy Operations (Grand Gulf Station), and CENTEC-XXI to demonstrate the {open_quotes}Advanced Resin Cleaning System{close_quotes} in a BWR.

  6. Cladding and Structural Materials for Advanced Nuclear Energy Systems

    SciTech Connect (OSTI)

    Was, G S; Allen, T R; Ila, D; C,; Levi,; Morgan, D; Motta, A; Wang, L; Wirth, B

    2011-06-30T23:59:59.000Z

    The goal of this consortium is to address key materials issues in the most promising advanced reactor concepts that have yet to be resolved or that are beyond the existing experience base of dose or burnup. The research program consists of three major thrusts: 1) high-dose radiation stability of advanced fast reactor fuel cladding alloys, 2) irradiation creep at high temperature, and 3) innovative cladding concepts embodying functionally-graded barrier materials. This NERI-Consortium final report represents the collective efforts of a large number of individuals over a period of three and a half years and included 9 PIs, 4 scientists, 3 post-docs and 12 students from the seven participating institutions and 8 partners from 5 national laboratories and 3 industrial institutions (see table). University participants met semi-annually and participants and partners met annually for meetings lasting 2-3 days and designed to disseminate and discuss results, update partners, address outstanding issues and maintain focus and direction toward achieving the objectives of the program. The participants felt that this was a highly successful program to address broader issues that can only be done by the assembly of a range of talent and capabilities at a more substantial funding level than the traditional NERI or NEUP grant. As evidence of the success, this group, collectively, has published 20 articles in archival journals and made 57 presentations at international conferences on the results of this consortium.

  7. Design of radiation resistant metallic multilayers for advanced nuclear systems

    SciTech Connect (OSTI)

    Zhernenkov, Mikhail, E-mail: zherne@bnl.gov, E-mail: gills@bnl.gov; Gill, Simerjeet, E-mail: zherne@bnl.gov, E-mail: gills@bnl.gov; Stanic, Vesna; DiMasi, Elaine; Kisslinger, Kim; Ecker, Lynne [Brookhaven National Laboratory, Upton, New York 11973 (United States); Baldwin, J. Kevin; Misra, Amit [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Demkowicz, M. J. [Department of Materials Science and Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States)

    2014-06-16T23:59:59.000Z

    Helium implantation from transmutation reactions is a major cause of embrittlement and dimensional instability of structural components in nuclear energy systems. Development of novel materials with improved radiation resistance, which is of the utmost importance for progress in nuclear energy, requires guidelines to arrive at favorable parameters more efficiently. Here, we present a methodology that can be used for the design of radiation tolerant materials. We used synchrotron X-ray reflectivity to nondestructively study radiation effects at buried interfaces and measure swelling induced by He implantation in Cu/Nb multilayers. The results, supported by transmission electron microscopy, show a direct correlation between reduced swelling in nanoscale multilayers and increased interface area per unit volume, consistent with helium storage in Cu/Nb interfaces in forms that minimize dimensional changes. In addition, for Cu/Nb layers, a linear relationship is demonstrated between the measured depth-dependent swelling and implanted He density from simulations, making the reflectivity technique a powerful tool for heuristic material design.

  8. Mapping Complexity Sources in Nuclear Power Plant Domains Understanding the sources of complexity in advanced Nuclear Power Plant (NPP) control rooms and their

    E-Print Network [OSTI]

    Cummings, Mary "Missy"

    Mapping Complexity Sources in Nuclear Power Plant Domains Understanding the sources of complexity in advanced Nuclear Power Plant (NPP) control rooms and their effects on human reliability is critical of complexity leveraging network theory. INTRODUCTION The nuclear power industry in United States has declined

  9. Office of Advanced Nuclear Research Office of Nuclear Energy, Science and Technology

    E-Print Network [OSTI]

    Integrate applicable work conducted in programs in the Offices of Nuclear Energy (Gen IV, NERI, I · FY 2010: Complete the design of a commercial-scale nuclear hydrogen production system · FY 2015 to budget uncertainties (risk/benefit) · Guide the development of technology to support decisions Develop

  10. Reactor Physics and Criticality Benchmark Evaluations for Advanced Nuclear Fuel - Final Technical Report

    SciTech Connect (OSTI)

    William Anderson; James Tulenko; Bradley Rearden; Gary Harms

    2008-09-11T23:59:59.000Z

    The nuclear industry interest in advanced fuel and reactor design often drives towards fuel with uranium enrichments greater than 5 wt% 235U. Unfortunately, little data exists, in the form of reactor physics and criticality benchmarks, for uranium enrichments ranging between 5 and 10 wt% 235U. The primary purpose of this project is to provide benchmarks for fuel similar to what may be required for advanced light water reactors (LWRs). These experiments will ultimately provide additional information for application to the criticality-safety bases for commercial fuel facilities handling greater than 5 wt% 235U fuel.

  11. The Path to Sustainable Nuclear Energy. Basic and Applied Research Opportunities for Advanced Fuel Cycles

    SciTech Connect (OSTI)

    Finck, P.; Edelstein, N.; Allen, T.; Burns, C.; Chadwick, M.; Corradini, M.; Dixon, D.; Goff, M.; Laidler, J.; McCarthy, K.; Moyer, B.; Nash, K.; Navrotsky, A.; Oblozinsky, P.; Pasamehmetoglu, K.; Peterson, P.; Sackett, J.; Sickafus, K. E.; Tulenko, J.; Weber, W.; Morss, L.; Henry, G.

    2005-09-01T23:59:59.000Z

    The objective of this report is to identify new basic science that will be the foundation for advances in nuclear fuel-cycle technology in the near term, and for changing the nature of fuel cycles and of the nuclear energy industry in the long term. The goals are to enhance the development of nuclear energy, to maximize energy production in nuclear reactor parks, and to minimize radioactive wastes, other environmental impacts, and proliferation risks. The limitations of the once-through fuel cycle can be overcome by adopting a closed fuel cycle, in which the irradiated fuel is reprocessed and its components are separated into streams that are recycled into a reactor or disposed of in appropriate waste forms. The recycled fuel is irradiated in a reactor, where certain constituents are partially transmuted into heavier isotopes via neutron capture or into lighter isotopes via fission. Fast reactors are required to complete the transmutation of long-lived isotopes. Closed fuel cycles are encompassed by the Department of Energy?s Advanced Fuel Cycle Initiative (AFCI), to which basic scientific research can contribute. Two nuclear reactor system architectures can meet the AFCI objectives: a ?single-tier? system or a ?dual-tier? system. Both begin with light water reactors and incorporate fast reactors. The ?dual-tier? systems transmute some plutonium and neptunium in light water reactors and all remaining transuranic elements (TRUs) in a closed-cycle fast reactor. Basic science initiatives are needed in two broad areas: ? Near-term impacts that can enhance the development of either ?single-tier? or ?dual-tier? AFCI systems, primarily within the next 20 years, through basic research. Examples: Dissolution of spent fuel, separations of elements for TRU recycling and transmutation Design, synthesis, and testing of inert matrix nuclear fuels and non-oxide fuels Invention and development of accurate on-line monitoring systems for chemical and nuclear species in the nuclear fuel cycle Development of advanced tools for designing reactors with reduced margins and lower costs ? Long-term nuclear reactor development requires basic science breakthroughs: Understanding of materials behavior under extreme environmental conditions Creation of new, efficient, environmentally benign chemical separations methods Modeling and simulation to improve nuclear reaction cross-section data, design new materials and separation system, and propagate uncertainties within the fuel cycle Improvement of proliferation resistance by strengthening safeguards technologies and decreasing the attractiveness of nuclear materials A series of translational tools is proposed to advance the AFCI objectives and to bring the basic science concepts and processes promptly into the technological sphere. These tools have the potential to revolutionize the approach to nuclear engineering R&D by replacing lengthy experimental campaigns with a rigorous approach based on modeling, key fundamental experiments, and advanced simulations.

  12. 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.

  13. A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles

    E-Print Network [OSTI]

    Djokic, Denia

    2013-01-01T23:59:59.000Z

    Nuclear   Fuel”,   Nuclear  Engineering  and  Technology,  in   Engineering  -­?  Nuclear  Engineering   and  the  in  Engineering  -­?  Nuclear  Engineering   and  the  

  14. 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.

  15. The Next Generation Nuclear Plant/Advanced Gas Reactor Fuel Irradiation Experiments in the Advanced Test Reactor

    SciTech Connect (OSTI)

    S. Blaine Grover

    2009-09-01T23:59:59.000Z

    The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradiating eight separate low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States, and will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of at least six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006, and the second experiment (AGR-2) is currently in the design phase. The design of test trains, as well as the support systems and fission product monitoring system that will monitor and control the experiment during irradiation will be discussed. In addition, the purpose and differences between the two experiments will be compared and the irradiation results to date on the first experiment will be presented.

  16. Spectroscopy of particle-phonon coupled states in 133Sb by the cluster transfer reaction of 132Sn on 7Li: an advanced test of nuclear interactions

    E-Print Network [OSTI]

    Leoni S, University of Milano and INFN Milano (Italy); Bocchi G, University of Milano and INFN Milano (Italy); Bottoni S, University of Milano and INFN Milano (Italy); Bracco A, University of Milano and INFN Milano (Italy); Camera F, University of Milano and INFN Milano (Italy; Crespi F, University of Milano and INFN Milano (Italy); Morales A, University of Milano and INFN Milano (Italy); Fornal B, IFJ-PAN Krakow (Poland); Szpak B, IFJ-PAN Krakow (Poland); Bednarczyk P, IFJ-PAN Krakow (Poland); Cieplicka N, IFJ-PAN Krakow (Poland); Krolas W, IFJ-PAN Krakow ( Poland); Maj A, IFJ-PAN Krakow (Poland); Rusek K, Heavy Ion Laboratory University of Warsaw (Poland); Bazzacco D, INFN Padova (Italy); Lunardi S, University of Padova and INFN Padova (Italy); Mengoni D, University of Padova and INFN Padova (Italy); Recchia F, University of Padova and INFN Padova (Italy); Ur C, INFN Padova (Italy); Valiente-Dobon J, LNL-INFN (Italy); Gramegna F, LNL-INFN (Italy); Marchi T, LNL-INFN (Italy); Huyse M, KU Leuven (Belgium); Raabe R, KU Leuven (Belgium); VanDuppen P, KU Leuven (Belgium); Sferrazza M, Université libre de Bruxelles (Belgium); Georgiev G, CSNSM Orsay (France); Blazhev A, Institut fur Kernphysik der Universitat zu Köln (Germany); Rosiak D, Institut fur Kernphysik der Universitat zu Köln (Germany); Siebeck B, Institut fur Kernphysik der Universitat zu Köln (Germany); Seidlitz M, Institut fur Kernphysik der Universitat zu Köln (Germany); Reiter P, Institut fur Kernphysik der Universitat zu Köln (Germany); Warr N, Institut fur Kernphysik der Universitat zu Koln (Germany); Hartig AL, TU Darmstadt (Germany); Henrich C, TU Darmstadt (Germany); Ilieva S, TU Darmstadt (Germany); Kroell T, TU Darmstadt (Germany); Thurauf M, TU Darmstadt (Germany); Gernhaeuser R, TU Munchen (Germany); Mucher D, TU Munchen (Germany); Janssens R, Argonne National Laboratory (USA); Carpenter MP, Argonne National Laboratory (USA); Zhu S, Argonne National Laboratory (USA); Kowalska M, ISOLDE-CERN (Switzerland); CERN. Geneva. ISOLDE and neutron Time-of-Flight Experiments Committee; INTC

    2014-01-01T23:59:59.000Z

    Spectroscopy of particle-phonon coupled states in 133Sb by the cluster transfer reaction of 132Sn on 7Li: an advanced test of nuclear interactions

  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. 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

    L. J. Hamilton Nuclear Reactor Analysis John Wiley and Sons,R. J. Neuhold, Introductury Nuclear Reactor Dynamics. ANSL. J. Hamilton Nuclear Reactor Analysis John Wiley and Sons,

  19. February 2004, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE

    Broader source: Energy.gov [DOE]

    The ANTT Subcommittee of NERAC met February 26th and 27th (S. Pillon absent) to begin a review of the potential role of transmutation technologies in increasing the capacity of the geological...

  20. Nuclear Systems Enhanced Performance Program, Maintenance Cycle Extension in Advanced Light Water Reactor Design

    SciTech Connect (OSTI)

    Professor Neill Todreas

    2001-10-01T23:59:59.000Z

    A renewed interest in new nuclear power generation in the US has spurred interest in developing advanced reactors with features which will address the public's concerns regarding nuclear generation. However, it is economic performance which will dictate whether any new orders for these plants will materialize. Economic performance is, to a great extent, improved by maximizing the time that the plant is on-line generating electricity relative to the time spent off-line conducting maintenance and refueling. Indeed, the strategy for the advanced light water reactor plant IRIS (International Reactor, Innovative and Secure) is to utilize an eight year operating cycle. This report describes a formalized strategy to address, during the design phase, the maintenance-related barriers to an extended operating cycle. The top-level objective of this investigation was to develop a methodology for injecting component and system maintainability issues into the reactor plant design process to overcome these barriers. A primary goal was to demonstrate the applicability and utility of the methodology in the context of the IRIS design. The first step in meeting the top-level objective was to determine the types of operating cycle length barriers that the IRIS design team is likely to face. Evaluation of previously identified regulatory and investment protection surveillance program barriers preventing a candidate operating PWR from achieving an extended (48 month) cycle was conducted in the context of the IRIS design. From this analysis, 54 known IRIS operating cycle length barriers were identified. The resolution methodology was applied to each of these barriers to generate design solution alternatives for consideration in the IRIS design. The methodology developed has been demonstrated to narrow the design space to feasible design solutions which enable a desired operating cycle length, yet is general enough to have broad applicability. Feedback from the IRIS design team indicates that the proposed solutions to the investigated operating cycle length barriers are both feasible and consistent with sound design practice.

  1. Systems Analysis of an Advanced Nuclear Fuel Cycle Based on a Modified UREX+3c Process

    SciTech Connect (OSTI)

    E. R. Johnson; R. E. Best

    2009-12-28T23:59:59.000Z

    The research described in this report was performed under a grant from the U.S. Department of Energy (DOE) to describe and compare the merits of two advanced alternative nuclear fuel cycles -- named by this study as the “UREX+3c fuel cycle” and the “Alternative Fuel Cycle” (AFC). Both fuel cycles were assumed to support 100 1,000 MWe light water reactor (LWR) nuclear power plants operating over the period 2020 through 2100, and the fast reactors (FRs) necessary to burn the plutonium and minor actinides generated by the LWRs. Reprocessing in both fuel cycles is assumed to be based on the UREX+3c process reported in earlier work by the DOE. Conceptually, the UREX+3c process provides nearly complete separation of the various components of spent nuclear fuel in order to enable recycle of reusable nuclear materials, and the storage, conversion, transmutation and/or disposal of other recovered components. Output of the process contains substantially all of the plutonium, which is recovered as a 5:1 uranium/plutonium mixture, in order to discourage plutonium diversion. Mixed oxide (MOX) fuel for recycle in LWRs is made using this 5:1 U/Pu mixture plus appropriate makeup uranium. A second process output contains all of the recovered uranium except the uranium in the 5:1 U/Pu mixture. The several other process outputs are various waste streams, including a stream of minor actinides that are stored until they are consumed in future FRs. For this study, the UREX+3c fuel cycle is assumed to recycle only the 5:1 U/Pu mixture to be used in LWR MOX fuel and to use depleted uranium (tails) for the makeup uranium. This fuel cycle is assumed not to use the recovered uranium output stream but to discard it instead. On the other hand, the AFC is assumed to recycle both the 5:1 U/Pu mixture and all of the recovered uranium. In this case, the recovered uranium is reenriched with the level of enrichment being determined by the amount of recovered plutonium and the combined amount of the resulting MOX. The study considered two sub-cases within each of the two fuel cycles in which the uranium and plutonium from the first generation of MOX spent fuel (i) would not be recycled to produce a second generation of MOX for use in LWRs or (ii) would be recycled to produce a second generation of MOX fuel for use in LWRs. The study also investigated the effects of recycling MOX spent fuel multiple times in LWRs. The study assumed that both fuel cycles would store and then reprocess spent MOX fuel that is not recycled to produce a next generation of LWR MOX fuel and would use the recovered products to produce FR fuel. The study further assumed that FRs would begin to be brought on-line in 2043, eleven years after recycle begins in LWRs, when products from 5-year cooled spent MOX fuel would be available. Fuel for the FRs would be made using the uranium, plutonium, and minor actinides recovered from MOX. For the cases where LWR fuel was assumed to be recycled one time, the 1st generation of MOX spent fuel was used to provide nuclear materials for production of FR fuel. For the cases where the LWR fuel was assumed to be recycled two times, the 2nd generation of MOX spent fuel was used to provide nuclear materials for production of FR fuel. The number of FRs in operation was assumed to increase in successive years until the rate that actinides were recovered from permanently discharged spent MOX fuel equaled the rate the actinides were consumed by the operating fleet of FRs. To compare the two fuel cycles, the study analyzed recycle of nuclear fuel in LWRs and FRs and determined the radiological characteristics of irradiated nuclear fuel, nuclear waste products, and recycle nuclear fuels. It also developed a model to simulate the flows of nuclear materials that could occur in the two advanced nuclear fuel cycles over 81 years beginning in 2020 and ending in 2100. Simulations projected the flows of uranium, plutonium, and minor actinides as these nuclear fuel materials were produced and consumed in a fleet of 100 1,000 MWe LWRs and in FRs. The model als

  2. THERMODYNAMIC AND KINETIC MODELING OF ADVANCED NUCLEAR FUELS - FINAL LDRD-ER REPORT

    SciTech Connect (OSTI)

    Turchi, P

    2011-11-28T23:59:59.000Z

    This project enhanced our theoretical capabilities geared towards establishing the basic science of a high-throughput protocol for the development of advanced nuclear fuel that should couple modern computational materials modeling and simulation tools, fabrication and characterization capabilities, and targeted high throughput performance testing experiments. The successful conclusion of this ER project allowed us to upgrade state-of-the-art modeling codes, and apply these modeling tools to ab initio energetics and thermodynamic assessments of phase diagrams of various mixtures of actinide alloys, propose a tool for optimizing composition of complex alloys for specific properties, predict diffusion behavior in diffusion couples made of actinide and transition metals, include one new equation in the LLNL phase-field AMPE code, and predict microstructure evolution during alloy coring. In FY11, despite limited funding, the team also initiated an experimental activity, with collaboration from Texas A&M University by preparing samples of nuclear fuels in bulk forms and for diffusion couple studies and metallic matrices, and performing preliminary characterization.

  3. Qualification issues associated with the use of advanced instrumentation and control systems hardware in nuclear power plants

    SciTech Connect (OSTI)

    Korsah, K. [Oak Ridge National Lab., TN (United States); Antonescu, C. [Nuclear Regulatory Commission, Rockville, MD (United States). Office of Nuclear Regulatory Research

    1993-10-01T23:59:59.000Z

    The instrumentation and control (I&C) systems in advanced reactors will make extensive use of digital controls, microprocessors, multiplexing, and Tiber-optic transmission. Elements of these advances in I&C have been implemented on some current operating plants. However, the widespread use of the above technologies, as well as the use of artificial intelligence with minimum reliance on human operator control of reactors, highlights the need to develop standards for qualifying I&C used in the next generation of nuclear power plants. As a first step in this direction, the protection system I&C for present-day plants was compared to that proposed for advanced light water reactors (ALWRs). An evaluation template was developed by assembling a configuration of a safety channel instrument string for a generic ALWR, then comparing the impact of environmental stressors on that string to their effect on an equivalent instrument string from an existing light water reactor. The template was then used to address reliability issues for microprocessor-based protection systems. Standards (or lack thereof) for the qualification of microprocessor-based safety I&C systems were also identified. This approach addresses in part issues raised in Nuclear Regulatory Commission policy document SECY-91-292. which recognizes that advanced I&C systems for the nuclear industry are ``being developed without consensus standards, as the technology available for design is ahead of the technology that is well understood through experience and supported by application standards.``

  4. 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.

  5. Improved best estimate plus uncertainty methodology including advanced validation concepts to license evolving nuclear reactors

    SciTech Connect (OSTI)

    Unal, Cetin [Los Alamos National Laboratory; Williams, Brian [Los Alamos National Laboratory; Mc Clure, Patrick [Los Alamos National Laboratory; Nelson, Ralph A [IDAHO NATIONAL LAB

    2010-01-01T23:59:59.000Z

    Many evolving nuclear energy programs plan to use advanced predictive multi-scale multi-physics simulation and modeling capabilities to reduce cost and time from design through licensing. Historically, the role of experiments was primary tool for design and understanding of nuclear system behavior while modeling and simulation played the subordinate role of supporting experiments. In the new era of multi-scale multi-physics computational based technology development, the experiments will still be needed but they will be performed at different scales to calibrate and validate models leading predictive simulations. Cost saving goals of programs will require us to minimize the required number of validation experiments. Utilization of more multi-scale multi-physics models introduces complexities in the validation of predictive tools. Traditional methodologies will have to be modified to address these arising issues. This paper lays out the basic aspects of a methodology that can be potentially used to address these new challenges in design and licensing of evolving nuclear technology programs. The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. An enhanced calibration concept is introduced and is accomplished through data assimilation. The goal is to enable best-estimate prediction of system behaviors in both normal and safety related environments. To achieve this goal requires the additional steps of estimating the domain of validation and quantification of uncertainties that allow for extension of results to areas of the validation domain that are not directly tested with experiments, which might include extension of the modeling and simulation (M&S) capabilities for application to full-scale systems. The new methodology suggests a formalism to quantify an adequate level of validation (predictive maturity) with respect to required selective data so that required testing can be minimized for cost saving purposes by showing further testing wold not enhance the quality of the validation of predictive tools. The proposed methodology is at a conceptual level. When matured and if considered favorably by the stakeholders, it could serve as a new framework for the next generation of the best estimate plus uncertainty licensing methodology that USNRC developed previously. In order to come to that level of maturity it is necessary to communicate the methodology to scientific, design and regulatory stakeholders for discussion and debates. This paper is the first step to establish this communication.

  6. Advances

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth (AOD)ProductssondeadjustsondeadjustAbout the BuildingInnovation PortalScienceScripting forAdvances in

  7. 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.

  8. Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels

    SciTech Connect (OSTI)

    Lu, Hongbing; Bukkapatnam, Satish; Harimkar, Sandip; Singh, Raman; Bardenhagen, Scott

    2014-01-09T23:59:59.000Z

    Enhancing performance of fuel cladding and duct alloys is a key means of increasing fuel burnup. This project will address the failure of fuel cladding via three-dimensional cracking models. Researchers will develop a simulation code for the failure of the fuel cladding and validate the code through experiments. The objective is to develop an algorithm to determine the failure of fuel cladding in the form of three-dimensional cracking due to prolonged exposure under varying conditions of pressure, temperature, chemical environment, and irradiation. This project encompasses the following tasks: 1. Simulate 3D crack initiation and growth under instantaneous and/or fatigue loads using a new variant of the material point method (MPM); 2. Simulate debonding of the materials in the crack path using cohesive elements, considering normal and shear traction separation laws; 3. Determine the crack propagation path, considering damage of the materials incorporated in the cohesive elements to allow the energy release rate to be minimized; 4. Simulate the three-dimensional fatigue crack growth as a function of loading histories; 5. Verify the simulation code by comparing results to theoretical and numerical studies available in the literature; 6. Conduct experiments to observe the crack path and surface profile in unused fuel cladding and validate against simulation results; and 7. Expand the adaptive mesh refinement infrastructure parallel processing environment to allow adaptive mesh refinement at the 3D crack fronts and adaptive mesh merging in the wake of cracks. Fuel cladding is made of materials such as stainless steels and ferritic steels with added alloying elements, which increase stability and durability under irradiation. As fuel cladding is subjected to water, chemicals, fission gas, pressure, high temperatures, and irradiation while in service, understanding performance is essential. In the fast fuel used in advanced burner reactors, simulations of the nuclear fuels are critical to understand the burnup, and thus the fuel efficiency.

  9. E-Print Network 3.0 - advanced nuclear technology Sample Search...

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

    : Objectives: Develop and demonstrate technologies for detecting the stages of a foreign nuclear weapons... and Testing Nonproliferation Enabling Technologies ... Source:...

  10. E-Print Network 3.0 - advancing nuclear technology Sample Search...

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

    : Objectives: Develop and demonstrate technologies for detecting the stages of a foreign nuclear weapons... and Testing Nonproliferation Enabling Technologies ... Source:...

  11. Analyzing the proliferation resistance of advanced nuclear fuel cycles : in search of an assessment methodology for use in fuel cycle simulations

    E-Print Network [OSTI]

    Pierpoint, Lara Marie

    2008-01-01T23:59:59.000Z

    A methodology to assess proliferation resistance of advanced nuclear energy systems is investigated. The framework, based on Multi-Attribute Utility Theory (MAUT), is envisioned for use within early-stage fuel cycle ...

  12. E-Print Network 3.0 - advanced nuclear precleaner Sample Search...

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

    Colloque C2, suppl. au Journal de Physique 11, Vol. 1, septembre 1991 Summary: .M. ARMSTRONG Institute of Advanced Microelectronics, Department of Electrical and Electronic...

  13. E-Print Network 3.0 - advanced bwr nuclear Sample Search Results

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

    BWR6... pressurized and boiling water reactors with emphasis on the nuclear steam supply system and its associated... safety and control systems. Textbook: El-Wakil, M. M.,...

  14. System Upgrades at the Advanced Test Reactor Help Ensure that Nuclear Energy Research Continues at the Idaho National Laboratory

    SciTech Connect (OSTI)

    Craig Wise

    2011-12-01T23:59:59.000Z

    Fully operational in 1967, the Advanced Test Reactor (ATR) is a first-of-its-kind materials test reactor. Located on the Idaho National Laboratory’s desert site, this reactor remains at the forefront of nuclear science, producing extremely high neutron irradiation in a relatively short time span. The Advanced Test Reactor is also the only U.S. reactor that can replicate multiple reactor environments concurrently. The Idaho National Laboratory and the Department of Energy recently invested over 13 million dollars to replace three of ATR’s instrumentation and control systems. The new systems offer the latest software and technology advancements, ensuring the availability of the reactor for future energy research. Engineers and project managers successfully completed the four year project in March while the ATR was in a scheduled maintenance outage. “These new systems represent state-of-the-art monitoring and annunciation capabilities,” said Don Feldman, ATR Station Manager. “They are comparable to systems currently used for advanced reactor designs planned for construction in the U.S. and in operation in some foreign countries.”

  15. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980

    SciTech Connect (OSTI)

    Not Available

    1980-06-25T23:59:59.000Z

    Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.

  16. Continuous wavelet transform analysis and modal location analysis acoustic emission source location for nuclear piping crack growth monitoring

    SciTech Connect (OSTI)

    Mohd, Shukri [Nondestructive Testing Group, Industrial Technology Division, Malaysian Nuclear Agency, 43000, Bangi, Selangor (Malaysia); Holford, Karen M.; Pullin, Rhys [Cardiff School of Engineering, Cardiff University, Queen's Buildings, The Parade, CARDIFF CF24 3AA (United Kingdom)

    2014-02-12T23:59:59.000Z

    Source location is an important feature of acoustic emission (AE) damage monitoring in nuclear piping. The ability to accurately locate sources can assist in source characterisation and early warning of failure. This paper describe the development of a novelAE source location technique termed 'Wavelet Transform analysis and Modal Location (WTML)' based on Lamb wave theory and time-frequency analysis that can be used for global monitoring of plate like steel structures. Source location was performed on a steel pipe of 1500 mm long and 220 mm outer diameter with nominal thickness of 5 mm under a planar location test setup using H-N sources. The accuracy of the new technique was compared with other AE source location methods such as the time of arrival (TOA) techniqueand DeltaTlocation. Theresults of the study show that the WTML method produces more accurate location resultscompared with TOA and triple point filtering location methods. The accuracy of the WTML approach is comparable with the deltaT location method but requires no initial acoustic calibration of the structure.

  17. Advanced dry head-end reprocessing of light water reactor spent nuclear fuel

    SciTech Connect (OSTI)

    Collins, Emory D.; Delcul, Guillermo D.; Hunt, Rodney D.; Johnson, Jared A.; Spencer, Barry B.

    2014-06-10T23:59:59.000Z

    A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.

  18. Advanced dry head-end reprocessing of light water reactor spent nuclear fuel

    DOE Patents [OSTI]

    Collins, Emory D; Delcul, Guillermo D; Hunt, Rodney D; Johnson, Jared A; Spencer, Barry B

    2013-11-05T23:59:59.000Z

    A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.

  19. E-Print Network 3.0 - advanced nuclear energy Sample Search Results

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

    is far less than any of the alternative energy technologies now... contemplated, such as solar, biomass and wind. Nuclear power must be part of any future solution to the...

  20. E-Print Network 3.0 - advance nuclear energy Sample Search Results

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

    is far less than any of the alternative energy technologies now... contemplated, such as solar, biomass and wind. Nuclear power must be part of any future solution to the...

  1. 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

    Nuclear power has the potential to help reduce rising carbon emissions, but to be considered sustainable, it must also demonstrate the availability of an indefinite fuel supply as well as not produce any significant negative environmental effects...

  2. THE ATTRACTIVENESS OF MATERIALS IN ADVANCED NUCLEAR FUEL CYCLES FOR VARIOUS PROLIFERATION AND THEFT SCENARIOS

    SciTech Connect (OSTI)

    Bathke, C. G.; Ebbinghaus, Bartley B.; Collins, Brian A.; Sleaford, Brad W.; Hase, Kevin R.; Robel, Martin; Wallace, R. K.; Bradley, Keith S.; Ireland, J. R.; Jarvinen, G. D.; Johnson, M. W.; Prichard, Andrew W.; Smith, Brian W.

    2012-08-29T23:59:59.000Z

    We must anticipate that the day is approaching when details of nuclear weapons design and fabrication will become common knowledge. On that day we must be particularly certain that all special nuclear materials (SNM) are adequately accounted for and protected and that we have a clear understanding of the utility of nuclear materials to potential adversaries. To this end, this paper examines the attractiveness of materials mixtures containing SNM and alternate nuclear materials associated with the plutonium-uranium reduction extraction (Purex), uranium extraction (UREX), coextraction (COEX), thorium extraction (THOREX), and PYROX (an electrochemical refining method) reprocessing schemes. This paper provides a set of figures of merit for evaluating material attractiveness that covers a broad range of proliferant state and subnational group capabilities. The primary conclusion of this paper is that all fissile material must be rigorously safeguarded to detect diversion by a state and must be provided the highest levels of physical protection to prevent theft by subnational groups; no 'silver bullet' fuel cycle has been found that will permit the relaxation of current international safeguards or national physical security protection levels. The work reported herein has been performed at the request of the U.S. Department of Energy (DOE) and is based on the calculation of 'attractiveness levels' that are expressed in terms consistent with, but normally reserved for, the nuclear materials in DOE nuclear facilities. The methodology and findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security is discussed.

  3. The Attractiveness of Materials in Advanced Nuclear Fuel Cycles for Various Proliferation and Theft Scenarios

    SciTech Connect (OSTI)

    Bathke, C. G.; Wallace, R. K.; Ireland, J. R.; Johnson, M. W.; Hase, Kevin R.; Jarvinen, G. D.; Ebbinghaus, B. B.; Sleaford, Brad W.; Bradley, Keith S.; Collins, Brian A.; Smith, Brian W.; Prichard, Andrew W.

    2010-09-01T23:59:59.000Z

    This paper is an extension to earlier studies1,2 that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) and alternate nuclear materials (ANM) associated with the PUREX, UREX, COEX, THOREX, and PYROX reprocessing schemes. This study extends the figure of merit (FOM) for evaluating attractiveness to cover a broad range of proliferant state and sub-national group capabilities. The primary conclusion of this study is that all fissile material needs to be rigorously safeguarded to detect diversion by a state and provided the highest levels of physical protection to prevent theft by sub-national groups; no “silver bullet” has been found that will permit the relaxation of current international safeguards or national physical security protection levels. This series of studies has been performed at the request of the United States Department of Energy (DOE) and is based on the calculation of "attractiveness levels" that are expressed in terms consistent with, but normally reserved for nuclear materials in DOE nuclear facilities.3 The expanded methodology and updated findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security are discussed.

  4. Development of Advanced Technologies to Reduce Design, Fabrication and Construction Costs for Future Nuclear Power Plants

    SciTech Connect (OSTI)

    Camillo A. DiNunzio Framatome ANP DE& S; Dr. Abhinav Gupta Assistant Professor NCSU; Dr. Michael Golay Professor MIT Dr. Vincent Luk Sandia National Laboratories; Rich Turk Westinghouse Electric Company Nuclear Systems; Charles Morrow, Sandia National Laboratories; Geum-Taek Jin, Korea Power Engineering Company Inc.

    2002-11-30T23:59:59.000Z

    OAK-B135 This report presents a summation of the third and final year of a three-year investigation into methods and technologies for substantially reducing the capital costs and total schedule for future nuclear plants. In addition, this is the final technical report for the three-year period of studies.

  5. Advanced neutron irradiation system using Texas A&M University Nuclear Science Center Reactor

    E-Print Network [OSTI]

    Jang, Si Young

    2005-11-01T23:59:59.000Z

    was installed in the irradiation cell of the Texas A&M University Nuclear Science Center Reactor (NSCR). By increasing the thickness of the lead-bismuth alloy, the neutron spectra were shifted into lower energies by the scattering interactions of fast...

  6. Requirements for a Dynamic Solvent Extraction Module to Support Development of Advanced Technologies for the Recycle of Used Nuclear Fuel

    SciTech Connect (OSTI)

    Jack Law; Veronica Rutledge; Candido Pereira; Jackie Copple; Kurt Frey; John Krebs; Laura Maggos; Kevin Nichols; Kent Wardle; Pratap Sadasivan; Valmor DeAlmieda; David Depaoli

    2011-06-01T23:59:59.000Z

    The Department of Energy's Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program has been established to create and deploy next generation, verified and validated nuclear energy modeling and simulation capabilities for the design, implementation, and operation of future nuclear energy systems to improve the U.S. energy security. As part of the NEAMS program, Integrated Performance and Safety Codes (IPSC's) are being produced to significantly advance the status of modeling and simulation of energy systems beyond what is currently available to the extent that the new codes be readily functional in the short term and extensible in the longer term. The four IPSC areas include Safeguards and Separations, Reactors, Fuels, and Waste Forms. As part of the Safeguards and Separations (SafeSeps) IPSC effort, interoperable process models are being developed that enable dynamic simulation of an advanced separations plant. A SafeSepss IPSC 'toolkit' is in development to enable the integration of separation process modules and safeguards tools into the design process by providing an environment to compose, verify and validate a simulation application to be used for analysis of various plant configurations and operating conditions. The modules of this toolkit will be implemented on a modern, expandable architecture with the flexibility to explore and evaluate a wide range of process options while preserving their stand-alone usability. Modules implemented at the plant-level will initially incorporate relatively simple representations for each process through a reduced modeling approach. Final versions will incorporate the capability to bridge to subscale models to provide required fidelity in chemical and physical processes. A dynamic solvent extraction model and its module implementation are needed to support the development of this integrated plant model. As a stand-alone application, it will also support solvent development of extraction flowsheets and integrated safeguards approaches within the Fuel Cycle Research and Development (FCR&D) Program. The purpose of this document is to identify the requirements for this dynamic solvent extraction model to guide process modelers and code developers to produce a computational module that meets anticipated future needs.

  7. Metamaterial flexible sheets could transform optics

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

    Metamaterial flexible sheets could transform optics Metamaterial flexible sheets could transform optics Advances would boost security screening systems, infrared thermal cameras,...

  8. Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors

    SciTech Connect (OSTI)

    Korsah, K.; Clark, R.L.; Wood, R.T. [Oak Ridge National Lab., TN (United States)

    1994-04-01T23:59:59.000Z

    Issues of obsolescence and lack of infrastructural support in (analog) spare parts, coupled with the potential benefits of digital systems, are driving the nuclear industry to retrofit analog instrumentation and control (I&C) systems with digital and microprocessor-based systems. While these technologies have several advantages, their application to safety-related systems in nuclear power plants raises key issues relating to the systems` environmental qualification and functional reliability. To bound the problem of new I&C system functionality and qualification, the authors focused this study on protection systems proposed for use in ALWRs. Specifically, both functional and environmental qualification issues for ALWR protection system I&C were addressed by developing an environmental, functional, and aging data template for a protection division of each proposed ALWR design. By using information provided by manufacturers, environmental conditions and stressors to which I&C equipment in reactor protection divisions may be subjected were identified. The resulting data were then compared to a similar template for an instrument string typically found in an analog protection division of a present-day nuclear power plant. The authors also identified fiber-optic transmission systems as technologies that are relatively new to the nuclear power plant environment and examined the failure modes and age-related degradation mechanisms of fiber-optic components and systems. One reason for the exercise of caution in the introduction of software into safety-critical systems is the potential for common-cause failure due to the software. This study, however, approaches the functionality problem from a systems point of view. System malfunction scenarios are postulated to illustrate the fact that, when dealing with the performance of the overall integrated system, the real issues are functionality and fault tolerance, not hardware vs. software.

  9. Advanced Fuels Campaign Execution Plan

    SciTech Connect (OSTI)

    Kemal Pasamehmetoglu

    2011-09-01T23:59:59.000Z

    The purpose of the Advanced Fuels Campaign (AFC) Execution Plan is to communicate the structure and management of research, development, and demonstration (RD&D) activities within the Fuel Cycle Research and Development (FCRD) program. Included in this document is an overview of the FCRD program, a description of the difference between revolutionary and evolutionary approaches to nuclear fuel development, the meaning of science-based development of nuclear fuels, and the 'Grand Challenge' for the AFC that would, if achieved, provide a transformational technology to the nuclear industry in the form of a high performance, high reliability nuclear fuel system. The activities that will be conducted by the AFC to achieve success towards this grand challenge are described and the goals and milestones over the next 20 to 40 year period of research and development are established.

  10. 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

  11. SciTech Connect: Recent advances in nuclear fission theory: pre- and

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administrationcontroller systemsBi (2) Sr (2) Ca (2)Frameworkextended bottompost-scission

  12. United States and Italy Sign Agreements to Advance Developments in Nuclear

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists' Research Petroleum ReserveDepartment ofEnergy, Office ofNuclear Damage |Energy |

  13. Advanced Outage and Control Center: Strategies for Nuclear Plant Outage Work Status Capabilities

    SciTech Connect (OSTI)

    Gregory Weatherby

    2012-05-01T23:59:59.000Z

    The research effort is a part of the Light Water Reactor Sustainability (LWRS) Program. LWRS is a research and development program sponsored by the Department of Energy, performed in close collaboration with industry to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. The LWRS Program serves to help the US nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. The Outage Control Center (OCC) Pilot Project was directed at carrying out the applied research for development and pilot of technology designed to enhance safe outage and maintenance operations, improve human performance and reliability, increase overall operational efficiency, and improve plant status control. Plant outage management is a high priority concern for the nuclear industry from cost and safety perspectives. Unfortunately, many of the underlying technologies supporting outage control are the same as those used in the 1980’s. They depend heavily upon large teams of staff, multiple work and coordination locations, and manual administrative actions that require large amounts of paper. Previous work in human reliability analysis suggests that many repetitive tasks, including paper work tasks, may have a failure rate of 1.0E-3 or higher (Gertman, 1996). With between 10,000 and 45,000 subtasks being performed during an outage (Gomes, 1996), the opportunity for human error of some consequence is a realistic concern. Although a number of factors exist that can make these errors recoverable, reducing and effectively coordinating the sheer number of tasks to be performed, particularly those that are error prone, has the potential to enhance outage efficiency and safety. Additionally, outage management requires precise coordination of work groups that do not always share similar objectives. Outage managers are concerned with schedule and cost, union workers are concerned with performing work that is commensurate with their trade, and support functions (safety, quality assurance, and radiological controls, etc.) are concerned with performing the work within the plants controls and procedures. Approaches to outage management should be designed to increase the active participation of work groups and managers in making decisions that closed the gap between competing objectives and the potential for error and process inefficiency.

  14. Design of the Next Generation Nuclear Plant Graphite Creep Experiments for Irradiation in the Advanced Test Reactor

    SciTech Connect (OSTI)

    S. Blaine Grover

    2009-05-01T23:59:59.000Z

    The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradiating six gas reactor graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These graphite irradiations are being accomplished to support development of the next generation reactors in the United States. The graphite experiments will be irradiated over the next six to eight years to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data at different temperatures and loading conditions to support design of the Next Generation Nuclear Plant Very High Temperature Gas Reactor, as well as other future gas reactors. The experiments will each consist of a single capsule that will contain seven separate stacks of graphite specimens. Six of the specimen stacks will have half of their graphite specimens under a compressive load, while the other half of the specimens will not be subjected to a compressive load during irradiation. The six stacks will be organized into pairs with a different compressive load being applied to the top half of each pair of specimen stacks. The seventh stack will not have a compressive load on the graphite specimens during irradiation. The specimens will be irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There will also be the capability of sampling the sweep gas effluent to determine if any oxidation or off-gassing of the specimens occurs during initial start-up of the experiment. The final design phase for the first experiment was completed in September 2008, and the fabrication and assembly of the experiment test train as well as installation and testing of the control and support systems that will monitor and control the experiment during irradiation are being completed in early calendar 2009. The first experiment is scheduled to be ready for insertion in the ATR by April 30, 2009. This paper will discuss the design of the experiment including the test train and the temperature and compressive load monitoring, control, and data collection systems.

  15. Americium/Lanthanide Separations in Alkaline Solutions for Advanced Nuclear Fuel Cycles

    SciTech Connect (OSTI)

    Goff, George S. [Los Alamos National Laboratory; Long, Kristy Marie [Los Alamos National Laboratory; Reilly, Sean D. [Los Alamos National Laboratory; Jarvinen, Gordon D. [Los Alamos National Laboratory; Runde, Wolfgang H. [Los Alamos National Laboratory

    2012-06-11T23:59:59.000Z

    Project goals: Can used nuclear fuel be partitioned by dissolution in alkaline aqueous solution to give a solution of uranium, neptunium, plutonium, americium and curium and a filterable solid containing nearly all of the lanthanide fission products and certain other fission products? What is the chemistry of Am/Cm/Ln in oxidative carbonate solutions? Can higher oxidation states of Am be stabilized and exploited? Conclusions: Am(VI) is kinetically stable in 0.5-2.0 M carbonate solutions for hours. Aliquat 336 in toluene has been successfully shown to extract U(VI) and Pu(VI) from carbonate solutions. (Stepanov et al 2011). Higher carbonate concentration gives lower D, SF{sub U/Eu} for = 4 in 1 M K{sub 2}CO{sub 3}. Experiments with Am(VI) were unsuccessful due to reduction by the organics. Multiple sources of reducing organics...more optimization. Reduction experiments of Am(VI) in dodecane/octanol/Aliquat 336 show that after 5 minutes of contact, only 30-40% of the Am(VI) has been reduced. Long enough to perform an extraction. Shorter contact times, lower T, and lower Aliquat 336 concentration still did not result in any significant extraction of Am. Anion exchange experiments using a strong base anion exchanger show uptake of U(VI) with minimal uptake of Nd(III). Experiments with Am(VI) indicate Am sorption with a Kd of 9 (10 minute contact) but sorption mechanism is not yet understood. SF{sub U/Nd} for = 7 and SF{sub U/Eu} for = 19 after 24 hours in 1 M K{sub 2}CO{sub 3}.

  16. Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC) : FY10 development and integration.

    SciTech Connect (OSTI)

    Criscenti, Louise Jacqueline; Sassani, David Carl; Arguello, Jose Guadalupe, Jr.; Dewers, Thomas A.; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Wang, Yifeng; Schultz, Peter Andrew

    2011-02-01T23:59:59.000Z

    This report describes the progress in fiscal year 2010 in developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. Waste IPSC activities in fiscal year 2010 focused on specifying a challenge problem to demonstrate proof of concept, developing a verification and validation plan, and performing an initial gap analyses to identify candidate codes and tools to support the development and integration of the Waste IPSC. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. This year-end progress report documents the FY10 status of acquisition, development, and integration of thermal-hydrologic-chemical-mechanical (THCM) code capabilities, frameworks, and enabling tools and infrastructure.

  17. Deployment & Market Transformation (Brochure)

    SciTech Connect (OSTI)

    Not Available

    2012-04-01T23:59:59.000Z

    NREL's deployment and market transformation (D and MT) activities encompass the laboratory's full range of technologies, which span the energy efficiency and renewable energy spectrum. NREL staff educates partners on how they can advance sustainable energy applications and also provides clients with best practices for reducing barriers to innovation and market transformation.

  18. Modeling Transformation

    E-Print Network [OSTI]

    Rose, Michael R.

    Modeling Transformation What does each step do? #12;Transformation Procedure #12;Transformation Procedure #12;Building Your Model Yarn = chromosomal DNA Beads - - - - - - - - - - - - - - Ribosomes #12;Add transformation solution Tube CaCl2 #12;Transformation solution: CaCl2

  19. Challenge problem and milestones for : Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC).

    SciTech Connect (OSTI)

    Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe, Jr.

    2010-09-01T23:59:59.000Z

    This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

  20. transformation restrictions

    E-Print Network [OSTI]

    Lyuu, Yuh-Dauh

    Integration of Graph Transformation and Temporal Logic for the Speci#12;cation of Distributed, namely distributed graph transformation and temporal logic. Distributed graph transformation is intended

  1. E-Print Network 3.0 - arithmetic fourier transform Sample Search...

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

    fourier transform Search Powered by Explorit Topic List Advanced Search Sample search results for: arithmetic fourier transform Page: << < 1 2 3 4 5 > >> 1 Fast Fourier transform...

  2. Transformation Telepresence

    E-Print Network [OSTI]

    Fisher, Kathleen

    Business Transformation through Telepresence Gaining Value with Enterprise Video Collaboration-based research and April, 2011 Business Transformation through Telepresence: Gaining Value with Enterprise Video be used to transform organizations. Why Does Your Business Need to Transform? Traditionally, organizations

  3. Evaluation of the applicability of existing nuclear power plant regulatory requirements in the U.S. to advanced small modular reactors.

    SciTech Connect (OSTI)

    LaChance, Jeffrey L.; Wheeler, Timothy A.; Farnum, Cathy Ottinger; Middleton, Bobby D.; Jordan, Sabina Erteza; Duran, Felicia Angelica; Baum, Gregory A.

    2013-05-01T23:59:59.000Z

    The current wave of small modular reactor (SMR) designs all have the goal of reducing the cost of management and operations. By optimizing the system, the goal is to make these power plants safer, cheaper to operate and maintain, and more secure. In particular, the reduction in plant staffing can result in significant cost savings. The introduction of advanced reactor designs and increased use of advanced automation technologies in existing nuclear power plants will likely change the roles, responsibilities, composition, and size of the crews required to control plant operations. Similarly, certain security staffing requirements for traditional operational nuclear power plants may not be appropriate or necessary for SMRs due to the simpler, safer and more automated design characteristics of SMRs. As a first step in a process to identify where regulatory requirements may be met with reduced staffing and therefore lower cost, this report identifies the regulatory requirements and associated guidance utilized in the licensing of existing reactors. The potential applicability of these regulations to advanced SMR designs is identified taking into account the unique features of these types of reactors.

  4. Report on the workshop "Decay spectroscopy at CARIBU: advanced fuel cycle applications, nuclear structure and astrophysics". 14-16 April 2011, Argonne National Laboratory, USA.

    SciTech Connect (OSTI)

    Kondev, F.; Carpenter, M.P.; Chowdhury, P.; Clark, J.A.; Lister, C.J.; Nichols, A.L.; Swewryniak, D. (Nuclear Engineering Division); (Univ. of Massachusetts); (Univ. of Surrey)

    2011-10-06T23:59:59.000Z

    A workshop on 'Decay Spectroscopy at CARIBU: Advanced Fuel Cycle Applications, Nuclear Structure and Astrophysics' will be held at Argonne National Laboratory on April 14-16, 2011. The aim of the workshop is to discuss opportunities for decay studies at the Californium Rare Isotope Breeder Upgrade (CARIBU) of the ATLAS facility with emphasis on advanced fuel cycle (AFC) applications, nuclear structure and astrophysics research. The workshop will consist of review and contributed talks. Presentations by members of the local groups, outlining the status of relevant in-house projects and availabile equipment, will also be organized. time will also be set aside to discuss and develop working collaborations for future decay studies at CARIBU. Topics of interest include: (1) Decay data of relevance to AFC applications with emphasis on reactor decay heat; (2) Discrete high-resolution gamma-ray spectroscopy following radioactive decya and related topics; (3) Calorimetric studies of neutron-rich fission framgents using Total ABsorption Gamma-Ray Spectrometry (TAGS) technique; (4) Beta-delayed neutron emissions and related topics; and (5) Decay data needs for nuclear astrophysics.

  5. Transformations ENGINEERING

    E-Print Network [OSTI]

    Gales, Mark

    On the Complexity of the Discrete Fourier Transform and Related Linear Transforms Preliminary straight line program that computes an encoding of the Hadamard Transform. The transform itself can transforms, like the DFT. 1 Introduction The complexity of special linear transformations (computations

  6. United States and Italy Sign Agreements to Advance Developments...

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

    Italy Sign Agreements to Advance Developments in Nuclear Energy United States and Italy Sign Agreements to Advance Developments in Nuclear Energy September 30, 2009 - 12:00am...

  7. Development of Technologies for the Simultaneous Separation of Cesium and Strontium from Spent Nuclear Fuel as Part of an Advanced Fuel Cycle

    SciTech Connect (OSTI)

    Jack D. Law; R. Scott HErbst; David H. Meikrantz; Dean R. Peterman; Catherine L. Riddle; Richard D. Tillotson; Terry A. Todd

    2005-04-01T23:59:59.000Z

    As part of the Advanced Fuel Cycle Initiative, two solvent extraction technologies are being developed to simultaneously separate cesium and strontium from dissolved spent nuclear fuel. The first process utilizes a solvent consisting of chlorinated cobalt dicarbollide and polyethylene glycol extractants in a phenyltrifluoromethyl sulfone diluent. Recent improvements to the process include development of a new, non-nitroaromatic diluent and development of new stripping reagents, including a regenerable strip reagent that can be recovered and recycled. Countercurrent flowsheets have been designed and tested on simulated and actual spent nuclear fuel feed streams with both cesium and strontium removal efficiencies of greater than 99 %. The second process developed to simultaneously separate cesium and strontium from spent nuclear fuel is based on two highly-specific extractants: 4,4',(5')-Di-(t-butyldicyclo-hexano)-18-crown-6 (DtBuCH18C6) and Calix[4]arene-bis-(tert-octylbenzo-crown-6) (BOBCalixC6). The DtBuCH18C6 extractant is selective for strontium and the BOBCalixC6 extractant is selective for cesium. A solvent composition has been developed that enables both elements to be removed together and, in fact, a synergistic effect was observed with strontium distributions in the combined solvent that are much higher that in the strontium extraction (SREX) process. Initial laboratory test results of the new combined cesium and strontium extraction process indicate good extraction and stripping performance. A flowsheet for treatment of spent nuclear fuel is currently being developed.

  8. Interagency Advanced Power Group, Joint Electrical and Nuclear Working Group, meeting minutes, November 16--17, 1993

    SciTech Connect (OSTI)

    Not Available

    1993-12-31T23:59:59.000Z

    Reports on soldier power R&D review, N-MCT power electronic building blocks, silicon carbide power semiconductor work, and ground based radar were made to the Power Conditioning Panel. An introduction to high temperature electronics needs, research and development was made to the High Temperature Electronics Subcommittee. The Pulse Power Panel received reports on the navy ETC gun, and army pulse power. The Superconductivity Panel received reports on high-tc superconducting wires, superconducting magnetic energy storage, and superconducting applications. The Nuclear Working Group received presentations on the Topaz nuclear power program, and space nuclear work in the Department of Energy.

  9. TITAN : an advanced three dimensional coupled neutronicthermal-hydraulics code for light water nuclear reactor core analysis

    E-Print Network [OSTI]

    Griggs, D. P.

    1984-01-01T23:59:59.000Z

    The accurate analysis of nuclear reactor transients frequently requires that neutronics, thermal-hydraulics and feedback be included. A number of coupled neutronics/thermal-hydraulics codes have been developed for this ...

  10. 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.

  11. Transforming development

    E-Print Network [OSTI]

    Verbrugge, Clark

    Transforming Java Bytecode Laurie Hendren, Patrick Lam, Jennifer for Analyzing and Transforming Java Bytecode -- p. 1/148 #12; ,Feng,Jennifer) Conclusion, Further Reading & Homework (Laurie) Soot, a Tool for Analyzing and Transforming Java Bytecode

  12. Transformations for densities Linear transformations

    E-Print Network [OSTI]

    Adler, Robert J.

    ' & $ % Lecture 28 Transformations for densities Linear transformations 1-1 differentiable functions General transformations Expectation of a function 1 #12;' & $ % Transformations for discrete transformation of a U[0, 1] · Take X U[0, 1], so that fX(x) = 1 0 0 and set Y

  13. Energy and Security in Northeast Asia: Proposals for Nuclear Cooperation

    E-Print Network [OSTI]

    Kaneko, Kumao; Suzuki, Atsuyuki; Choi, Jor-Shan; Fei, Edward

    1998-01-01T23:59:59.000Z

    Henry S. Rowen, "Nuclear Energy and Nuclear Proliferation -Northeast Asian nuclear energy cooperation advanced byAsia). 2 Cooperation on nuclear energy would have a direct

  14. Appell Transformation and Canonical Transforms

    E-Print Network [OSTI]

    Amalia Torre

    2011-07-19T23:59:59.000Z

    The interpretation of the optical Appell transformation, as previously elaborated in relation to the free-space paraxial propagation under both a rectangular and a circular cylindrical symmetry, is reviewed. Then, the caloric Appell transformation, well known in the theory of heat equation, is shown to be amenable for a similar interpretation involving the Laplace transform rather than the Fourier transform, when dealing with the 1D heat equation. Accordingly, when considering the radial heat equation, suitably defined Hankel-type transforms come to be involved in the inherent Appell transformation. The analysis is aimed at outlining the link between the Appell transformation and the canonical transforms.

  15. Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment

    Broader source: Energy.gov [DOE]

    Presenter: Bentley Harwood, Advanced Test Reactor Nuclear Safety Engineer Battelle Energy Alliance Idaho National Laboratory

  16. Integral transformation and Darboux transformation

    E-Print Network [OSTI]

    Kouichi Takemura

    2009-11-11T23:59:59.000Z

    We review Darboux-Crum transformation of Heun's differential equation. By rewriting an integral transformation of Heun's differential equation into a form of elliptic functions, we see that the integral representation is a generalization of Darboux-Crum transformation. We also consider conservation of monodromy with respect to the transformations.

  17. Grid Transformation Workshop Results Grid Transformation Workshop Results 2 April 2012

    E-Print Network [OSTI]

    Grid Transformation Workshop Results April 2012 #12;Grid Transformation Workshop Results 2 April 2012 Grid Transformation Workshop Results plications. We will explore the basics of data modeling Transformation Workshop: Advanced Reading Material Product ID 1024659. The material in this report builds upon

  18. Massachusetts Institute of Technology Department of Nuclear Engineering

    E-Print Network [OSTI]

    Massachusetts Institute of Technology Department of Nuclear Engineering Advanced Reactor Technology of Technology Department of Nuclear Engineering Advanced Reactor Technology Pebble Bed Project MPBR-2 Student Department of Nuclear Engineering Advanced Reactor Technology Pebble Bed Project MPBR-3 Project Objective

  19. Advanced Pipe Replacement Procedure for a Defective CRDM Housing Nozzle Enables Continued Normal Operation of a Nuclear Power Plant

    SciTech Connect (OSTI)

    Gilmore, Geoff; Becker, Andrew [Climax Portable Machine Tools, Inc., 2712 East Second Street, Newberg, OR 97132 (United States)

    2006-07-01T23:59:59.000Z

    During the 2003 outage at the Ringhals Nuclear Plant in Sweden, a leak was found in the vicinity of a Control Rod Drive Mechanism (CRDM) housing nozzle at Unit 1. Based on the ALARA principle for radioactive contamination, a unique repair process was developed. The repair system includes utilization of custom, remotely controlled GTAW-robots, a CNC cutting and finishing machine, snake-arm robots and NDE equipment. The success of the repair solution was based on performing the machining and welding operations from the inside of the SCRAM pipe through the CRDM housing since accessibility from the outside was extremely limited. Before the actual pipe replacement procedure was performed, comprehensive training programs were conducted. Training was followed by certification of equipment, staff and procedures during qualification tests in a full scale mock-up of the housing nozzle. Due to the ingenuity of the overall repair solution and training programs, the actual pipe replacement procedure was completed in less than half the anticipated time. As a result of the successful pipe replacement, the nuclear power plant was returned to normal operation. (authors)

  20. Market Transformation

    SciTech Connect (OSTI)

    Not Available

    2008-09-01T23:59:59.000Z

    Summarizes the goals and activities of the DOE Solar Energy Technologies Program efforts within its market transformation subprogram.

  1. transformations: representations

    E-Print Network [OSTI]

    Nguyen, Dat H.

    Overview 1. Number transformations: from one base to another 2. Integer representations 3. Real rate, caches... #12; ECS 50, Discussion on 4/25 2 Integer Transformation: From Decimal to Binary Let, Discussion on 4/25 3 Integer Transformation: From Binary to Decimal Compute the weight of each digit position

  2. Transformation Composition

    E-Print Network [OSTI]

    Drewes, Frank

    Proc. AGTIVE'99, to appear in LNCS Graph Transformation Modules and their Composition ? Frank,knirsch,kreo,kuskeg@informatik.uni-bremen.de Abstract. In this paper, we investigate the notion of transformation modules as a structuring principle. Based on the notion of transformation units, a concept that allows to specify binary relations on graphs

  3. Transforming IMAGINATION

    E-Print Network [OSTI]

    Weber, David J.

    Our CAMPAIGN: Transforming MEDICINE Beyond IMAGINATION Endowed Professorships and Chairs #12;As, I know firsthand the many ways that endowed professorships can be transformative. Receiving the John. In the following pages, you can learn more about establishing your legacy by participating in the "Transforming

  4. Transforming IMAGINATION

    E-Print Network [OSTI]

    Weber, David J.

    Our CAMPAIGN: Transforming MEDICINE Beyond IMAGINATION The School of Medicine Research Building in the Transforming Medicine Beyond Imagination Campaign, and to learn more about the specific needs, relative and translational research and help drive medical breakthroughs that will transform the health and well

  5. Final LDRD report : nanoscale mechanisms in advanced aging of materials during storage of spent %22high burnup%22 nuclear fuel.

    SciTech Connect (OSTI)

    Clark, Blythe G.; Rajasekhara, Shreyas; Enos, David George; Dingreville, Remi Philippe Michel; Doyle, Barney Lee; Hattar, Khalid Mikhiel; Weiner, Ruth F.

    2013-09-01T23:59:59.000Z

    We present the results of a three-year LDRD project focused on understanding microstructural evolution and related property changes in Zr-based nuclear cladding materials towards the development of high fidelity predictive simulations for long term dry storage. Experiments and modeling efforts have focused on the effects of hydride formation and accumulation of irradiation defects. Key results include: determination of the influence of composition and defect structures on hydride formation; measurement of the electrochemical property differences between hydride and parent material for understanding and predicting corrosion resistance; in situ environmental transmission electron microscope observation of hydride formation; development of a predictive simulation for mechanical property changes as a function of irradiation dose; novel test method development for microtensile testing of ionirradiated material to simulate the effect of neutron irradiation on mechanical properties; and successful demonstration of an Idaho National Labs-based sample preparation and shipping method for subsequent Sandia-based analysis of post-reactor cladding.

  6. LAPPED TRANSFORMS Ricardo L. de Queiroz

    E-Print Network [OSTI]

    de Queiroz, Ricardo L.

    LAPPED TRANSFORMS Ricardo L. de Queiroz Advanced Color Imaging Xerox Corporation queiroz@wrc.xerox.com 0.1 Introduction The idea of a lapped transform (LT, for short) maintaining orthogonality and non with the blocking artifacts so common in traditional block transform coding of images. The idea was to extend

  7. E-Print Network 3.0 - azimuth transform interpolation Sample...

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

    transform interpolation Search Powered by Explorit Topic List Advanced Search Sample search results for: azimuth transform interpolation Page: << < 1 2 3 4 5 > >> 1 IEEE...

  8. E-Print Network 3.0 - adaptive wavelet transform Sample Search...

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

    wavelet transform Search Powered by Explorit Topic List Advanced Search Sample search results for: adaptive wavelet transform Page: << < 1 2 3 4 5 > >> 1 Complex Wavelets Arnab...

  9. Advanced Test Reactor Tour

    SciTech Connect (OSTI)

    Miley, Don

    2011-01-01T23:59:59.000Z

    The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

  10. Advanced Test Reactor Tour

    ScienceCinema (OSTI)

    Miley, Don

    2013-05-28T23:59:59.000Z

    The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

  11. TRANSFORME Dpartement

    E-Print Network [OSTI]

    Mignotte, Max

    GEODESIE et TRANSFORMATIONS GEODESIQUES Serge BEUCHER CMM ­ Mines ParisTech Novembre 2013 #12;Cours transformation a la propriété suivante: dX,l+m = dX,l [ dX,m] · d est croissante et extensive · d est également croissante lorsqu'on la considère comme une transformation appliquée à l'espace géodésique X (Y fixé) YY

  12. Market Transformation

    Fuel Cell Technologies Publication and Product Library (EERE)

    This Fuel Cell Technologies Program fact sheet outlines current status and challenges in the market transformation of hydrogen and fuel cell technologies.

  13. TRANSFORME Dpartement

    E-Print Network [OSTI]

    Mignotte, Max

    transformers of kind #3; ! #3;: NatF : #3; ! #3; NatF := #21;X: 1 +X Nat : #3; Nat := #22; NatF #15; Works also

  14. Advanced LBB methodology and considerations

    SciTech Connect (OSTI)

    Olson, R.; Rahman, S.; Scott, P. [Battelle, Columbus, OH (United States)] [and others

    1997-04-01T23:59:59.000Z

    LBB applications have existed in many industries and more recently have been applied in the nuclear industry under limited circumstances. Research over the past 10 years has evolved the technology so that more advanced consideration of LBB can now be given. Some of the advanced considerations for nuclear plants subjected to seismic loading evaluations are summarized in this paper.

  15. Advanced Components and Materials | ornl.gov

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

    Novel energy materials Advanced sensors Power electronics Intelligent power flow control High-capacity cables and conductors Compact modular transformers Community Energy Storage...

  16. Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model - 13413

    SciTech Connect (OSTI)

    Djokic, Denia [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States)] [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States); Piet, Steven J.; Pincock, Layne F.; Soelberg, Nick R. [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)] [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. 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. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system, and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity. (authors)

  17. Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model

    SciTech Connect (OSTI)

    Denia Djokic; Steven J. Piet; Layne F. Pincock; Nick R. Soelberg

    2013-02-01T23:59:59.000Z

    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. 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. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system , and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity.

  18. ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS - EBS INPUT

    SciTech Connect (OSTI)

    Sutton, M; Blink, J A; Greenberg, H R; Sharma, M

    2012-04-25T23:59:59.000Z

    The Used Fuel Disposition (UFD) Campaign within the Department of Energy's Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation's spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. The planning, construction, and operation of a nuclear disposal facility is a long-term process that involves engineered barriers that are tailored to both the geologic environment and the waste forms being emplaced. The UFD Campaign is considering a range of fuel cycles that in turn produce a range of waste forms. The UFD Campaign is also considering a range of geologic media. These ranges could be thought of as adding uncertainty to what the disposal facility design will ultimately be; however, it may be preferable to thinking about the ranges as adding flexibility to design of a disposal facility. For example, as the overall DOE-NE program and industrial actions result in the fuel cycles that will produce waste to be disposed, and the characteristics of those wastes become clear, the disposal program retains flexibility in both the choice of geologic environment and the specific repository design. Of course, other factors also play a major role, including local and State-level acceptance of the specific site that provides the geologic environment. In contrast, the Yucca Mountain Project (YMP) repository license application (LA) is based on waste forms from an open fuel cycle (PWR and BWR assemblies from an open fuel cycle). These waste forms were about 90% of the total waste, and they were the determining waste form in developing the engineered barrier system (EBS) design for the Yucca Mountain Repository design. About 10% of the repository capacity was reserved for waste from a full recycle fuel cycle in which some actinides were extracted for weapons use, and the remaining fission products and some minor actinides were encapsulated in borosilicate glass. Because the heat load of the glass was much less than the PWR and BWR assemblies, the glass waste form was able to be co-disposed with the open cycle waste, by interspersing glass waste packages among the spent fuel assembly waste packages. In addition, the Yucca Mountain repository was designed to include some research reactor spent fuel and naval reactor spent fuel, within the envelope that was set using the commercial reactor assemblies as the design basis waste form. This milestone report supports Sandia National Laboratory milestone M2FT-12SN0814052, and is intended to be a chapter in that milestone report. The independent technical review of this LLNL milestone was performed at LLNL and is documented in the electronic Information Management (IM) system at LLNL. The objective of this work is to investigate what aspects of quantifying, characterizing, and representing the uncertainty associated with the engineered barrier are affected by implementing different advanced nuclear fuel cycles (e.g., partitioning and transmutation scenarios) together with corresponding designs and thermal constraints.

  19. Global Nuclear Energy Partnership Fact Sheet - Expand Domestic...

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

    Expand Domestic Use of Nuclear Power Global Nuclear Energy Partnership Fact Sheet - Expand Domestic Use of Nuclear Power GNEP will build on the recent advances made by the...

  20. TRANSFORMATIONS GEODESIQUES

    E-Print Network [OSTI]

    Beucher, Serge

    to A if there is a transformation R which for every input x of B yields an equivalent input R(x) of A. { The answer to x for B

  1. Transformative copy

    E-Print Network [OSTI]

    Offenhuber, Dietmar

    2008-01-01T23:59:59.000Z

    The ability to create an unlimited number of identical copies is a privilege of digital documents. What if that would not be the case, if each copy of a digital file would go along with some sort of transformation? This ...

  2. argonne advanced research reactor: Topics by E-print Network

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

    and aerospace industry. ... enables methods, is used for in-service inspection of nuclear power plant components, such as tubing, piping the safe operationof advanced nuclear...

  3. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) verification and validation plan. version 1.

    SciTech Connect (OSTI)

    Bartlett, Roscoe Ainsworth; Arguello, Jose Guadalupe, Jr.; Urbina, Angel; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Knupp, Patrick Michael; Wang, Yifeng; Schultz, Peter Andrew; Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); McCornack, Marjorie Turner

    2011-01-01T23:59:59.000Z

    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. To meet this objective, NEAMS Waste IPSC M&S capabilities will be applied to challenging spatial domains, temporal domains, multiphysics couplings, and multiscale couplings. A strategic verification and validation (V&V) goal is to establish evidence-based metrics for the level of confidence in M&S codes and capabilities. Because it is economically impractical to apply the maximum V&V rigor to each and every M&S capability, M&S capabilities will be ranked for their impact on the performance assessments of various components of the repository systems. Those M&S capabilities with greater impact will require a greater level of confidence and a correspondingly greater investment in V&V. This report includes five major components: (1) a background summary of the NEAMS Waste IPSC to emphasize M&S challenges; (2) the conceptual foundation for verification, validation, and confidence assessment of NEAMS Waste IPSC M&S capabilities; (3) specifications for the planned verification, validation, and confidence-assessment practices; (4) specifications for the planned evidence information management system; and (5) a path forward for the incremental implementation of this V&V plan.

  4. Nuclear power high technology colloquium: proceedings

    SciTech Connect (OSTI)

    Not Available

    1984-12-10T23:59:59.000Z

    Reports presenting information on technology advancements in the nuclear industry and nuclear power plant functions have been abstracted and are available on the energy data base.

  5. A survey of Existing V&V, UQ and M&S Data and Knowledge Bases in Support of the Nuclear Energy - Knowledge base for Advanced Modeling and Simulation (NE-KAMS)

    SciTech Connect (OSTI)

    Hyung Lee; Rich Johnson, Ph.D.; Kimberlyn C. Moussesau

    2011-12-01T23:59:59.000Z

    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, Oak Ridge National Laboratory, Utah State University and others. The objective of this consortium is to establish a comprehensive knowledge base to provide Verification and Validation (V&V) and Uncertainty Quantification (UQ) and other resources for advanced modeling and simulation (M&S) in nuclear reactor design and analysis. NE-KAMS will become a valuable resource for the nuclear industry, the national laboratories, the U.S. NRC and the public to help ensure the safe operation of existing and future nuclear reactors. A survey and evaluation of the state-of-the-art of existing V&V and M&S databases, including the Department of Energy and commercial databases, has been performed to ensure that the NE-KAMS effort will not be duplicating existing resources and capabilities and to assess the scope of the effort required to develop and implement NE-KAMS. The survey and evaluation have indeed highlighted the unique set of value-added functionality and services that NE-KAMS will provide to its users. Additionally, the survey has helped develop a better understanding of the architecture and functionality of these data and knowledge bases that can be used to leverage the development of NE-KAMS.

  6. Advanced LWR Nuclear Fuel Development

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

    - Radiation (Part I) - Alkali-AggregateSilica Reaction (Part II) - Creepcreep-fracture interaction (Roadmap to be developed) Part I- Irradiated Concrete Research results...

  7. Small Market Advanced Retrofit Transformation Program (SMART...

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

    and government administrators of energy efficiency programs for small- and medium-sized buildings (SMBs). SMART Scale is looking to achieve an average of 20% energy savings per...

  8. Transforming America's Energy Economy Transforming America's

    E-Print Network [OSTI]

    #12;Transforming America's Energy Economy Transforming America's Energy Economy This document #12;Transforming America's Energy Economy A. Introduction: A Call for Action B. Envisioning the Future.5 Energy Efficiency C. Charting the Path Forward 1 #12;Transforming America's Energy Economy

  9. SPATIAL TRANSFORMATIONS 1 Running head: Spatial transformations

    E-Print Network [OSTI]

    Zacks, Jeffrey M.

    SPATIAL TRANSFORMATIONS 1 Running head: Spatial transformations Multiple Systems for Spatial Imagery: Transformations of Objects and Bodies Jeffrey M. Zacks* and Barbara Tversky * Washington COGNITION & COMPUTATION #12;SPATIAL TRANSFORMATIONS 2 Abstract Problem-solving often requires imagining

  10. Fourier Transform Pairs The Fourier transform transforms a function of

    E-Print Network [OSTI]

    Masci, Frank

    Fourier Transform Pairs The Fourier transform transforms a function of time, f(t), into a function of frequency, F(s): F {f(t)}(s) = F(s) = Z - f(t)e- j2st dt. The inverse Fourier transform transforms a func. The inverse Fourier transform of the Fourier trans- form is the identity transform: f(t) = Z - Z - f()e- j2s

  11. transform your thinking transform your environment

    E-Print Network [OSTI]

    Subramanian, Venkat

    MBA #12;transform your thinking 2 transform your environment 18 transform your career 26 start your transformation now 34 transform yourself www.olin.wustl.edu/MBA #12;What distinguishes Washington University. But a great business school transforms the way you think, lead and give back to the world community. #12

  12. The Laplace Transform 1 Laplace transform and inverse transform

    E-Print Network [OSTI]

    Yengulalp, Lynne

    The Laplace Transform Name: 1 Laplace transform and inverse transform Definition. Let f(t) be a function defined for t 0. Then the integral L {f(t)} = 0 e-st f(t)dt is said to be the Laplace transform of f provided the integral converges. Fill in the following Laplace transforms. L {tn } = L {eat } = L

  13. The Laplace Transform 1 Laplace transform and inverse transform

    E-Print Network [OSTI]

    Yengulalp, Lynne

    The Laplace Transform Name: 1 Laplace transform and inverse transform Definition. Let f be a function defined for t 0. Then the integral L {f(t)} = 0 e-st f(t)dt is said to be the Laplace transform of f provided the integral converges. Fill in the following Laplace transforms. L {tn } = n! sn+1 L

  14. 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.

  15. Advertise Subscribe Log in Register Advanced search

    E-Print Network [OSTI]

    Advertise Subscribe Log in Register Advanced search Home News Comment Special reports People power Europe does not need nuclear power to meet its future energy needs. Question of nuclear subsidies-reduction target would be better. Blowing away nuclear power Europe does not need nuclear power to meet its future

  16. Implementing Arrangement Between the U.S. Department of Energy and the Agency of Natural Resources and Energy of Japan Concerning Cooperation in the Joint Nuclear Energy Research Initiative on Advanced Nuclear Technologies

    Broader source: Energy.gov [DOE]

    Noting further that representatives of DOE's Office of Nuclear Energy, Science, and Technology and ANRE have identified common interests in innovative light water reactor technologies, including...

  17. DOE Seeks to Invest up to $15 Million in Funding for Nuclear...

    Energy Savers [EERE]

    following areas: Used Fuel Separations Technology, Advanced Nuclear Fuel Development, Fast Burner Reactors and Advanced Transmutation Systems, Advanced Fuel Cycle Systems...

  18. Transformers Transformer device used to raise (for

    E-Print Network [OSTI]

    Bertulani, Carlos A. - Department of Physics and Astronomy, Texas A&M University

    Transformers Transformer ­ device used to raise (for transmission) and lower (for use) the ac with different #s of turns #12;Transformers Alternating primary current induces alternating magnetic flux in iron dt d NV B PP -= dt d NV B SS -= S S P P N V N V = #12;Transformers Transformation of voltage

  19. Introduction to Image Transform Fourier Transform

    E-Print Network [OSTI]

    Chen, Chaur-Chin

    Monad Transformers as Monoid Transformers Mauro Jaskelioff CIFASIS/Universidad Nacional de Rosario monadic semantics constructs complex monads by using monad transformers to add computational features transformers to monoid transformers. The generalization brings more simplicity and clarity, and opens the way

  20. Hough Transform Common Names: Hough transform

    E-Print Network [OSTI]

    Masci, Frank

    Hough Transform Common Names: Hough transform Brief Description The Hough transform is a technique that the desired features be specified in some parametric form, the classical Hough transform is most commonly used for the detection of regular curves such as lines, circles, ellipses, etc. A generalized Hough transform can

  1. A Career in Nuclear Energy

    ScienceCinema (OSTI)

    Lambregts, Marsha

    2013-05-28T23:59:59.000Z

    Nuclear chemist Dr. Marsha Lambregts talks about the Center for Advanced Energy Studies and the benefits of a nuclear energy career. For more information about careers at INL, visit http://www.facebook.com/idahonationallaboratory.

  2. A Career in Nuclear Energy

    SciTech Connect (OSTI)

    Lambregts, Marsha

    2009-01-01T23:59:59.000Z

    Nuclear chemist Dr. Marsha Lambregts talks about the Center for Advanced Energy Studies and the benefits of a nuclear energy career. For more information about careers at INL, visit http://www.facebook.com/idahonationallaboratory.

  3. Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC) : gap analysis for high fidelity and performance assessment code development.

    SciTech Connect (OSTI)

    Lee, Joon H.; Siegel, Malcolm Dean; Arguello, Jose Guadalupe, Jr.; Webb, Stephen Walter; Dewers, Thomas A.; Mariner, Paul E.; Edwards, Harold Carter; Fuller, Timothy J.; Freeze, Geoffrey A.; Jove-Colon, Carlos F.; Wang, Yifeng

    2011-03-01T23:59:59.000Z

    This report describes a gap analysis performed in the process of developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with rigorous verification, validation, and software quality requirements. The gap analyses documented in this report were are performed during an initial gap analysis to identify candidate codes and tools to support the development and integration of the Waste IPSC, and during follow-on activities that delved into more detailed assessments of the various codes that were acquired, studied, and tested. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. The gap analysis indicates that significant capabilities may already exist in the existing THC codes although there is no single code able to fully account for all physical and chemical processes involved in a waste disposal system. Large gaps exist in modeling chemical processes and their couplings with other processes. The coupling of chemical processes with flow transport and mechanical deformation remains challenging. The data for extreme environments (e.g., for elevated temperature and high ionic strength media) that are needed for repository modeling are severely lacking. In addition, most of existing reactive transport codes were developed for non-radioactive contaminants, and they need to be adapted to account for radionuclide decay and in-growth. The accessibility to the source codes is generally limited. Because the problems of interest for the Waste IPSC are likely to result in relatively large computational models, a compact memory-usage footprint and a fast/robust solution procedure will be needed. A robust massively parallel processing (MPP) capability will also be required to provide reasonable turnaround times on the analyses that will be performed with the code. A performance assessment (PA) calculation for a waste disposal system generally requires a large number (hundreds to thousands) of model simulations to quantify the effect of model parameter uncertainties on the predicted repository performance. A set of codes for a PA calculation must be sufficiently robust and fast in terms of code execution. A PA system as a whole must be able to provide multiple alternative models for a specific set of physical/chemical processes, so that the users can choose various levels of modeling complexity based on their modeling needs. This requires PA codes, preferably, to be highly modularized. Most of the existing codes have difficulties meeting these requirements. Based on the gap analysis results, we have made the following recommendations for the code selection and code development for the NEAMS waste IPSC: (1) build fully coupled high-fidelity THCMBR codes using the existing SIERRA codes (e.g., ARIA and ADAGIO) and platform, (2) use DAKOTA to build an enhanced performance assessment system (EPAS), and build a modular code architecture and key code modules for performance assessments. The key chemical calculation modules will be built by expanding the existing CANTERA capabilities as well as by extracting useful components from other existing codes.

  4. Transformation and Quantization

    E-Print Network [OSTI]

    Yang, Shih-Hsuan

    Transformation and Quantization Shih-Hsuan Yang CSIE Department, NTUT #12;Contents Quantization and Distortion Analysis Lloyd Quantizer Vector Quantization Block Transforms Transform Kernels JPEG Other

  5. Lorentz Transformations

    E-Print Network [OSTI]

    Bernard R. Durney

    2011-12-09T23:59:59.000Z

    This paper describes a particularly didactic and transparent derivation of basic properties of the Lorentz group. The generators for rotations and boosts along an arbitrary direction, as well as their commutation relations, are written as functions of the unit vectors that define the axis of rotation or the direction of the boost (an approach that can be compared with the one that in electrodynamics, works with the electric and magnetic fields instead of the Maxwell stress tensor). For finite values of the angle of rotation or the boost's velocity, collectively denoted by V, the existence of an exponential expansion for the coordinate transformation's matrix, M (in terms of GV where G is the generator) requires that the matrix's derivative with respect to V, be equal to GM. This condition can only be satisfied if the transformation is additive as it is indeed the case for rotations, but not for velocities. If it is assumed, however, that for boosts such an expansion exists, with V = V(v), v being the velocity, and if the above condition is imposed on the boost's matrix then its expression in terms of hyperbolic cosh(V) and sinh(V} is recovered, and the expression for V(= arc tanh(v)) is determined. A general Lorentz transformation can be written as an exponential containing the sum of a rotation and a boost, which to first order is equal to the product of a boost with a rotation. The calculations of the second and third order terms show that the equations for the generators used in this paper, allow to reliably infer the expressions for the higher order generators, without having recourse to the commutation relations. The transformationmatrices for Weyl spinors are derived for finite values of the rotation and velocity, and field representations, leading to the expression for the angular momentum operator, are studied.

  6. Nuclear Astrophysics

    E-Print Network [OSTI]

    Carl R. Brune

    2005-02-28T23:59:59.000Z

    Nuclear physics has a long and productive history of application to astrophysics which continues today. Advances in the accuracy and breadth of astrophysical data and theory drive the need for better experimental and theoretical understanding of the underlying nuclear physics. This paper will review some of the scenarios where nuclear physics plays an important role, including Big Bang Nucleosynthesis, neutrino production by our sun, nucleosynthesis in novae, the creation of elements heavier than iron, and neutron stars. Big-bang nucleosynthesis is concerned with the formation of elements with A nuclear physics inputs required are few-nucleon reaction cross sections. The nucleosynthesis of heavier elements involves a variety of proton-, alpha-, neutron-, and photon-induced reactions, coupled with radioactive decay. The advent of radioactive ion beam facilities has opened an important new avenue for studying these processes, as many involve radioactive species. Nuclear physics also plays an important role in neutron stars: both the nuclear equation of state and cooling processes involving neutrino emission play a very important role. Recent developments and also the interplay between nuclear physics and astrophysics will be highlighted.

  7. Department of Energy Announces Fellows Program for Advance Research...

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

    and entrepreneurs as we continue to look for creative and inventive approaches to transform the global energy landscape while advancing America's technology leadership." The...

  8. AMO's New Institute for Advanced Composites Manufacturing Innovation...

    Energy Savers [EERE]

    as strong and twice as light as the lightest metals. These advanced materials have the potential to transform products ranging from wind turbines to automobiles. This new...

  9. Testability Transformation --Program Transformation to Improve Testability

    E-Print Network [OSTI]

    Binkley, David W.

    Testability Transformation -- Program Transformation to Improve Testability Mark Harman1 , Andr, 26 Richmond Street, Glasgow G1 1XH, UK. Corresponding Author. Abstract. Testability transformation. The goal is to improve the testing process by transforming a program to one that is more amenable

  10. Testability Transformation: Program Transformation to Improve Testability

    E-Print Network [OSTI]

    Singer, Jeremy

    Testability Transformation: Program Transformation to Improve Testability An Overview of Recent Author. Abstract. Testability transformation is a new form of program transfor- mation in which the goal to some chosen test adequacy criterion. The goal is to improve the testing process by transforming

  11. Transformation Transformation Sommersemester 2012 1 / 121

    E-Print Network [OSTI]

    Snelting, Gregor

    Testability Transformation: Program Transformation to Improve Testability An Overview of Recent Author. Abstract. Testability transformation is a new form of program transfor- mation in which the goal to some chosen test adequacy criterion. The goal is to improve the testing process by transforming

  12. Transformation Market Transformation is based on

    E-Print Network [OSTI]

    Market Transformation Market Transformation is based on the concept that federal support can and reducing high insurance costs. Strategies Market Transformation's primary goal is to accelerate-world implementation Market transformation is built on forming partnerships with stakeholders through- out the country

  13. Tag: transformation

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security AdministrationcontrollerNanocrystallineForeign ObjectOUR TableE9.security Tag: security Displaying

  14. UTNEUPDATEUTNEUPDATEA Publication from the Department of Nuclear Engineering at the University of Tennessee Continues Nuclear

    E-Print Network [OSTI]

    Tennessee, University of

    UTNEUPDATEUTNEUPDATEA Publication from the Department of Nuclear Engineering at the University of Tennessee FALL 2014 UCOR Continues Nuclear Engineering Support Sam Donnald and Nathan Capps Outstanding NE Engineering Achieves Major Advances in Enrollment, Research, and Recognition UT Nuclear Engineering Achieves

  15. E-Print Network 3.0 - advanced development volume Sample Search...

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

    Advanced Fuel Cycle... (GNEP). An Argonne researcher tests a nuclear fuel treatment process. Advanced Separations ... Source: Kemner, Ken - Biosciences Division, Argonne...

  16. MIT Nuclear Space Research Andrew C. Kadak

    E-Print Network [OSTI]

    SELENE MIT Nuclear Space Research Andrew C. Kadak Professor of the Practice Nuclear Science with Nuclear Energy ­ Selene - Sodium-Cooled Epithermal Long-term Exploration Nuclear Engine (MS thesis) ­ The Martian Surface Reactor: An Advanced Nuclear Power Station for Manned Extraterrestrial Exploration

  17. Ultrafast Transformations in Superionic Nanocrystals

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIAUltrafast Transformations in Superionic

  18. Presented by CASL: The Consortium for Advanced

    E-Print Network [OSTI]

    Presented by Nuclear Energy CASL: The Consortium for Advanced Simulation of Light Water Reactors A DOE Energy Innovation Hub for Modeling and Simulation of Nuclear Reactors Doug Kothe Director, CASL is a DOE Energy Innovation Hub? · Modeled after research entities like the Manhattan Project (nuclear

  19. 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)

  20. Analyzing Signals Fourier transform

    E-Print Network [OSTI]

    Sweldens, Wim

    Page 1 1 Analyzing Signals Fourier transform s frequency content s linear combination of sin frequency analysis s windowed Fourier transform 6 #12;Page 4 7 Gabor Transform function to analyze window Gabor Transform Spatial domain Gabor domain b #12;Page 5 9 Gabor Transform Problems s discrete version

  1. E-Print Network 3.0 - amplified dispersive fourier-transform...

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

    fourier-transform Search Powered by Explorit Topic List Advanced Search Sample search results for: amplified dispersive fourier-transform Page: << < 1 2 3 4 5 > >> 1 Pulse energy...

  2. GIS TRANSFORMATIONS Conference Presentation

    E-Print Network [OSTI]

    Tobler, Waldo

    GIS TRANSFORMATIONS Conference Presentation Waldo Tobler Geography Department University, line, area, or field phenomena, then the sixteen common classes of transformation are: point -> point (scalar, vector, tensor) data, to obtain eighty distinct possible classes of transformation. The common

  3. Transformations KolahdouzRahimi

    E-Print Network [OSTI]

    Lano, Kevin Charles

    An Incremental XSLT Transformation Processor for XML Document Manipulation Lionel Villard ­ Nabil;Outline Motivation Incremental transformations Principles Static Analysis Incremental execution Conclusion presentation architecture NegotiationNegotiation Result of negotiation (Transformation Sheets) Result

  4. Advancing Small Modular Reactors: How We're Supporting Next-Gen...

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

    Advancing Small Modular Reactors: How We're Supporting Next-Gen Nuclear Energy Technology Advancing Small Modular Reactors: How We're Supporting Next-Gen Nuclear Energy Technology...

  5. Evaluating Transformer Losses

    E-Print Network [OSTI]

    Grun, R. L. Jr.

    and replacing them with low loss units. Today few industrials evaluate losses on either power or distribution transformers. TRANSFORMER LOSSES Transformer losses are divided 'nto load losses and no-load losses. Load losses are due to the winding resista... therefore are a function of the load squared. No-load losses occur from energizing the transformer steel and fore are continuous regardless of the transformer load. TRANSFORMER DESIGN Both types of losses are a fun ce here ion of design. If losses...

  6. E-Print Network 3.0 - advanced pwr fuel Sample Search Results

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

    Advanced nuclear reactor theory... equations, prompt jump approximation; subcritical reactor kinetics, circulating fuel reactor dynamics 5... Short-term Reactivity...

  7. Enterprise SRS: Leveraging Ongoing Operations to Advance National Programs - 13108

    SciTech Connect (OSTI)

    Marra, J.E.; Murray, A.M. [Savannah River National Laboratory, Building 773-A, Aiken S.C 29808 (United States)] [Savannah River National Laboratory, Building 773-A, Aiken S.C 29808 (United States); McGuire, P.W.; Wheeler, V.B. [Department of Energy-Savannah River Operations Office, Aiken SC 29808 (United States)] [Department of Energy-Savannah River Operations Office, Aiken SC 29808 (United States)

    2013-07-01T23:59:59.000Z

    The SRS is re-purposing its vast array of assets to solve future national issues regarding environmental stewardship, national security, and clean energy. The vehicle for this transformation is Enterprise SRS which presents a new, strategic view of SRS as a united endeavor for 'all things nuclear' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into facilities in conjunction with ongoing missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, The DOE Savannah River Operations Office, Savannah River Nuclear Solutions, and the Savannah River National Laboratory (SRNL) have established the Center for Applied Nuclear Materials Processing and Engineering Research (CANMPER). The key objective of this initiative is to bridge the gap between promising transformational nuclear materials management advancements and large-scale deployment of the technology by leveraging SRS assets (e.g. facilities, staff, and property) for those critical engineering-scale demonstrations necessary to assure the successful deployment of new technologies. CANMPER will coordinate the demonstration of R and D technologies and serve as the interface between the engineering-scale demonstration and the R and D programs, essentially providing cradle-to-grave support to the R and D team during the demonstration. While the initial focus of CANMPER will be on the effective use of SRS assets for these demonstrations, CANMPER also will work with research teams to identify opportunities to perform R and D demonstrations at other facilities. Unique to this approach is the fact that these SRS assets will continue to accomplish DOE's critical nuclear material missions (e.g., processing in H-Canyon and plutonium storage in K-Area). The demonstration can be accomplished in a more cost-effective manner through the use of existing facilities in conjunction with ongoing missions. Essentially, the R and D program would not need to pay the full operational cost of a facility, just the incremental cost of performing the demonstration. Current CANMPER activities have been focused on integrating advanced safeguards monitoring technology demonstrations into the SRS H-Canyon and advanced location technology demonstrations into K-Area Materials Storage. These demonstrations are providing valuable information to researchers and program owners. In addition these demonstrations are providing CANMPER with an improved protocol for demonstration management that can be exercised across the entire SRS (and to offsite venues) to ensure that future demonstrations are done efficiently and provide an opportunity to use these unique assets for multiple purposes involving national laboratories, academia, and commercial entities. Key among the envisioned future demonstrations is the use of H-Canyon to demonstrate new nuclear materials separations technologies critical for advancing the mission needs of three major program offices: DOE-EM, DOE-Nuclear Energy (DOE-NE), and the NNSA. Given the modular design of H-Canyon, the demonstrations would be accomplished using a process frame. The demonstration equipment would be installed on the process frame and that frame would then be positioned into an H Canyon cell so that the demonstration is performed in a radiological environment involving prototypic nuclear materials. (authors)

  8. Advancing Cellulosic Ethanol for Large Scale Sustainable Transportation

    E-Print Network [OSTI]

    Wyman, C

    2007-01-01T23:59:59.000Z

    Advancing Cellulosic Ethanol for Large Scale SustainableHydrogen Batteries Nuclear By Lee Lynd, Dartmouth Ethanol •Ethanol, ethyl alcohol, fermentation ethanol, or just “

  9. Application for Graduate Admission Supplementary Application Advanced Engineering Programs

    E-Print Network [OSTI]

    Rubloff, Gary W.

    061) Nuclear Engineering (online) (Z050) Project Management (Z063) Project Management (online) (Z040) Materials Science and Engineering (PMMS) Mechanical Engineering (PMME) Nuclear Engineering (online) (MENUApplication for Graduate Admission Supplementary Application ­ Advanced Engineering Programs Please

  10. 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.

  11. Learning Transformations From Video

    E-Print Network [OSTI]

    Wang, Ching Ming

    2010-01-01T23:59:59.000Z

    on Natural Video . . . . . . . . . . . . . . . . .3 Learning Continuous Transformation from VideoProposed Video Coder

  12. transformation languages Introduction

    E-Print Network [OSTI]

    Nierstrasz, Oscar

    transformation languages Introduction Transformation languages are widely used for to process can I change / transform the design of a certain task without changing it's logic The common/and hierarchical or/and abstract set of information. It can even be a stream of data. · The transformation engine

  13. TRANSFORMATIONAL GOALS FOR THE

    E-Print Network [OSTI]

    Rhode Island, University of

    TRANSFORMATIONAL GOALS FOR THE 21ST CENTURY PROGRESS REPORT FALL 2014 #12;CONTENTS EXECUTIVE Transformational Goals progress report Fall 2014 #12;Transformational Goals Progress Report | FALL 20142 In 2010 Island Build a community at URI that values and embraces equity and diversity #12;Transformational Goals

  14. 2006 NUCLEAR ENERGY RESEARCH INITIATIVE AWARDS

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

    NUCLEAR ENERGY RESEARCH INITIATIVE AWARDS Lead Organization Project Title Collaborators Advanced Fuel Cycle Initiative Massachusetts Institute of Technology The Development and...

  15. Celebrating 15 years | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    established NNSA in 2000 as a separately organized agency within the Department of Energy to manage and ensure the security of the Nation's nuclear weapons stockpile, advance...

  16. 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...

  17. 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...

  18. Code Transformations for Energy-Efficient Device Management

    E-Print Network [OSTI]

    Bianchini, Ricardo

    transformations that increase device idle times and inform the operating system about the length of each upcoming, or both. Recent advances in fast, low-power microproces- sors and their use in battery-operated computersCode Transformations for Energy-Efficient Device Management Taliver Heath, Eduardo Pinheiro, Jerry

  19. Perfect NOT transformation and conjugate transformation

    E-Print Network [OSTI]

    Fengli Yan; Ting Gao; Zhichao Yan

    2012-03-15T23:59:59.000Z

    The perfect NOT transformation, probabilistic perfect NOT transformation and conjugate transformation are studied. Perfect NOT transformation criteria on a quantum state set $S$ of a qubit are obtained. Two necessary and sufficient conditions for realizing a perfect NOT transformation on $S$ are derived. When these conditions are not satisfied we discuss a probabilistic perfect NOT transformation (gate). We construct a probabilistic perfect NOT machine (gate) by a general unitary-reduction operation. With a postselection of the measurement outcomes, the probabilistic NOT gate yields perfectly complements of the input states. We prove that one can realize probabilistically the NOT gate of the input states secretly chosen from a certain set $S=\\{|\\Psi_1>, |\\Psi_2>,..., |\\Psi_n>\\}$ if and only if $|\\Psi_1>, |\\Psi_2>,...,$ and $|\\Psi_n>$ are linearly independent. We also generalize the probabilistic NOT transformation to the conjugate transformation in the multi-level quantum system. The lower bound of the best possible efficiencies attained by a probabilistic perfect conjugate transformation are obtained.

  20. Radiation effects in nuclear materials: Role of nuclear and electronic energy losses and their synergy

    SciTech Connect (OSTI)

    Thomé, Lionel [Centre de Spectrométrie Nucléaire et de Spectrométrie de Masse, CNRS-IN2P3-Université Paris-Sud; Debelle, Aurelien [Universite Paris Sud, Orsay, France; Garrido, Frederico [Universite Paris Sud, Orsay, France; Mylonas, Stamatis [Universite Paris Sud, Orsay, France; Décamps, B. [Universite Paris Sud, Orsay, France; Bachelet, C. [Universite Paris Sud, Orsay, France; Sattonnay, G. [LEMHE/ICMMO, Université Paris-Sud, Bât. Orsay, France; Moll, Sandra [French Atomic Energy Commission (CEA), Centre de Saclay, Gif sur Yvette; Pellegrino, S. [French Atomic Energy Commission (CEA); Miro, S. [French Atomic Energy Commission (CEA); Trocellier, P. [French Atomic Energy Commission (CEA); Serruys, Y. [French Atomic Energy Commission (CEA); Velisa, G. [French Atomic Energy Commission (CEA); Grygiel, C. [CNRS, France; Monnet, I. [CIMAP, CEA-CNRS-Université de Caen, France; Toulemonde, Marcel [French Atomic Energy Commission (CEA), French National Centre for Scientific Research (CNRS)-ENSICAE; Simon, P. [CEMHTI, CNRS, France; Jagielski, Jacek [Institute for Electronic Materials Technology; Jozwik-Biala, Iwona [Institute for Electronic Materials Technology; Nowicki, Lech [Soltan Institute for Nuclear Studies, Swierk, Poland; Behar, M. [Instituto de Fisica, Universidade Federal do Rio Grande do Sul, Porto Alegre,; Weber, William J [ORNL; Zhang, Yanwen [ORNL; Backman, Marie [University of Tennessee, Knoxville (UTK); Nordlund, Kai [University of Helsinki; Djurabekova, Flyura [University of Helsinki

    2013-01-01T23:59:59.000Z

    Ceramic oxides and carbides are promising matrices for the immobilization and/or transmutation of nuclear wastes, cladding materials for gas-cooled fission reactors and structural components for fusion reactors. For these applications there is a need of fundamental data concerning the behavior of nuclear ceramics upon irradiation. This article is focused on the presentation of a few remarkable examples regarding ion-beam modifications of nuclear ceramics with an emphasis on the mechanisms leading to damage creation and phase transformations. Results obtained by combining advanced techniques (Rutherford backscattering spectrometry and channeling, X-ray diffraction, transmission electron microscopy, Raman spectroscopy) concern irradiations in a broad energy range (from keV to GeV) with the aim of exploring both nuclear collision (Sn) and electronic excitation (Se) regimes. Finally, the daunting challenge of the demonstration of the existence of synergistic effects between Sn and Se is tackled by discussing the healing due to intense electronic energy deposition (SHIBIEC) and by reporting results recently obtained in dual-beam irradiation (DBI) experiments.

  1. Ultrafast Transformations in Superionic Nanocrystals

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIAUltrafast Transformations in SuperionicUltrafast

  2. Advanced Fuels Campaign 2012 Accomplishments

    SciTech Connect (OSTI)

    Not Listed

    2012-11-01T23:59:59.000Z

    The Advanced Fuels Campaign (AFC) under the Fuel Cycle Research and Development (FCRD) program is responsible for developing fuels technologies to support the various fuel cycle options defined in the DOE Nuclear Energy Research and Development Roadmap, Report to Congress, April 2010. The fiscal year 2012 (FY 2012) accomplishments are highlighted below. Kemal Pasamehmetoglu is the National Technical Director for AFC.

  3. Department of Advanced Materials Science

    E-Print Network [OSTI]

    Katsumoto, Shingo

    @k.u-tokyo.ac.jpe-mail 04-7136-3781T E L Environmental-friendly materials process, Metal smelting and re ning process of Advanced Materials Science masashi@issp.u-tokyo.ac.jpe-mail 04-7136-3225T E L Nuclear magnetic resonance New Materials Synthesis, Superconductivity, Quantum Spin Liquid,Topological Hall Effect takatama

  4. Gauge transformations are canonical transformations, redux

    E-Print Network [OSTI]

    Z. K. Silagadze

    2014-09-02T23:59:59.000Z

    In this short note we return to the old paper by Tai L. Chow (Eur. J. Phys. 18 (1997), 467-468) and correct its erroneous final part. We also note that the main result of that paper, that gauge transformations of mechanics are canonical transformations, was known much earlier.

  5. Advanced Safeguards Approaches for New Reprocessing Facilities

    SciTech Connect (OSTI)

    Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Richard; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

    2007-06-24T23:59:59.000Z

    U.S. efforts to promote the international expansion of nuclear energy through the Global Nuclear Energy Partnership (GNEP) will result in a dramatic expansion of nuclear fuel cycle facilities in the United States. New demonstration facilities, such as the Advanced Fuel Cycle Facility (AFCF), the Advanced Burner Reactor (ABR), and the Consolidated Fuel Treatment Center (CFTC) will use advanced nuclear and chemical process technologies that must incorporate increased proliferation resistance to enhance nuclear safeguards. The ASA-100 Project, “Advanced Safeguards Approaches for New Nuclear Fuel Cycle Facilities,” commissioned by the NA-243 Office of NNSA, has been tasked with reviewing and developing advanced safeguards approaches for these demonstration facilities. Because one goal of GNEP is developing and sharing proliferation-resistant nuclear technology and services with partner nations, the safeguards approaches considered are consistent with international safeguards as currently implemented by the International Atomic Energy Agency (IAEA). This first report reviews possible safeguards approaches for the new fuel reprocessing processes to be deployed at the AFCF and CFTC facilities. Similar analyses addressing the ABR and transuranic (TRU) fuel fabrication lines at AFCF and CFTC will be presented in subsequent reports.

  6. Uncertainty Analyses of Advanced Fuel Cycles

    SciTech Connect (OSTI)

    Laurence F. Miller; J. Preston; G. Sweder; T. Anderson; S. Janson; M. Humberstone; J. MConn; J. Clark

    2008-12-12T23:59:59.000Z

    The Department of Energy is developing technology, experimental protocols, computational methods, systems analysis software, and many other capabilities in order to advance the nuclear power infrastructure through the Advanced Fuel Cycle Initiative (AFDI). Our project, is intended to facilitate will-informed decision making for the selection of fuel cycle options and facilities for development.

  7. Finding transition states for crystalline solidsolid phase transformations

    E-Print Network [OSTI]

    Barr, Al

    a method to identify transition states and minimum energy paths for martensitic solid­solid phase transformations, thereby allowing quantification of the activation energies of such transformations. Our approach introduce an analogue to the Born­ Oppenheimer approximation that allows a decoupling of nuclear motion

  8. E-Print Network 3.0 - advanced computed tomography Sample Search...

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

    advanced computed tomography Page: << < 1 2 3 4 5 > >> 1 CAT scan and RadonX-ray transform Relations with the Fourier transform. Dual Radon Summary: problems X-ray tomography...

  9. Advanced Simulation Capability

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power Systems EngineeringDepartment of EnergyAbout UsAdvanced Modeling &NuclearNewsletter3

  10. Implementing Arrangement Between the U.S. Department of Energy and the Agency of Natural Resources and Energy of Japan Concerning Cooperation in the Joint Nuclear Energy Research Initiative

    Broader source: Energy.gov [DOE]

    Sharing an interest in fostering advanced nuclear engineering and pursuing scientific research and development in the nuclear field; 

  11. Landscapes of transformation

    E-Print Network [OSTI]

    Ambs, Emily (Emily Kiersten)

    2007-01-01T23:59:59.000Z

    This thesis aims to examine the cultural effect of transformation through the lens of procedural techniques applied to the human body and architecture. The body and architecture both operate as landscapes of transformation. ...

  12. Metrics for enterprise transformation

    E-Print Network [OSTI]

    Blackburn, Craig D. (Craig David), S. M. Massachusetts Institute of Technology

    2009-01-01T23:59:59.000Z

    The objective of this thesis is to depict the role of metrics in the evolving journey of enterprise transformation. To this end, three propositions are explored: (i) metrics and measurement systems drive transformation, ...

  13. Transformations Ordered set of

    E-Print Network [OSTI]

    Jacobs, David

    Modeling Transformations Michael Kazhdan (600.357 / 600.457) HB Ch. 5 FvDFH Ch. 5 #12;Anouncements · Assignment 2 has been posted! #12;Overview · Ray-Tracing so far · Modeling transformations #12;Ray Casting

  14. The Patch Transform

    E-Print Network [OSTI]

    Avidan, Shai

    The patch transform represents an image as a bag of overlapping patches sampled on a regular grid. This representation allows users to manipulate images in the patch domain, which then seeds the inverse patch transform to ...

  15. LAPPED TRANSFORMS COMPRESSION

    E-Print Network [OSTI]

    de Queiroz, Ricardo L.

    Chapter 6 LAPPED TRANSFORMS FOR IMAGE COMPRESSION Ricardo L. de Queiroz Digital Imaging Technology aspects of lapped transforms and their applications to image compression. It is a subject that has been extensively studied mainly because lapped transforms are closely related to filter banks, wavelets, and time

  16. TRANSFORMATIONAL GOALS FOR THE

    E-Print Network [OSTI]

    Rhode Island, University of

    TRANSFORMATIONAL GOALS FOR THE 21ST CENTURY The presidenT's 21sT cenTury fund for excellence #12;TRANSFORMATIONAL GOALS FOR THE 21ST CENTURY 1 THE UNIVERSITY OF RHODE ISLAND The University of Rhode Island and transform our approaches to teaching, research, and service so that we can prepare students for a rapidly

  17. Transforming Health Research

    E-Print Network [OSTI]

    Diggle, Peter J.

    Transforming Health Research the first two years National Institute for Health Research Progress For Information R OCR R ef: 0 Gateway R ef: 9298 Title Transforming Health Research the first two years. Health Institute for Health Research Progress Report i Transforming Health Research the first two years National

  18. transform e Construction

    E-Print Network [OSTI]

    Csürös, Miklós

    Abstraction by Symbolic Indexing Transformations Thomas F. Melham1 and Robert B. Jones2 1 describes some logical machinery aimed at bridging these gaps. We present an algorithm to transform ordinary-conditions that must hold for this transformation to be sound. We also describe how the algorithm can be applied

  19. Transformation and Quantization

    E-Print Network [OSTI]

    Yang, Shih-Hsuan

    ' & $ % Linear Transformations (Yet Again!!) Mark Gales CAMBRIDGE UNIVERSITY ENGINEERING DEPARTMENT mjfg@eng.cam.ac.uk 1 #12; ' & $ % Introduction Linear transformations within HMM systems have been shown to be very useful. ffl Adaptation: MLLR, SAT, CAT, Cluster Transform etc etc. ffl Feature space

  20. Transforming Anxiety into ENERGYTM

    E-Print Network [OSTI]

    Maryland, Baltimore County, University of

    Transforming Anxiety into ENERGYTM How to Prevent Panic and Promote Productivity in Turbulent Times By Wendy Mack with contributions from Meredith Kimbell and Myron Radio #12;Transforming Anxiety into Energy, consultants, and researchers who shared their stories and expertise. 1 #12;Transforming Anxiety into Energy

  1. Spacetime transformation acoustics

    E-Print Network [OSTI]

    C. García-Meca; S. Carloni; C. Barceló; G. Jannes; J. Sánchez-Dehesa; A. Martínez

    2014-07-08T23:59:59.000Z

    A recently proposed analogue transformation method has allowed the extension of transformation acoustics to general spacetime transformations. We analyze here in detail the differences between this new analogue transformation acoustics (ATA) method and the standard one (STA). We show explicitly that STA is not suitable for transformations that mix space and time. ATA takes as starting point the acoustic equation for the velocity potential, instead of that for the pressure as in STA. This velocity-potential equation by itself already allows for some transformations mixing space and time, but not all of them. We explicitly obtain the entire set of transformations that do not leave its form invariant. It is in these cases that ATA shows its true potential, allowing for building a transformation acoustics method that enables the full range of spacetime transformations. We provide an example of an important transformation which cannot be achieved with STA. Using this transformation, we design and simulate an acoustic frequency converter via the ATA approach. Furthermore, in those cases in which one can apply both the STA and ATA approaches, we study the different transformational properties of the corresponding physical quantities.

  2. TRANSFORM a electronics

    E-Print Network [OSTI]

    Candan, Cagatay

    THE DISCRETE FRACTIONAL FOURIER TRANSFORM a thesis submitted to the department of electrical TRANSFORM C ¸a~ gatay Candan M.S. in Electrical and Electronics Engineering Supervisor: Haldun M. ¨ Ozakta Transform (FrFT) is proposed, discussed and consolidated. The discrete trans­ form generalizes the Discrete

  3. Transformation haskell-Programs

    E-Print Network [OSTI]

    Ábrahám, Erika

    On the Transformation of Control Flow between Block-Oriented and Graph-Oriented Process Modeling E-mail: zdun@acm.org Abstract: Much recent research work discusses the transformation between differ. In this article, we aim to abstract from concrete transformations by distinguishing two major paradigms

  4. The Tunneling Transform

    E-Print Network [OSTI]

    Robert Hipple

    2014-11-10T23:59:59.000Z

    We supplement the Lorentz transform $L(v)$ with a new "Tunneling" transform $T(v)$. Application of this new transform to elementary quantum mechanics offers a novel, intuitive insight into the nature of quantum tunneling; in particular, the so called "Klein Paradox" is discussed.

  5. Transforming Data into Knowledge

    E-Print Network [OSTI]

    Giles, C. Lee

    The Application Of Correctness Preserving Transformations To Software Maintenance J. Paul Gibson transformation (CPT), to a real software engineering prob- lem: the need for optimization during the maintenance of code. We present four program transformations and a model that forms a framework for proof

  6. transforming human health

    E-Print Network [OSTI]

    Kenny, Paraic

    transforming human health AnnUAl REpoRt 2011­2012 #12;#12;how we're changing medical research 1 are transforming health. He proposed an entirely new theory for developing drugs to treat diseases that have malaria and solid tumors such as lung and breast cancers are in development. #12;A TrAnsformATive educ

  7. Transforming our information systems

    E-Print Network [OSTI]

    Strathclyde, University of

    Transforming our information systems and technology Information Systems Development Framework #12 university. In support of this position we are transforming our information systems, servicesDonald Principal and Vice-Chancellor #12;Strategy for transformation Tactical Delivering the services and tools our

  8. Mark Peters testifies for Congress on nuclear energy 5/19/10

    SciTech Connect (OSTI)

    Peters, Mark

    2010-01-01T23:59:59.000Z

    Mark Peters, Deputy Lab Director at Argonne National Laboratory, testifies before Congress on advanced nuclear fuel cycle R&D and the DOE nuclear roadmap. May 19, 2010.

  9. Mark Peters testifies for Congress on nuclear energy 5/19/10

    SciTech Connect (OSTI)

    Mark Peters

    2010-05-25T23:59:59.000Z

    Mark Peters, Deputy Lab Director at Argonne National Laboratory, testifies before Congress on advanced nuclear fuel cycle R&D and the DOE nuclear roadmap. May 19, 2010.

  10. Mark Peters testifies for Congress on nuclear energy 5/19/10

    ScienceCinema (OSTI)

    Peters, Mark

    2013-04-19T23:59:59.000Z

    Mark Peters, Deputy Lab Director at Argonne National Laboratory, testifies before Congress on advanced nuclear fuel cycle R&D and the DOE nuclear roadmap. May 19, 2010.

  11. Mark Peters testifies for Congress on nuclear energy 5/19/10

    ScienceCinema (OSTI)

    Mark Peters

    2010-09-01T23:59:59.000Z

    Mark Peters, Deputy Lab Director at Argonne National Laboratory, testifies before Congress on advanced nuclear fuel cycle R&D and the DOE nuclear roadmap. May 19, 2010.

  12. E-Print Network 3.0 - automated nuclear chemistry Sample Search...

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

    chemistry Search Powered by Explorit Topic List Advanced Search Sample search results for: automated nuclear chemistry Page: << < 1 2 3 4 5 > >> 1 Dr. Jeff Fortner Nuclear Power...

  13. Invertible Darboux Transformations

    E-Print Network [OSTI]

    Ekaterina Shemyakova

    2013-01-04T23:59:59.000Z

    For operators of many different kinds it has been proved that (generalized) Darboux transformations can be built using so called Wronskian formulae. Such Darboux transformations are not invertible in the sense that the corresponding mappings of the operator kernels are not invertible. The only known invertible ones were Laplace transformations (and their compositions), which are special cases of Darboux transformations for hyperbolic bivariate operators of order 2. In the present paper we find a criteria for a bivariate linear partial differential operator of an arbitrary order d to have an invertible Darboux transformation. We show that Wronkian formulae may fail in some cases, and find sufficient conditions for such formulae to work.

  14. Sandia National Laboratories: Advanced Research & Development

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0Energy Advanced Nuclear Energy The Advanced Nuclear

  15. Transformation Nets -A Runtime Model for Transformation Languages

    E-Print Network [OSTI]

    Hochreiter, Sepp

    Transformation Nets - A Runtime Model for Transformation Languages Johannes Schoenboeck Institute transformation languages. Although numerous approaches are available, they lack convenient facilities for supporting debugging and understand- ing of the transformation logic. This is not least because

  16. Nuclear medicine review syllabus

    SciTech Connect (OSTI)

    Kirchner, P.T. (ed.)

    1980-01-01T23:59:59.000Z

    A comprehensive review of the major scientific and clinical advances that have occurred in nuclear medicine since the early 1970s is given. The chapters include Radiopharmacology, Instrumentation, Radiation Effects and Radiation Protection, Cardiovascular, Central Nervous System, Endocrinology, Gastroenterology, Genito-Urinary System. Hematology-Oncology, Pulmonary, Radioassay, and the Skeletal System.

  17. Advanced Combustion

    SciTech Connect (OSTI)

    Holcomb, Gordon R. [NETL

    2013-03-11T23:59:59.000Z

    The activity reported in this presentation is to provide the mechanical and physical property information needed to allow rational design, development and/or choice of alloys, manufacturing approaches, and environmental exposure and component life models to enable oxy-fuel combustion boilers to operate at Ultra-Supercritical (up to 650{degrees}C & between 22-30 MPa) and/or Advanced Ultra-Supercritical conditions (760{degrees}C & 35 MPa).

  18. Advances in nuclear instrumentation for safeguards

    SciTech Connect (OSTI)

    Prettyman, T.H.; Reilly, T.D.; Miller, M.C.; Hollas, C.L.; Pickrell, M.M.; Prommel, J.M.; Dreicer, J.S.

    1996-12-31T23:59:59.000Z

    This paper describes detectors, instrumentation, and analytical methods under development to address the above issues. The authors will describe work underway on room-temperature semiconductors including attempts to model the response of these detectors to improve spectrum analysis procedures and detector design. Computerized tomography is used in many medical and industrial applications; they are developing both gamma-ray and neutron tomography for improved measurements of waste and direct-use materials. Modern electronics and scintillation detectors should permit the development of fast neutron coincidence detectors with dramatically improved signal-to-noise ratios. For active measurements, they are studying several improved neutron sources, including a high-fluence, plasma-based, d-t generator. New analysis tools from information theory may permit one to better combine data from different measurement systems. This paper attempts to briefly describe a range of new sensors, electronics, and data analysis methods under study at Los Alamos and other laboratories to promote discussion of promising technology that they may bring to bear on these important global issues.

  19. Advanced Technology Development and Mitigation | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Technology Development and Mitigation This sub-program includes laboratory code and computer engineering and science projects that pursue long-term simulation and computing goals...

  20. Integrated Nuclear-Renewable Energy Systems: Foundational Workshop Report

    SciTech Connect (OSTI)

    Shannon Bragg-Sitton; Richard Boardman; John Collins; Mark Ruth; Owen Zinaman; Charles Forsberg

    2014-08-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) recognizes the need to transform the energy infrastructure of the U.S. and elsewhere to systems that can drastically reduce environmental impacts in an efficient and economically viable manner while utilizing both hydrocarbon resources and clean energy generation sources. Thus, DOE is supporting research and development that could lead to more efficient utilization of clean energy generation sources, including renewable and nuclear options. A concept being advanced by the DOE Offices of Nuclear Energy (NE) and Energy Efficiency and Renewable Energy (EERE) is tighter coupling of nuclear and renewable energy sources in a manner that produces new energy currency for the combined electricity grid, industrial manufacturing, and the transportation energy sectors. This integration concept has been referred to as a “hybrid system” that is capable of providing the right type of energy, at the right time, in the right place. At the direction of DOE-NE and DOE-EERE leadership, project leads at Idaho National Laboratory (INL), National Renewable Energy Laboratory (NREL) and Massachusetts Institute of Technology (MIT) have identified and engaged stakeholders in discussing integrated energy systems that would optimize renewable and nuclear energy integration on a region-by-region basis. Subsequent work will entail conduct of technical, economic, environmental and socio-political evaluations of the leading integrated system options based on a set of criteria established with stakeholder input. The Foundational Workshop for Integrated Nuclear – Renewable Energy Systems was organized around the following objectives: 1. Identify and refine priority region-specific opportunities for integrated nuclear-renewable energy systems in the U.S.; 2. Select Figures of Merit (FOM) to rank and prioritize candidate systems; 3. Discuss enabling technology development needs; 4. Identify analysis requirements, capabilities and gaps to estimate FOM for integrated system options; 5. Identify experimental needs to develop and demonstrate nuclear-renewable energy systems.

  1. Grid Transformation Workshop

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

    3-03-Grid-Transformation-Workshop Sign In About | Careers | Contact | Investors | bpa.gov Search News & Us Expand News & Us Projects & Initiatives Expand Projects &...

  2. Transforming a Transformative School | Department of Energy

    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 on Delicious Rank EERE:YearRound-Up from theDepartment of EnergyThe Sun andDepartmentTransformationalTransforming a

  3. Presented by CASL: The Consortium for Advanced Simulation

    E-Print Network [OSTI]

    Presented by Nuclear Energy CASL: The Consortium for Advanced Simulation of Light Water Reactors A DOE Energy Innovation Hub for Modeling and Simulation of Nuclear Reactors Doug Kothe Director, CASL (BWR) Common types of Light Water Reactors (LWRs) #12;www.casl.gov U.S. Nuclear Energy Increasing

  4. Advanced Combustion

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth (AOD)ProductssondeadjustsondeadjustAbout the Building TechnologiesS1!4T opAddress:AdolphusAdvanced Energy

  5. Biochemical transformation of coals

    DOE Patents [OSTI]

    Lin, M.S.; Premuzic, E.T.

    1999-03-23T23:59:59.000Z

    A method of biochemically transforming macromolecular compounds found in solid carbonaceous materials, such as coal is provided. The preparation of new microorganisms, metabolically weaned through challenge growth processes to biochemically transform solid carbonaceous materials at extreme temperatures, pressures, pH, salt and toxic metal concentrations is also disclosed. 7 figs.

  6. Exploring Functional Mellin Transforms

    E-Print Network [OSTI]

    J. LaChapelle

    2015-01-08T23:59:59.000Z

    We define functional Mellin transforms within a scheme for functional integration proposed in [1]. Functional Mellin transforms can be used to define functional traces, logarithms, and determinants. The associated functional integrals are useful tools for probing function spaces in general and $C^\\ast$-algebras in particular. Several interesting aspects are explored.

  7. TRANSFORMATION FOURIER--BOREL

    E-Print Network [OSTI]

    Waldschmidt, Michel

    LA TRANSFORMATION DE FOURIER--BOREL : â?? â?? de Hilbert est duale de celle de Gel'fond, tandis que la z e , t h d dz t dont la transforme â??e de Fourier--Borel est #(u) = q th u t e h#u . 0 1 #(## 0 # 1

  8. Transforming Education at Einstein

    E-Print Network [OSTI]

    Yates, Andrew

    Transforming Education at Einstein EinstEin Winter/spring 2012 The Magazine for Alumni and Friends trANsfOrMiNg eDuCAtiON At eiNsteiN Education at Albert Einstein College of Medicine is undergoing

  9. ADVANCED REACTOR SAFETY PROGRAM – STAKEHOLDER INTERACTION AND FEEDBACK

    SciTech Connect (OSTI)

    Spencer, Benjamin W; Huang, Hai

    2014-08-01T23:59:59.000Z

    In the Spring of 2013, we began discussions with our industry stakeholders on how to upgrade our safety analysis capabilities. The focus of these improvements would primarily be on advanced safety analysis capabilities that could help the nuclear industry analyze, understand, and better predict complex safety problems. The current environment in the DOE complex is such that recent successes in high performance computer modeling could lead the nuclear industry to benefit from these advances, as long as an effort to translate these advances into realistic applications is made. Upgrading the nuclear industry modeling analysis capabilities is a significant effort that would require substantial participation and coordination from all industry segments: research, engineering, vendors, and operations. We focus here on interactions with industry stakeholders to develop sound advanced safety analysis applications propositions that could have a positive impact on industry long term operation, hence advancing the state of nuclear safety.

  10. Advanced Vehicle Testing & Evaluation

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

    Provide benchmark data for advanced technology vehicles Develop lifecycle cost data for production vehicles utilizing advanced power trains Provide fleet...

  11. Amplified Quantum Transforms

    E-Print Network [OSTI]

    David Cornwell

    2014-06-01T23:59:59.000Z

    In this thesis we investigate two new Amplified Quantum Transforms. In particular we create and analyze the Amplified Quantum Fourier Transform (Amplified-QFT) and the Amplified-Haar Wavelet Transform. First, we provide a brief history of quantum mechanics and quantum computing. Second, we examine the Amplified-QFT in detail and compare it against the Quantum Fourier Transform (QFT) and Quantum Hidden Subgroup (QHS) algorithms for solving the Local Period Problem. We calculate the probabilities of success of each algorithm and show the Amplified-QFT is quadratically faster than the QFT and QHS algorithms. Third, we examine the Amplified-QFT algorithm for solving The Local Period Problem with an Error Stream. Fourth, we produce an uncertainty relation for the Amplified-QFT algorithm. Fifth, we show how the Amplified-Haar Wavelet Transform can solve the Local Constant or Balanced Signal Decision Problem which is a generalization of the Deutsch-Jozsa algorithm.

  12. Program Transformation Mechanics A Classification of Mechanisms for Program Transformation

    E-Print Network [OSTI]

    Utrecht, Universiteit

    Program Transformation Mechanics A Classification of Mechanisms for Program Transformation with a Survey of Existing Transformation Systems Jonne van Wijngaarden Eelco Visser UU-CS-2003-048 Institute Transformation Mechanics A Classification of Mechanisms for Program Transformation with a Survey of Existing

  13. Logarithmic transformation of response Logarithmic transformation of response

    E-Print Network [OSTI]

    Komarek, Arnost

    Logarithmic transformation of response Logarithmic transformation of response Often, support S of Y is S = (0, ). Logarithm is then one of transformations to consider when trying to obtain a correct (wrong. Model Building 1. Transformation of response #12;Logarithmic transformation of response When does

  14. IMAGINED TRANSFORMATIONS 1 Running head: IMAGINED TRANSFORMATION OF BODIES

    E-Print Network [OSTI]

    Zacks, Jeffrey M.

    IMAGINED TRANSFORMATIONS 1 Running head: IMAGINED TRANSFORMATION OF BODIES Imagined Transformations TRANSFORMATIONS 2 Abstract A number of spatial reasoning problems can be solved by performing an imagined transformation of one's egocentric perspective. A series of experiments were carried out to characterize

  15. Laplace Transforms (Ch. 7) LAPLACE TRANSFORMS (Ch. 7)

    E-Print Network [OSTI]

    Meade, Douglas B.

    Laplace Transforms (Ch. 7) LAPLACE TRANSFORMS (Ch. 7) ? restart; ? with( plots ): ? with( DEtools ): The Laplace transform is a very common, and useful, technique for solving and analyz­ ing the solution of the Laplace transform is that derivatives are transformed into powers; thus, the differential equation

  16. Advanced LIGO

    E-Print Network [OSTI]

    The LIGO Scientific Collaboration

    2014-11-17T23:59:59.000Z

    The Advanced LIGO gravitational wave detectors are second generation instruments designed and built for the two LIGO observatories in Hanford, WA and Livingston, LA. The two instruments are identical in design, and are specialized versions of a Michelson interferometer with 4 km long arms. As in initial LIGO, Fabry-Perot cavities are used in the arms to increase the interaction time with a gravitational wave, and power recycling is used to increase the effective laser power. Signal recycling has been added in Advanced LIGO to improve the frequency response. In the most sensitive frequency region around 100 Hz, the design strain sensitivity is a factor of 10 better than initial LIGO. In addition, the low frequency end of the sensitivity band is moved from 40 Hz down to 10 Hz. All interferometer components have been replaced with improved technologies to achieve this sensitivity gain. Much better seismic isolation and test mass suspensions are responsible for the gains at lower frequencies. Higher laser power, larger test masses and improved mirror coatings lead to the improved sensitivity at mid- and high- frequencies. Data collecting runs with these new instruments are planned to begin in mid-2015.

  17. ADVANCED FUELS CAMPAIGN 2013 ACCOMPLISHMENTS

    SciTech Connect (OSTI)

    Not Listed

    2013-10-01T23:59:59.000Z

    The mission of the Advanced Fuels Campaign (AFC) is to perform Research, Development, and Demonstration (RD&D) activities for advanced fuel forms (including cladding) to enhance the performance and safety of the nation’s current and future reactors; enhance proliferation resistance of nuclear fuel; effectively utilize nuclear energy resources; and address the longer-term waste management challenges. This includes development of a state-of-the art Research and Development (R&D) infrastructure to support the use of “goal-oriented science-based approach.” In support of the Fuel Cycle Research and Development (FCRD) program, AFC is responsible for developing advanced fuels technologies to support the various fuel cycle options defined in the Department of Energy (DOE) Nuclear Energy Research and Development Roadmap, Report to Congress, April 2010. Accomplishments made during fiscal year (FY) 2013 are highlighted in this report, which focuses on completed work and results. The process details leading up to the results are not included; however, the technical contact is provided for each section.

  18. Ohio Advanced Energy Manufacturing Center

    SciTech Connect (OSTI)

    Kimberly Gibson; Mark Norfolk

    2012-07-30T23:59:59.000Z

    The program goal of the Ohio Advanced Energy Manufacturing Center (OAEMC) is to support advanced energy manufacturing and to create responsive manufacturing clusters that will support the production of advanced energy and energy-efficient products to help ensure the nation's energy and environmental security. This goal cuts across a number of existing industry segments critical to the nation's future. Many of the advanced energy businesses are starting to make the transition from technology development to commercial production. Historically, this transition from laboratory prototypes through initial production for early adopters to full production for mass markets has taken several years. Developing and implementing manufacturing technology to enable production at a price point the market will accept is a key step. Since these start-up operations are configured to advance the technology readiness of the core energy technology, they have neither the expertise nor the resources to address manufacturing readiness issues they encounter as the technology advances toward market entry. Given the economic realities of today's business environment, finding ways to accelerate this transition can make the difference between success and failure for a new product or business. The advanced energy industry touches a wide range of industry segments that are not accustomed to working together in complex supply chains to serve large markets such as automotive and construction. During its first three years, the Center has catalyzed the communication between companies and industry groups that serve the wide range of advanced energy markets. The Center has also found areas of common concern, and worked to help companies address these concerns on a segment or industry basis rather than having each company work to solve common problems individually. EWI worked with three industries through public-private partnerships to sew together disparate segments helping to promote overall industry health. To aid the overall advanced energy industry, EWI developed and launched an Ohio chapter of the non-profit Advanced Energy Economy. In this venture, Ohio joins with six other states including Colorado, Connecticut, Illinois, Maine, Massachusetts, New Hampshire, Rhode Island and Vermont to help promote technologies that deliver energy that is affordable, abundant and secure. In a more specific arena, EWI's advanced energy group collaborated with the EWI-run Nuclear Fabrication Consortium to promote the nuclear supply chain. Through this project EWI has helped bring the supply chain up to date for the upcoming period of construction, and assisted them in understanding the demands for the next generation of facilities now being designed. In a more targeted manner, EWI worked with 115 individual advanced energy companies that are attempting to bring new technology to market. First, these interactions helped EWI develop an awareness of issues common to companies in different advanced energy sectors. By identifying and addressing common issues, EWI helps companies bring technology to market sooner and at a lower cost. These visits also helped EWI develop a picture of industry capability. This helped EWI provide companies with contacts that can supply commercial solutions to their new product development challenges. By providing assistance in developing supply chain partnerships, EWI helped companies bring their technology to market faster and at a lower cost than they might have been able to do by themselves. Finally, at the most granular level EWI performed dedicated research and development on new manufacturing processes for advanced energy. During discussions with companies participating in advanced energy markets, several technology issues that cut across market segments were identified. To address some of these issues, three crosscutting technology development projects were initiated and completed with Center support. This included reversible welds for batteries and high temperature heat exchangers. It also included a novel advanced weld trainer that EWI

  19. 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.

  20. PNNL Radiation Detection for Nuclear Security Summer School

    SciTech Connect (OSTI)

    Runkle, Bob

    2013-07-10T23:59:59.000Z

    PNNL's Radiation Detection for Nuclear Security Summer School gives graduate and advanced graduate students an understanding of how radiation detectors are used in national security missions.

  1. E-Print Network 3.0 - alternative nuclear energy Sample Search...

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

    Powered by Explorit Topic List Advanced Search Sample search results for: alternative nuclear energy Page: << < 1 2 3 4 5 > >> 1 Preparing Non-nuclear Engineers for the Nuclear...

  2. A discrete fractional random transform

    E-Print Network [OSTI]

    Zhengjun Liu; Haifa Zhao; Shutian Liu

    2006-05-20T23:59:59.000Z

    We propose a discrete fractional random transform based on a generalization of the discrete fractional Fourier transform with an intrinsic randomness. Such discrete fractional random transform inheres excellent mathematical properties of the fractional Fourier transform along with some fantastic features of its own. As a primary application, the discrete fractional random transform has been used for image encryption and decryption.

  3. Transformer Abdullah Al-Otaibi

    E-Print Network [OSTI]

    Masoudi, Husain M.

    Transformer Abdullah Al-Otaibi ID#242374 Section#2 Abstract- this is a brief description for transformer and how it works. I. DEFINITION A transformer is a device that transfers electrical energy from of the transformer in 1831. The transformer is used by Faraday only to demonstrate the principle of electromagnetic

  4. Lorentz transformation by mimicking the Lorentz transformation

    E-Print Network [OSTI]

    Bernhard Rothenstein; Stefan Popescu

    2007-09-24T23:59:59.000Z

    We show that starting with the fact that special relativity theory is concerned with a distortion of the observed length of a moving rod, without mentioning if it is a "contraction" or "dilation", we can derive the Lorentz transformations for the spacetime coordinates of the same event. This derivation is based on expressing the length of the moving rod as a sum of components with all the lengths involved in this summation being measured by the observers of the same inertial reference frame.

  5. Nuclear Resonance Fluorescence for Nuclear Materials Assay

    E-Print Network [OSTI]

    Quiter, Brian Joseph

    2010-01-01T23:59:59.000Z

    Potential of Nuclear Resonance Fluorescence . . . . . . . .2.9.1 Nuclear ThomsonSections . . . . . . . . . . . . . . . Nuclear Resonance

  6. Utilizing Cultural Engagement to Advance Knowledge & Transform Lives

    E-Print Network [OSTI]

    ;Additional Participants · Guests invited to attend · Examples: ­ Residential College ­ International Studies Journal ­ Convention and Visitors Bureau #12;Purpose · To share information in the planning stages international audiences · To make connections that contribute to the cultural life of the campus and greater

  7. Transform, Protect and Advance - DOE's IT Modernization Strategy |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomenthe House Committee on EnergyEnergyThe sun risesThe U.S.

  8. Small Market Advanced Retrofit Transformation Program (SMART Scale) - 2014

    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 on Delicious Rank EERE:YearRound-Up from the GridwiseSite Management Guide SiteEnergy SmallAssessment Report |ofFuel

  9. Transform Analysis Using the definition of the Laplace transform, Laplace transform properties, and the integral

    E-Print Network [OSTI]

    Landers, Robert G.

    Transform Analysis QUESTION 1 Using the definition of the Laplace transform, Laplace transform properties, and the integral tables on the course website, determine the Laplace transforms of the functions - = (3) QUESTION 2 Determine the inverse Laplace transform for the functions in equations (1)­(4). ( ) 3

  10. TRANSFORMATIONS 4.1 TRANSFORMATIONS, ISOMETRIES. The term transformation has several

    E-Print Network [OSTI]

    1 Chapter 4 TRANSFORMATIONS 4.1 TRANSFORMATIONS, ISOMETRIES. The term transformation has several. On the other hand, in linear algebra courses a linear transformation maps vectors to vectors and subspaces to subspaces. When we use the term transformation in geometry, however, we have all of these interpretations

  11. Linear Transformer Ideal Transformer Consider linear and ideal transformers attached to Circuit 1 and Circuit 2.

    E-Print Network [OSTI]

    Kozick, Richard J.

    Linear Transformer Ideal Transformer I1 + V2 _ + V1 _ Consider linear and ideal transformers in linear transformer equations for :MLL ,, 21 ( ) ( ) ( ) ( ) ( ) ( ) 12212212 2 1 112 2 12 2 1 2212 2 PP Now solve the linear transformer equations for the currents: 1 212 2 22 2 1 2 1 212 2 22 12 2 2 2

  12. Transforming California's Freight Transport System

    E-Print Network [OSTI]

    California at Davis, University of

    Transforming California's Freight Transport System Policy Forum on the Role of Freight Transport Standard #12;2050 Vision- Key Conceptual Outcomes Technology Transformation Early Action Cleaner Combustion Multiple Strategies Federal Action Efficiency Gains Energy Transformation 9 #12;Further reduce localized

  13. The Quantum Mellin transform

    E-Print Network [OSTI]

    J. Twamley; G. J. Milburn

    2007-02-12T23:59:59.000Z

    We uncover a new type of unitary operation for quantum mechanics on the half-line which yields a transformation to ``Hyperbolic phase space''. We show that this new unitary change of basis from the position x on the half line to the Hyperbolic momentum $p_\\eta$, transforms the wavefunction via a Mellin transform on to the critial line $s=1/2-ip_\\eta$. We utilise this new transform to find quantum wavefunctions whose Hyperbolic momentum representation approximate a class of higher transcendental functions, and in particular, approximate the Riemann Zeta function. We finally give possible physical realisations to perform an indirect measurement of the Hyperbolic momentum of a quantum system on the half-line.

  14. Transformation inverse design

    E-Print Network [OSTI]

    Liu, David

    We present a new technique for the design of transformation-optics devices based on large-scale optimization to achieve the optimal effective isotropic dielectric materials within prescribed index bounds, which is ...

  15. Functional Mellin Transforms

    E-Print Network [OSTI]

    J. LaChapelle

    2015-01-07T23:59:59.000Z

    Functional integrals are defined in terms of locally compact topological groups and their associated Banach-valued Haar integrals. This approach generalizes the functional integral scheme of Cartier and DeWitt-Morette. The definition allows a construction of functional Mellin transforms. In turn, the functional Mellin transforms can be used to define functional traces, logarithms, and determinants. The associated functional integrals are useful tools for probing function spaces in general and $C^\\ast$-algebras in particular. Several interesting aspects are explored.

  16. Series Transmission Line Transformer

    DOE Patents [OSTI]

    Buckles, Robert A. (Livermore, CA); Booth, Rex (Livermore, CA); Yen, Boris T. (El Cerrito, CA)

    2004-06-29T23:59:59.000Z

    A series transmission line transformer is set forth which includes two or more of impedance matched sets of at least two transmissions lines such as shielded cables, connected in parallel at one end ans series at the other in a cascading fashion. The cables are wound about a magnetic core. The series transmission line transformer (STLT) which can provide for higher impedance ratios and bandwidths, which is scalable, and which is of simpler design and construction.

  17. Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 1, Plenary sessions, reactor licensing topics, NUREG-1150, risk analysis/PRA applications, innovative concepts for increased safety of advanced power reactors, severe accident modeling and analysis

    SciTech Connect (OSTI)

    Weiss, A.J. (comp.)

    1988-02-01T23:59:59.000Z

    This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 1, discusses the following: plenary sessions; reactor licensing; NUREG-1150; risk analysis; innovative concepts for increased safety of advanced power reactors; and severe accident modeling and analysis. Thirty-two reports have been cataloged separately.

  18. E-Print Network 3.0 - advanced brayton cycles Sample Search Results

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

    BY ADVANCED GAS... -temperature steam electrolysis (HTSE) supported by a supercritical CO2 ... Source: Yildiz, Bilge - Department of Nuclear Science and Engineering,...

  19. E-Print Network 3.0 - advanced modeling technology Sample Search...

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

    Pebble Bed Reactor Collection: Fission and Nuclear Technologies 9 Kompetenzzentrum fr Automobil-und Industrieelektronik Summary: of materials for these advanced semiconductor...

  20. E-Print Network 3.0 - advanced technologies based Sample Search...

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

    Bed Reactor Collection: Fission and Nuclear Technologies 18 Kompetenzzentrum fr Automobil-und Industrieelektronik Summary: of materials for these advanced semiconductor...

  1. E-Print Network 3.0 - advanced reactor research Sample Search...

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

    to build the world's most advanced nuclear fusion reactor... ) International Thermonuclear Experimental Reactor (ITER), which will be built at Cadarache, near the...

  2. E-Print Network 3.0 - advanced research reactor Sample Search...

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

    to build the world's most advanced nuclear fusion reactor... ) International Thermonuclear Experimental Reactor (ITER), which will be built at Cadarache, near the...

  3. E-Print Network 3.0 - advanced marine reactor Sample Search Results

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

    to build the world's most advanced nuclear fusion reactor... ) International Thermonuclear Experimental Reactor (ITER), which will be built at Cadarache, near the...

  4. E-Print Network 3.0 - advanced hanaro reactor Sample Search Results

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

    to build the world's most advanced nuclear fusion reactor... ) International Thermonuclear Experimental Reactor (ITER), which will be built at Cadarache, near the...

  5. E-Print Network 3.0 - advanced lwr concept Sample Search Results

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

    ENABLING SUSTAINABLE NUCLEAR POWER Summary: and NRE Design Class., "Advances in the Subcritical, Gas-Cooled Fast Transmutation Reactor Concept", Nucl... uranium energy...

  6. E-Print Network 3.0 - advanced reactor licensing Sample Search...

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

    in advanced fuel and materials, nuclear medicine... of fission power reactors, to thermonuclear fusion and plasma physics, ... Source: Entekhabi, Dara - Kavli Institute for...

  7. E-Print Network 3.0 - advanced reactors transition Sample Search...

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

    than 30 countries signed a deal on Tuesday to build the world's most advanced nuclear fusion reactor... ) International Thermonuclear Experimental Reactor (ITER), which will be...

  8. E-Print Network 3.0 - advanced integral reactor Sample Search...

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

    in advanced fuel and materials, nuclear medicine... of fission power reactors, to thermonuclear fusion and plasma physics, ... Source: Entekhabi, Dara - Kavli Institute for...

  9. E-Print Network 3.0 - advanced reactor instrumentation Sample...

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

    in advanced fuel and materials, nuclear medicine... of fission power reactors, to thermonuclear fusion and plasma physics, ... Source: Entekhabi, Dara - Kavli Institute for...

  10. Nuclear Nonproliferation

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

    Nuclear Nonproliferation As more countries embrace nuclear power as a cost-effective and clean alternative to fossil fuels, the need exists to ensure that the nuclear fuel cycle is...

  11. Nuclear Engineering Nuclear Criticality Safety

    E-Print Network [OSTI]

    Kemner, Ken

    Nuclear Engineering Nuclear Criticality Safety The Nuclear Engineering Division (NE) of Argonne National Laboratory is experienced in performing criticality safety and shielding evaluations for nuclear, and neutron spectra. The NE nuclear criticality safety (NCS) capabilities are based on a staff with decades

  12. Plant maintenance and advanced reactors issue, 2008

    SciTech Connect (OSTI)

    Agnihotri, Newal (ed.)

    2009-09-15T23:59:59.000Z

    The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: Technologies of national importance, by Tsutomu Ohkubo, Japan Atomic Energy Agency, Japan; Modeling and simulation advances brighten future nuclear power, by Hussein Khalil, Argonne National Laboratory, Energy and desalination projects, by Ratan Kumar Sinha, Bhabha Atomic Research Centre, India; A plant with simplified design, by John Higgins, GE Hitachi Nuclear Energy; A forward thinking design, by Ray Ganthner, AREVA; A passively safe design, by Ed Cummins, Westinghouse Electric Company; A market-ready design, by Ken Petrunik, Atomic Energy of Canada Limited, Canada; Generation IV Advanced Nuclear Energy Systems, by Jacques Bouchard, French Commissariat a l'Energie Atomique, France, and Ralph Bennett, Idaho National Laboratory; Innovative reactor designs, a report by IAEA, Vienna, Austria; Guidance for new vendors, by John Nakoski, U.S. Nuclear Regulatory Commission; Road map for future energy, by John Cleveland, International Atomic Energy Agency, Vienna, Austria; and, Vermont's largest source of electricity, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovation article is titled Intelligent monitoring technology, by Chris Demars, Exelon Nuclear.

  13. ADVANCED SEISMIC BASE ISOLATION METHODS FOR MODULAR REACTORS

    SciTech Connect (OSTI)

    E. Blanford; E. Keldrauk; M. Laufer; M. Mieler; J. Wei; B. Stojadinovic; P.F. Peterson

    2010-09-20T23:59:59.000Z

    Advanced technologies for structural design and construction have the potential for major impact not only on nuclear power plant construction time and cost, but also on the design process and on the safety, security and reliability of next generation of nuclear power plants. In future Generation IV (Gen IV) reactors, structural and seismic design should be much more closely integrated with the design of nuclear and industrial safety systems, physical security systems, and international safeguards systems. Overall reliability will be increased, through the use of replaceable and modular equipment, and through design to facilitate on-line monitoring, in-service inspection, maintenance, replacement, and decommissioning. Economics will also receive high design priority, through integrated engineering efforts to optimize building arrangements to minimize building heights and footprints. Finally, the licensing approach will be transformed by becoming increasingly performance based and technology neutral, using best-estimate simulation methods with uncertainty and margin quantification. In this context, two structural engineering technologies, seismic base isolation and modular steel-plate/concrete composite structural walls, are investigated. These technologies have major potential to (1) enable standardized reactor designs to be deployed across a wider range of sites, (2) reduce the impact of uncertainties related to site-specific seismic conditions, and (3) alleviate reactor equipment qualification requirements. For Gen IV reactors the potential for deliberate crashes of large aircraft must also be considered in design. This report concludes that base-isolated structures should be decoupled from the reactor external event exclusion system. As an example, a scoping analysis is performed for a rectangular, decoupled external event shell designed as a grillage. This report also reviews modular construction technology, particularly steel-plate/concrete construction using factory prefabricated structural modules, for application to external event shell and base isolated structures.

  14. Nuclear Physics

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

    Underground Research Facility in South Dakota, which will search for neutrinoless double-beta decay. Strong Los Alamos programs in nuclear data and nuclear theory supports...

  15. Nuclear Energy

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

    Nuclear Energy Idaho National Laboratory is the Department of Energy's lead nuclear energy research and development facility. Building upon its legacy responsibilities,...

  16. APPENDIX F. TRANSFORMS, COMPLEX ANALYSIS 1 Transforms, Complex

    E-Print Network [OSTI]

    Callen, James D.

    APPENDIX F. TRANSFORMS, COMPLEX ANALYSIS 1 Appendix F Transforms, Complex Analysis This appendix discusses Fourier and Laplace transforms as they are used in plasma physics and this book. Also, key properties of complex variable theory that are needed for understanding and inverting these transforms

  17. From transformation traces to transformation rules: Assisting Model Driven Engineering

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    From transformation traces to transformation rules: Assisting Model Driven Engineering approach. In this paper we are interested in semi-automatically gen- erating labelled graph (model) transformations conform to a particu- lar syntax (meta-model). Those transformations are basic operations in model driven

  18. Optical transformation from chirplet to fractional Fourier transformation kernel

    E-Print Network [OSTI]

    Hong-yi Fan; Li-yun Hu

    2009-02-11T23:59:59.000Z

    We find a new integration transformation which can convert a chirplet function to fractional Fourier transformation kernel, this new transformation is invertible and obeys Parseval theorem. Under this transformation a new relationship between a phase space function and its Weyl-Wigner quantum correspondence operator is revealed.

  19. Laplace Transforms An integral transform is an operator

    E-Print Network [OSTI]

    Ikenaga, Bruce

    9­28­1998 Laplace Transforms An integral transform is an operator F (s) = Z b a K(s; t)f(t) dt: The input to the transform is the function f(t); the output is the function F (s). (By convention, small letters denote the inputs to a transform, and the corresponding capital letters denote the corresponding

  20. Transform Coding: Past, Present, and Future Transforms are perva-

    E-Print Network [OSTI]

    Vetterli, Martin

    Transform Coding: Past, Present, and Future Transforms are perva- sive in signal process- ing) and wavelets are part of the widely used JPEG standards, transforms are at the heart of the compression engine of transforms in compression, and the flurry of activ- ity in both research and applications around signal

  1. Report on Advanced Detector Development

    SciTech Connect (OSTI)

    James K. Jewell

    2012-09-01T23:59:59.000Z

    Neutron, gamma and charged particle detection improvements are key to supporting many of the foreseen measurements and systems envisioned in the R&D programs and the future fuel cycle requirements, such as basic nuclear physics and data, modeling and simulation, reactor instrumentation, criticality safety, materials management and safeguards. This task will focus on the developmental needs of the FCR&D experimental programs, such as elastic/inelastic scattering, total cross sections and fission neutron spectra measurements, and will leverage a number of existing neutron detector development efforts and programs, such as those at LANL, PNNL, INL, and IAC as well as those at many universities, some of whom are funded under NE grants and contracts. Novel materials and fabrication processes combined with state-of-the-art electronics and computing provide new opportunities for revolutionary detector systems that will be able to meet the high precision needs of the program. This work will be closely coordinated with the Nuclear Data Crosscut. The Advanced Detector Development effort is a broadly-focused activity that supports the development of improved nuclear data measurements and improved detection of nuclear reactions and reactor conditions. This work supports the design and construction of large-scale, multiple component detectors to provide nuclear reaction data of unprecedented quality and precision. Examples include the Time Projection Chamber (TPC) and the DANCE detector at LANL. This work also supports the fabrication and end-user application of novel scintillator materials detection and monitoring.

  2. Physics high-ranking Journals (category 2) Advances in Physics

    E-Print Network [OSTI]

    Physics high-ranking Journals (category 2) Advances in Physics Annual Review of Astronomy and Astrophysics Annual Review of Nuclear and Particle Science Applied Physics Letters Astronomy & Astrophysics Astronomy and Astrophysics Review Astrophysical Journal European Physical Journal D. Atomic, Molecular

  3. advanced reactor design: Topics by E-print Network

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

    20 21 22 23 24 25 Next Page Last Page Topic Index 1 Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors University of California...

  4. advanced reactor designs: Topics by E-print Network

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

    20 21 22 23 24 25 Next Page Last Page Topic Index 1 Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors University of California...

  5. Generalization of Conformal Transformations

    E-Print Network [OSTI]

    G. I. Garas'ko

    2005-09-19T23:59:59.000Z

    Conformal transformations of a Euclidean (complex) plane have some kind of completeness (sufficiency) for the solution of many mathematical and physical-mathematical problems formulated on this plane. There is no such completeness in the case of Euclidean, pseudo-Euclidean and polynumber spaces of dimension greater than two. In the present paper we show that using the concepts of analogical geometries allows us to generalize conformal transformations not only to the case of Euclidean or pseudo-Euclidean spaces, but also to the case of Finsler spaces, analogous to the spaces of affine connectedness. Examples of such transformations in the case of complex and hypercomplex numbers H_4 are presented. In the general case such transformations form a group of transitions, the elements of which can be viewed as transitions between projective Euclidean geometries of a distinguished class fixed by the choice of metric geometry admitting affine coordinates. The correlation between functions realizing generalized conformal transformations and generalized analytical functions can appear to be productive for the solution of fundamental problems in theoretical and mathematical physics.

  6. CalHEAT Research and Market Transformation Roadmap for Medium

    E-Print Network [OSTI]

    California at Davis, University of

    - 8 Work Trucks Work Site Support Tractors - Short Haul/ Regional Class 2b/3 vans/pickup s Class 3 - 8CalHEAT Research and Market Transformation Roadmap for Medium and Heavy Duty Trucks Delivering President CALSTART #12;California Hybrid, Efficient and Advanced Truck Research Center What is Cal

  7. Development of a portable neutron coincidence counter for field measurements of nuclear materials using the advanced multiplicity capabilities of MCNPX 2.5.F and the neutron coincidence point model

    E-Print Network [OSTI]

    Thornton, Angela Lynn

    2009-05-15T23:59:59.000Z

    Neutron coincidence counting is an important passive Nondestructive Assay (NDA) technique widely used for qualitative and quantitative analysis of nuclear material in bulk samples. During the fission process, multiple neutrons are simultaneously...

  8. Development of a portable neutron coincidence counter for field measurements of nuclear materials using the advanced multiplicity capabilities of MCNPX 2.5.F and the neutron coincidence point model

    E-Print Network [OSTI]

    Thornton, Angela Lynn

    2008-10-10T23:59:59.000Z

    Neutron coincidence counting is an important passive Nondestructive Assay (NDA) technique widely used for qualitative and quantitative analysis of nuclear material in bulk samples. During the fission process, multiple neutrons are simultaneously...

  9. Nuclear Matter and Nuclear Dynamics

    E-Print Network [OSTI]

    M Colonna

    2009-02-26T23:59:59.000Z

    Highlights on the recent research activity, carried out by the Italian Community involved in the "Nuclear Matter and Nuclear Dynamics" field, will be presented.

  10. Phase Formation and Transformations in Transmutation Fuel Materials for the LIFE Engine Part I - Path Forward

    SciTech Connect (OSTI)

    Turchi, P E; Kaufman, L; Fluss, M J

    2008-11-10T23:59:59.000Z

    The current specifications of the LLNL fusion-fission hybrid proposal, namely LIFE, impose severe constraints on materials, and in particular on the nuclear fissile or fertile nuclear fuel and its immediate environment. This constitutes the focus of the present report with special emphasis on phase formation and phase transformations of the transmutation fuel and their consequences on particle and pebble thermal, chemical and mechanical integrities. We first review the work that has been done in recent years to improve materials properties under the Gen-IV project, and with in particular applications to HTGR and MSR, and also under GNEP and AFCI in the USA. Our goal is to assess the nuclear fuel options that currently exist together with their issues. Among the options, it is worth mentioning TRISO, IMF, and molten salts. The later option will not be discussed in details since an entire report is dedicated to it. Then, in a second part, with the specific LIFE specifications in mind, the various fuel options with their most critical issues are revisited with a path forward for each of them in terms of research, both experimental and theoretical. Since LIFE is applicable to very high burn-up of various fuels, distinctions will be made depending on the mission, i.e., energy production or incineration. Finally a few conclusions are drawn in terms of the specific needs for integrated materials modeling and the in depth knowledge on time-evolution thermochemistry that controls and drastically affects the performance of the nuclear materials and their immediate environment. Although LIFE demands materials that very likely have not yet been fully optimized, the challenge are not insurmountable and a well concerted experimental-modeling effort should lead to dramatic advances that should well serve other fission programs such as Gen-IV, GNEP, AFCI as well as the international fusion program, ITER.

  11. Center For Advanced Energy Studies Overview

    ScienceCinema (OSTI)

    Blackman, Harold

    2013-05-28T23:59:59.000Z

    A collaboration between Idaho National Laboratory, Boise State University, Idaho State University and the University of Idaho. Conducts research in nuclear energy, advanced materials, carbon management, bioenergy, energy policy, modeling and simulation, and energy efficiency. Educates next generation of energy workforce. Visit us at www.caesenergy.org.

  12. Panel report: nuclear physics

    SciTech Connect (OSTI)

    Carlson, Joseph A [Los Alamos National Laboratory; Hartouni, Edward P [LLNL

    2010-01-01T23:59:59.000Z

    Nuclear science is at the very heart of the NNSA program. The energy produced by nuclear processes is central to the NNSA mission, and nuclear reactions are critical in many applications, including National Ignition Facility (NIF) capsules, energy production, weapons, and in global threat reduction. Nuclear reactions are the source of energy in all these applications, and they can also be crucial in understanding and diagnosing the complex high-energy environments integral to the work of the NNSA. Nuclear processes are complex quantum many-body problems. Modeling and simulation of nuclear reactions and their role in applications, coupled tightly with experiments, have played a key role in NNSA's mission. The science input to NNSA program applications has been heavily reliant on experiment combined with extrapolations and physical models 'just good enough' to provide a starting point to extensive engineering that generated a body of empirical information. This body of information lacks the basic science underpinnings necessary to provide reliable extrapolations beyond the domain in which it was produced and for providing quantifiable error bars. Further, the ability to perform additional engineering tests is no longer possible, especially those tests that produce data in the extreme environments that uniquely characterize these applications. The end of testing has required improvements to the predictive capabilities of codes simulating the reactions and associated applications for both well known and well characterized cases as well as incompletely known cases. Developments in high performance computing, computational physics, applied mathematics and nuclear theory have combined to make spectacular advances in the theory of fission, fusion and nuclear reactions. Current research exploits these developments in a number of Office of Science and NNSA programs, and in joint programs such as the SciDAC (Science Discovery through Advanced Computing) that supports the project Building a Universal Nuclear Energy Density Fuctional whose goals are to provide the unified approach to calculating the properties of nuclei. The successful outcome of this, and similar projects is a first steps toward a predictive nuclear theory based on fundamental interactions between constituent nucleons. The application of this theory to the domain of nuclei important for national security missions will require computational resources at the extreme scale, beyond what will be available in the near term future.

  13. Fourier Transform Infrared Spectroscopy

    E-Print Network [OSTI]

    Nizkorodov, Sergey

    FTIR - 1 Fourier Transform Infrared Spectroscopy FTIR DETERMINATION OF MTBE IN GASOLINE AND ETHANOL FTIR DETERMINATION OF MTBE IN GASOLINE AND ETHANOL IN VODKA AND MOUTHWASH INTRODUCTION As a part has contained MTBE (methyl tert­butyl ether) as its primary oxygenate. However, there has been

  14. Research Councils UK Transforming

    E-Print Network [OSTI]

    Berzins, M.

    research is helping to accelerate the use of green energy technologies. RCUK has played a key role to help combat climate change, accelerate the deployment of green energy technologies and create newResearch Councils UK Transforming our energy future #12;Research funded by the Research Councils

  15. TO TRANSFORM BIOMEDICAL ENGINEERING

    E-Print Network [OSTI]

    IT'S TIME TO TRANSFORM BIOMEDICAL ENGINEERING EDUCATION #12;Charles H. & Bettye Barclay Professor Head, Department of Biomedical Engineering Texas A&M University We're dedicated to solving the world in biomedical engineering research and education ­ and we're well on our way. Our faculty continues to engineer

  16. Science Drivers and Technical Challenges for Advanced Magnetic Resonance

    SciTech Connect (OSTI)

    Mueller, Karl T.; Pruski, Marek; Washton, Nancy M.; Lipton, Andrew S.

    2013-03-07T23:59:59.000Z

    This report recaps the "Science Drivers and Technical Challenges for Advanced Magnetic Resonance" workshop, held in late 2011. This exploratory workshop's goal was to discuss and address challenges for the next generation of magnetic resonance experimentation. During the workshop, participants from throughout the world outlined the science drivers and instrumentation demands for high-field dynamic nuclear polarization (DNP) and associated magnetic resonance techniques, discussed barriers to their advancement, and deliberated the path forward for significant and impactful advances in the field.

  17. Sandia National Laboratories: advanced controls

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1development Sandia, NREL Release Wave EnergyLinksZparts of thecontrols Advanced

  18. Sandia National Laboratories: Past Market Transformation Activities

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -theErik Spoerke SSLSMolten-SaltReliabilityIntroduction of Prof.TransformationPast

  19. Sandia National Laboratories: Solar Market Transformation

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -theErikGroundbreaking WorkTransformationSitingMolten Salt TestGlare

  20. Linear Transformations, Canonoid Transformations and BiHamiltonian Structures

    E-Print Network [OSTI]

    Giovanni Rastelli; Manuele Santoprete

    2014-07-19T23:59:59.000Z

    We give a characterization of linear canonoid transformations on symplectic manifolds and we use it to generate biHamiltonian structures for some mechanical systems. Utilizing this characterization we also study the behavior of quadratic superintegrable systems under canonoid transformations. We present a description of canonoid transformations due to E.T. Whittaker, and we show that it leads, in a natural way, to the modern, coordinate-independent definition of canonoid transformations. We also generalize canonoid transformations to Poisson manifolds by introducing Poissonoid transformations. We give examples of such transformations for Euler's equations of the rigid body (on $ \\mathfrak{ so}^\\ast (3) $ and $ \\mathfrak{ so}^\\ast (4)$) and for an integrable case of Kirchhoff's equations for the motion of a rigid body immersed in an ideal fluid. We study the relationship between biHamiltonian structures and Poissonoid transformations for these examples.

  1. ENTERPRISE SRS: LEVERAGING ONGOING OPERATIONS TO ADVANCE RADIOACTIVE WASTE MANAGEMENT TECHNOLOGIES

    SciTech Connect (OSTI)

    Murray, A.; Wilmarth, B.; Marra, J.; Mcguire, P.; Wheeler, V.

    2013-05-16T23:59:59.000Z

    The Savannah River Site (SRS) is repurposing its vast array of assets to solve future national issues regarding environmental stewardship, national security, and clean energy. The vehicle for this transformation is Enterprise SRS which presents a new, strategic view of SRS as a united endeavor for “all things nuclear” as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into facilities in conjunction with ongoing missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, The DOE Savannah River Operations Office, Savannah River Nuclear Solutions, and the Savannah River National Laboratory (SRNL) have established a center for applied nuclear materials processing and engineering research (hereafter referred to as the Center). The key objective of this initiative is to bridge the gap between promising transformational nuclear materials management advancements and large-scale deployment of the technology by using SRS assets (e.g. facilities, staff, and property) for those critical engineering-scale demonstrations necessary to assure the successful deployment of new technologies. The Center will coordinate the demonstration of R&D technologies and serve as the interface between the engineering-scale demonstration and the R&D programs, essentially providing cradle-to-grave support to the R&D team during the demonstration. While the initial focus of the Center will be on the effective use of SRS assets for these demonstrations, the Center also will work with research teams to identify opportunities to perform R&D demonstrations at other facilities. Unique to this approach is the fact that these SRS assets will continue to accomplish DOE’s critical nuclear material missions (e.g., processing in H-Canyon and plutonium storage in K-Area). These demonstrations can be accomplished in a more cost-effective manner through the use of existing facilities in conjunction with ongoing missions. Essentially, the R&D program would not need to pay the full operational cost of a facility, just the incremental cost of performing the demonstration. Current Center activities have been focused on integrating advanced safeguards monitoring technology demonstrations into the SRS H-Canyon and advanced location technology demonstrations into K-Area Materials Storage. These demonstrations are providing valuable information to researchers and program owners. In addition these demonstrations are providing the Center with an improved protocol for demonstration management that can be exercised across the entire SRS (and to offsite venues) to ensure that future demonstrations are done efficiently and provide an opportunity to use these unique assets for multiple purposes involving national laboratories, academia, and commercial entities. Key among the envisioned future use of SRS assets is the demonstration of new radioactive waste management technologies critical for advancing the mission needs of the DOE-EM program offices in their efforts to cleanup 107 sites across the United States. Of particular interest is the demonstration of separations technologies in H-Canyon. Given the modular design of H-Canyon, those demonstrations would be accomplished using a process frame. The demonstration equipment would be installed on the process frame and that frame would then be positioned into an H-Canyon cell so that the demonstration is performed in a radiological environment involving prototypic nuclear materials.

  2. EIS-0236-S4: Final Complex Transformation Supplemental Programmatic Environmental Impact Statement

    Broader source: Energy.gov [DOE]

    This Complex Transformation Supplemental Programmatic Environmental Impact Statement (SPEIS) analyzes the potential environmental impacts of reasonable alternatives to continue transformation of the nuclear weapons complex to be smaller, and more responsive, efficient, and secure in order to meet national security requirements.

  3. Liquid Metal Transformers

    E-Print Network [OSTI]

    Sheng, Lei; Liu, Jing

    2014-01-01T23:59:59.000Z

    The room temperature liquid metal is quickly emerging as an important functional material in a variety of areas like chip cooling, 3D printing or printed electronics etc. With diverse capabilities in electrical, thermal and flowing behaviors, such fluid owns many intriguing properties that had never been anticipated before. Here, we show a group of unconventional phenomena occurring on the liquid metal objects. Through applying electrical field on the liquid metals immersed in water, a series of complex transformation behaviors such as self-assembling of a sheet of liquid metal film into a single sphere, quick mergences of separate metal droplets, controlled self-rotation and planar locomotion of liquid metal objects can be realized. Meanwhile, it was also found that two accompanying water vortexes were induced and reliably swirled near the rotating liquid metal sphere. Further, effects of the shape, size, voltage, orientation and geometries of the electrodes to control the liquid metal transformers were clar...

  4. Transformations of polynomial ensembles

    E-Print Network [OSTI]

    Arno B. J. Kuijlaars

    2015-01-30T23:59:59.000Z

    A polynomial ensemble is a probability density function for the position of $n$ real particles of the form $\\frac{1}{Z_n} \\, \\prod_{jtransformations that preserve the structure of a polynomial ensemble. These transformations include the restriction of a Hermitian matrix by removing one row and one column, a rank-one modification of a Hermitian matrix, and the extension of a Hermitian matrix by adding an extra row and column with complex Gaussians.

  5. Sandia National Laboratories: Advanced Research Projects Agency-Energy

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0Energy Advanced Nuclear Energy The Advanced NuclearResearch

  6. Transformative Wave Technologies Kent, Washington

    E-Print Network [OSTI]

    California at Davis, University of

    Transformative Wave Technologies Kent, Washington www.transformativewave.com #12;#12;North America are shifted to off peak times #12;#12;Transformative Wave Technologies www.transformativewave.com #12

  7. Transforming Parks and Protected Areas

    E-Print Network [OSTI]

    Bolch, Tobias

    Transforming Parks and Protected Areas Policy and governance in a changing world Edited by Kevin S from the British Library Library of Congress Cataloging In Publication Data Transforming parks

  8. Nonlocal conservation laws and related Bäcklund transformations via reciprocal transformations

    E-Print Network [OSTI]

    Sen-Yue Lou

    2014-06-08T23:59:59.000Z

    A set of infinitely many nonlocal conservation laws are revealed for (1+1)-dimensional evolution equations. For some special known integrable systems, say, the KdV and Dym equations, it is found that different nonlocal conservation laws can lead to same new integrable systems via reciprocal transformation. On the other hand, it can be considered as one solution of the new model obtained via reciprocal transformation(s) can be changed to different solutions of the original model. The fact indicates also that two or more different (local and nonlocal) conservation laws can be used to find implicit auto-B\\"acklund transformations via reciprocal transformation to other systems.

  9. Metal fire implications for advanced reactors. Part 1, literature review.

    SciTech Connect (OSTI)

    Nowlen, Steven Patrick; Radel, Ross F.; Hewson, John C.; Olivier, Tara Jean; Blanchat, Thomas K.

    2007-10-01T23:59:59.000Z

    Public safety and acceptance is extremely important for the nuclear power renaissance to get started. The Advanced Burner Reactor and other potential designs utilize liquid sodium as a primary coolant which provides distinct challenges to the nuclear power industry. Fire is a dominant contributor to total nuclear plant risk events for current generation nuclear power plants. Utilizing past experience to develop suitable safety systems and procedures will minimize the chance of sodium leaks and the associated consequences in the next generation. An advanced understanding of metal fire behavior in regards to the new designs will benefit both science and industry. This report presents an extensive literature review that captures past experiences, new advanced reactor designs, and the current state-of-knowledge related to liquid sodium combustion behavior.

  10. Generalized Transforms and Special Functions

    E-Print Network [OSTI]

    G. Dattoli; E. Sabia

    2010-10-08T23:59:59.000Z

    We study the properties of different type of transforms by means of operational methods and discuss the relevant interplay with many families of special functions. We consider in particular the binomial transform and its generalizations. A general method, based on the use of the Fourier transform technique, is proposed for the study of the properties of functions of operators.

  11. VLA Antenna Pad Transformer Breaker

    E-Print Network [OSTI]

    Groppi, Christopher

    NRAO VLA Antenna Pad Transformer Breaker Survey B-Array, November 22nd , 2013 Summary: None connections in the cabinet and may be indicating a problem inside the transformer. If the heating on these bushings continues the transformer may need service. NOTE: The low ambient temperature and good conductance

  12. VLA Antenna Pad Transformer Breaker

    E-Print Network [OSTI]

    Groppi, Christopher

    NRAO VLA Antenna Pad Transformer Breaker Survey D-Array, April 5th 2013 #12;VLA Antenna Pad Transformer Breaker Survey D-Array, April 2013, Bob Broilo 2 Summary: No action needed. Inspected by: Bob2 Visible Light Image Notes: #12;VLA Antenna Pad Transformer Breaker Survey D-Array, April 2013, Bob

  13. VLA Antenna Pad Transformer Breaker

    E-Print Network [OSTI]

    Groppi, Christopher

    NRAO VLA Antenna Pad Transformer Breaker Survey A-Array, July 2011, Bob Broilo #12;A-Array Antenna Pad Transformer Survey July 2011, Bob Broilo 2 Inspected by: Bob Broilo Inspection Date: 6/16/2011 2 Transformer Survey July 2011, Bob Broilo 3 Inspected by: Bob Broilo Inspection Date: 6/16/2011 1:58:06 PM

  14. VLA Antenna Pad Transformer Breaker

    E-Print Network [OSTI]

    Groppi, Christopher

    NRAO VLA Antenna Pad Transformer Breaker Survey C-Array, August 20th 2013 #12;VLA Antenna Pad Transformer Breaker Survey C-Array, August 2013, Bob Broilo 2 Summary: Breaker at CE7 needs to be replaced transformer can be shut down with the switch at DE9. Inspected by: Bob Broilo Inspection Date: 8/16/2013 2

  15. VLA Antenna Pad Transformer Breaker

    E-Print Network [OSTI]

    Groppi, Christopher

    NRAO VLA Antenna Pad Transformer Breaker Survey D-Array, October 2011, Bob Broilo #12;D-Array Antenna Pad Transformer Survey October 2011, Bob Broilo 2 Inspected by: Bob Broilo Inspection Date: 10-hand) feeds DE2. #12;D-Array Antenna Pad Transformer Survey October 2011, Bob Broilo 3 Inspected by: Bob

  16. The Transformer By Aaron Lo

    E-Print Network [OSTI]

    Treuille, Adrien

    (3) Transforming lambda-expressions with several patterns n pat 1 : : : pat n -> exp n pat 1 -> (n pat 2 -> : : : (n pat n -> exp) : : :) where n #21; 2 (4) Transforming lambda-patterns into case n pat -> exp n var -> case var of pat -> exp where pat is no variable, var is new (5) Transforming case

  17. VLA Antenna Pad Transformer Breaker

    E-Print Network [OSTI]

    Groppi, Christopher

    NRAO VLA Antenna Pad Transformer Breaker Survey C-Array, April 2012, Bob Broilo #12;C-Array Antenna Pad Transformer Survey April 2012, Bob Broilo 2 Inspected by: Bob Broilo Inspection Date: 4/4/2012 2 Pad Transformer Survey April 2012, Bob Broilo 3 Inspected by: Bob Broilo Inspection Date: 4/4/2012 2

  18. VLA Antenna Pad Transformer Breaker

    E-Print Network [OSTI]

    Groppi, Christopher

    NRAO VLA Antenna Pad Transformer Breaker Survey A-Array, May 20, 2014 Summary: The breakers at AN5 Transformer Breaker Survey A-Array, May 2014, Bob Broilo 2 Inspected by: Bob Broilo Inspection Date: 5 Notes: #12;VLA Antenna Pad Transformer Breaker Survey A-Array, May 2014, Bob Broilo 3 Inspected by: Bob

  19. TRANSFORMING MEDICINE October 1, 2009

    E-Print Network [OSTI]

    Valero-Cuevas, Francisco

    TRANSFORMING MEDICINE October 1, 2009 Strategic Plan #12;ABOUT THE KECK SCHOOL OF MEDICINE OF USC Century for the benefit of humankind. This is an exciting time of great transformation as we endeavor of Medicine is undergoing a major transformation. It was sparked by the expansion of biomedical research

  20. VLA Antenna Pad Transformer Breaker

    E-Print Network [OSTI]

    Groppi, Christopher

    NRAO VLA Antenna Pad Transformer Breaker Survey B-Array, May 2011, Bob Broilo #12;B-array Antenna Pad Transformer Breaker Survey May 2011, Bob Broilo 2 Inspected by: Bob Broilo Inspection Date: 5 Transformer Breaker Survey May 2011, Bob Broilo 3 Inspected by: Bob Broilo Inspection Date: 5/5/2011 3

  1. ADVANCED TURBINE SYSTEMS PROGRAM

    SciTech Connect (OSTI)

    Sy Ali

    2002-03-01T23:59:59.000Z

    The market for power generation equipment is undergoing a tremendous transformation. The traditional electric utility industry is restructuring, promising new opportunities and challenges for all facilities to meet their demands for electric and thermal energy. Now more than ever, facilities have a host of options to choose from, including new distributed generation (DG) technologies that are entering the market as well as existing DG options that are improving in cost and performance. The market is beginning to recognize that some of these users have needs beyond traditional grid-based power. Together, these changes are motivating commercial and industrial facilities to re-evaluate their current mix of energy services. One of the emerging generating options is a new breed of advanced fuel cells. While there are a variety of fuel cell technologies being developed, the solid oxide fuel cells (SOFC) and molten carbonate fuel cells (MCFC) are especially promising, with their electric efficiency expected around 50-60 percent and their ability to generate either hot water or high quality steam. In addition, they both have the attractive characteristics of all fuel cells--relatively small siting footprint, rapid response to changing loads, very low emissions, quiet operation, and an inherently modular design lending itself to capacity expansion at predictable unit cost with reasonably short lead times. The objectives of this project are to:(1) Estimate the market potential for high efficiency fuel cell hybrids in the U.S.;(2) Segment market size by commercial, industrial, and other key markets;(3) Identify and evaluate potential early adopters; and(4) Develop results that will help prioritize and target future R&D investments. The study focuses on high efficiency MCFC- and SOFC-based hybrids and competing systems such as gas turbines, reciprocating engines, fuel cells and traditional grid service. Specific regions in the country have been identified where these technologies and the corresponding early adopters are likely to be located.

  2. Master's programme in Nuclear Energy Engineering Programme outline

    E-Print Network [OSTI]

    Haviland, David

    Master's programme in Nuclear Energy Engineering Programme outline The two-year Master's programme to work abroad. career ProsPects Nuclear power is a significant part of the current energy balance.With advances in science and technology, nuclear energy is increasingly re- garded as an eminent part

  3. Getting to Know Nuclear Energy: The Past, Present & Future

    E-Print Network [OSTI]

    Kemner, Ken

    Getting to Know Nuclear Energy: The Past, Present & Future Argonne National Laboratory was founded on the peaceful uses of nuclear energy and has pioneered many of the technologies in use today. Argonne's Roger Blomquist will discuss the history of nuclear energy, advanced reactor designs and future technologies, all

  4. Nuclear Engineer (Nuclear Safety Specialist)

    Broader source: Energy.gov [DOE]

    A successful candidate of this position will serve as a Nuclear Engineer (Nuclear Safety Specialist) responsible for day-to-day technical monitoring, and evaluation of aspects of authorization...

  5. Advanced Critical Advanced Energy Retrofit Education and Training...

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

    Critical Advanced Energy Retrofit Education and Training and Credentialing - 2014 BTO Peer Review Advanced Critical Advanced Energy Retrofit Education and Training and...

  6. Nuclear Safety

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

    and Management Services Department at INL involves providing advanced risk and reliability analytical capabilities to support complex engineered facilities and processes. The...

  7. Transforming Commercial Building Operations

    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 on Delicious RankCombustion |Energy Usage »of EnergyThe EnergyDepartment7 th ,TopDepartmentPlanarWorkshopTransforming

  8. Transformations | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revisionEnvReviewNonInvasiveExplorationUT-gTaguspark JumpDetective:Toyo Aluminium KK JumpMyTransformations Jump

  9. Sandia National Laboratories: Advanced Materials Laboratory

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwardsSafeguardsEngineersSandia/NewAdvancedAdvanced

  10. Applying Improved Efficiency Transformers

    E-Print Network [OSTI]

    Haggerty, N. K.; Malone, T. P.

    Wh Energy LblMWH Coal 1576 56.3 18.3 Natural Gas 264 9.4 0.0 Petroleum 89 3.2 11.9 Nuclear 619 22.1 Hydro 240 8.6 Geothermal 10 0.4 Avg. NOx Avg. CO 2 Emission Emission LblMWH LblMWH 9.0 2063 4.7 1206 3.8 1569 Avg. S02 Avg. NOx Avg. CO 2...

  11. Italian Academy Advanced Studies

    E-Print Network [OSTI]

    Qian, Ning

    The Italian Academy for Advanced Studies in America at Columbia University Annual Report 2006­2007 The Italian Academy for Advanced Studies in America at Columbia University Annual Report 2006­2007 #12;italian academy for advanced studies in america 1161 Amsterdam Avenue New York, NY 10027 tel: (212) 854-2306 fax

  12. Advanced Search Search Tips

    E-Print Network [OSTI]

    Kinosita Jr., Kazuhiko

    Advanced Search Search Tips Advanced Search Search Tips springerlink.com SpringerLink 2,000 40,000 20,000 2010 11 Please visit 7 http://www.springerlink.com GO 1997 1997 SpringerLink Advanced Search Search Tips CONTENT DOI CITATION DOI ISSN ISBN CATEGORY AND DATE LIMITERS Journals Books Protocols

  13. Fundamental Thermal Fluid Physics of High Temperature Flows in Advanced Reactor Systems - Nuclear Energy Research Initiative Program Interoffice Work Order (IWO) MSF99-0254 Final Report for Period 1 August 1999 to 31 December 2002

    SciTech Connect (OSTI)

    McEligot, D.M.; Condie, K.G.; Foust, T.D.; McCreery, G.E.; Pink, R.J.; Stacey, D.E. (INEEL); Shenoy, A.; Baccaglini, G. (General Atomics); Pletcher, R.H. (Iowa State U.); Wallace, J.M.; Vukoslavcevic, P. (U. Maryland); Jackson, J.D. (U. Manchester, UK); Kunugi, T. (Kyoto U., Japan); Satake, S.-i. (Tokyo U. Science, Japan)

    2002-12-31T23:59:59.000Z

    The ultimate goal of the study is the improvement of predictive methods for safety analyses and design of advanced reactors for higher efficiency and enhanced safety and for deployable reactors for electrical power generation, process heat utilization and hydrogen generation. While key applications would be advanced gas-cooled reactors (AGCRs) using the closed Brayton cycle (CBC) for higher efficiency (such as the proposed Gas Turbine - Modular Helium Reactor (GT-MHR) of General Atomics [Neylan and Simon, 1996]), results of the proposed research should also be valuable in reactor systems with supercritical flow or superheated vapors, e.g., steam. Higher efficiency leads to lower cost/kwh and reduces life-cycle impacts of radioactive waste (by reducing waters/kwh). The outcome will also be useful for some space power and propulsion concepts and for some fusion reactor concepts as side benefits, but they are not the thrusts of the investigation. The objective of the project is to provide fundamental thermal fluid physics knowledge and measurements necessary for the development of the improved methods for the applications.

  14. Liquid Metal Transformers

    E-Print Network [OSTI]

    Lei Sheng; Jie Zhang; Jing Liu

    2014-01-30T23:59:59.000Z

    The room temperature liquid metal is quickly emerging as an important functional material in a variety of areas like chip cooling, 3D printing or printed electronics etc. With diverse capabilities in electrical, thermal and flowing behaviors, such fluid owns many intriguing properties that had never been anticipated before. Here, we show a group of unconventional phenomena occurring on the liquid metal objects. Through applying electrical field on the liquid metals immersed in water, a series of complex transformation behaviors such as self-assembling of a sheet of liquid metal film into a single sphere, quick mergences of separate metal droplets, controlled self-rotation and planar locomotion of liquid metal objects can be realized. Meanwhile, it was also found that two accompanying water vortexes were induced and reliably swirled near the rotating liquid metal sphere. Further, effects of the shape, size, voltage, orientation and geometries of the electrodes to control the liquid metal transformers were clarified. Such events are hard to achieve otherwise on rigid metal or conventional liquid spheres. This finding has both fundamental and practical significances which suggest a generalized way of making smart soft machine, collecting discrete metal fluids, as well as flexibly manipulating liquid metal objects including accompanying devices.

  15. Sandia National Laboratories: Advanced Simulation and Computing:

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0Energy Advanced Nuclear Energy The

  16. LU transformation invariant operators and LU transformation invariant

    E-Print Network [OSTI]

    Xin-wei Zha; Chun-min Zhang

    2007-02-06T23:59:59.000Z

    We proposed a concept of LU transformation invariant operators. By using this operator, arbitrary multi-qubit states LU transformation invariant and SLOCC invariant could be easily obtained. And we find that presences two kinds of invariant operators and corresponding invariants. One kind of operators yields LU invariants and the other operators results in SLOCC invariants. For three-qubit states, all independence LU transformation invariant are obtained. Furthermore, by this system method, arbitrary multi-qubit states invariants can be given.

  17. Design of Radiation-Tolerant Structural Alloys for Generation IV Nuclear Energy Systems

    SciTech Connect (OSTI)

    Todd R. Allen

    2009-06-30T23:59:59.000Z

    This project will use proton irradiation to further understand the microstructural stability of ceramics being considered as matrix material for advanced nuclear fuels.

  18. Novel Fabrication of SiC Based Ceramics for Nuclear Applications.

    E-Print Network [OSTI]

    Singh, Abhishek Kumar

    2009-01-01T23:59:59.000Z

    ??Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures… (more)

  19. A framework for nuclear facility safeguard evaluation using probabilistic methods and expert elicitation

    E-Print Network [OSTI]

    Iamsumang, Chonlagarn

    2010-01-01T23:59:59.000Z

    With the advancement of the next generation of nuclear fuel cycle facilities, concerns of the effectiveness of nuclear facility safeguards have been increasing due to the inclusion of highly enriched material and reprocessing ...

  20. Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report

    Broader source: Energy.gov [DOE]

    The development of advanced nuclear energy systems in the U.S. will depend greatly on the continued success of currently operating light water nuclear power plants and the ordering of new...

  1. E-Print Network 3.0 - acordo nuclear brasil-alemanha Sample Search...

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

    acordo nuclear brasil-alemanha Search Powered by Explorit Topic List Advanced Search Sample search results for: acordo nuclear brasil-alemanha Page: << < 1 2 3 4 5 > >> 1 Portugal...

  2. Nuclear Counterterrorism

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2013-08-26T23:59:59.000Z

    The Order defines requirements for the protection of sensitive improvised nuclear device information and provides a framework to support DOE activities related to nuclear counterterrorism. (A supplemental DOE Manual, Control of and Access to Improvised Nuclear Device Information, provides requirements and procedures for protecting Sigma 20 information.) Appendices A and B are Official Use Only. Point of contact is Adam Boyd (NA-82), 202-586-0010. Cancels DOE O 457.1 and DOE M 457.1-1.

  3. Instrumentation to Enhance Advanced Test Reactor Irradiations

    SciTech Connect (OSTI)

    J. L. Rempe; D. L. Knudson; K. G. Condie; J. E. Daw; S. C. Taylor

    2009-09-01T23:59:59.000Z

    The Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007 to support U.S. leadership in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR will support basic and applied nuclear research and development, further advancing the nation's energy security needs. A key component of the ATR NSUF effort is to prove new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. To address this need, an assessment of instrumentation available and under-development at other test reactors has been completed. Based on this review, recommendations are made with respect to what instrumentation is needed at the ATR and a strategy has been developed for obtaining these sensors. Progress toward implementing this strategy is reported in this document. It is anticipated that this report will be updated on an annual basis.

  4. LIFE Materials: Phase Formation and Transformations in Transmutation Fuel Materials for the LIFE Engine Part I - Path Forward Volume 3

    SciTech Connect (OSTI)

    Turchi, P A; Kaufman, L; Fluss, M

    2008-12-19T23:59:59.000Z

    The current specifications of the LLNL fusion-fission hybrid proposal, namely LIFE, impose severe constraints on materials, and in particular on the nuclear fissile or fertile nuclear fuel and its immediate environment. This constitutes the focus of the present report with special emphasis on phase formation and phase transformations of the transmutation fuel and their consequences on particle and pebble thermal, chemical, and mechanical integrities. We first review the work that has been done in recent years to improve materials properties under the Gen-IV project, and with in particular applications to HTGR and MSR, and also under GNEP and AFCI in the USA. Our goal is to assess the nuclear fuel options that currently exist together with their issues. Among the options, it is worth mentioning TRISO, IMF, and molten salts. The later option will not be discussed in details since an entire report (Volume 8 - Molten-salt Fuels) is dedicated to it. Then, in a second part, with the specific LIFE specifications in mind, the various fuel options with their most critical issues are revisited with a path forward for each of them in terms of research, both experimental and theoretical. Since LIFE is applicable to very high burn-up of various fuels, distinctions will be made depending on the mission, i.e., energy production or incineration. Finally a few conclusions are drawn in terms of the specific needs for integrated materials modeling and the in depth knowledge on time-evolution thermo-chemistry that controls and drastically affects the performance of the nuclear materials and their immediate environment. Although LIFE demands materials that very likely have not yet been fully optimized, the challenges are not insurmountable, and a well concerted experimental-modeling effort should lead to dramatic advances that should well serve other fission programs such as Gen-IV, GNEP, AFCI as well as the international fusion program, ITER.

  5. nuclear controls

    National Nuclear Security Administration (NNSA)

    the Office of Nonproliferation and International Security (NIS) is to prevent the proliferation of nuclear weapons, materials, technology, and expertise. NIS applies technical...

  6. z Transform Chapter Intended Learning Outcomes

    E-Print Network [OSTI]

    So, Hing-Cheung

    z Transform Chapter Intended Learning Outcomes: (i) Understanding the relationship between transform and the Fourier transform for discrete-time signals (ii) Understanding the characteristics and properties of transform (iii) Ability to compute transform and inverse transform (iv) Ability to apply

  7. Advanced Reactors Transition Program Resource Loaded Schedule

    SciTech Connect (OSTI)

    BOWEN, W.W.

    1999-11-08T23:59:59.000Z

    The Advanced Reactors Transition (ART) Resource Loaded Schedule (RLS) provides a cost and schedule baseline for managing the project elements within the ART Program. The Fast Flux Test Facility (FFTF) activities are delineated through the end of FY 2000, assuming continued standby. The Nuclear Energy (NE) Legacies and Plutonium Recycle Test Reactor (PRTR) activities are delineated through the end of the deactivation process. This document reflects the 1 Oct 1999 baseline.

  8. Advanced Reactor Technologies | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energy UsageAUDITVehiclesTankless orA BRIEF HISTORY OFEnergyAdvancedNuclear Reactor

  9. Advanced Sensors and Instrumentation | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energy UsageAUDITVehiclesTankless orA BRIEF HISTORY OFEnergyAdvancedNuclear

  10. Particle Detector / Beam Current Transformer

    E-Print Network [OSTI]

    McDonald, Kirk

    Particle Detector / Beam Current Transformer Analysis December 8, 2009 Harold G. Kirk #12;ShotSignal,A.U. Proton Bunch Number Beam Current Transformer - 17011 0 2 4 6 8 0 2 4 6 8 10 12 14 16 18 20 Integrated Transformer Pump 187829 (au) Probe 196504 (au) Ratios: Beam Current 1.046 SF 1.019 2.9% difference #12;Shot

  11. Future Transient Testing of Advanced Fuels

    SciTech Connect (OSTI)

    Jon Carmack

    2009-09-01T23:59:59.000Z

    The transient in-reactor fuels testing workshop was held on May 4–5, 2009 at Idaho National Laboratory. The purpose of this meeting was to provide a forum where technical experts in transient testing of nuclear fuels could meet directly with technical instrumentation experts and nuclear fuel modeling and simulation experts to discuss needed advancements in transient testing to support a basic understanding of nuclear fuel behavior under off-normal conditions. The workshop was attended by representatives from Commissariat à l'Énergie Atomique CEA, Japanese Atomic Energy Agency (JAEA), Department of Energy (DOE), AREVA, General Electric – Global Nuclear Fuels (GE-GNF), Westinghouse, Electric Power Research Institute (EPRI), universities, and several DOE national laboratories. Transient testing of fuels and materials generates information required for advanced fuels in future nuclear power plants. Future nuclear power plants will rely heavily on advanced computer modeling and simulation that describes fuel behavior under off-normal conditions. TREAT is an ideal facility for this testing because of its flexibility, proven operation and material condition. The opportunity exists to develop advanced instrumentation and data collection that can support modeling and simulation needs much better than was possible in the past. In order to take advantage of these opportunities, test programs must be carefully designed to yield basic information to support modeling before conducting integral performance tests. An early start of TREAT and operation at low power would provide significant dividends in training, development of instrumentation, and checkout of reactor systems. Early start of TREAT (2015) is needed to support the requirements of potential users of TREAT and include the testing of full length fuel irradiated in the FFTF reactor. The capabilities provided by TREAT are needed for the development of nuclear power and the following benefits will be realized by the refurbishment and restart of TREAT. •TREAT is an absolute necessity in the suite of reactor fuel test capabilities •TREAT yields valuable information on reactivity effects, margins to failure, fuel dispersal, and failure propagation •Most importantly, interpretation of TREAT experiment results is a stringent test of the integrated understanding of fuel performance.

  12. Developing Tutorials for Advanced Physics Students: Processes and Lessons Learned

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    Developing Tutorials for Advanced Physics Students: Processes and Lessons Learned Charles Baily electrodynamics, active learning, course transformation. PACS: 01.40.Fk, 01.40.gb INTRODUCTION A common theme in physics education research (PER) is that students will learn more when they are active participants

  13. Advanced Calculus 2 1. The derivative: Let Rm

    E-Print Network [OSTI]

    Logan, David

    , . . . , m). (9) We assume the transformation (9) to be invertible, that is, we can for the xj as functionsAdvanced Calculus 2 1. The derivative: Let Rm have components j and x: Rm Rn by x() = x1 matrix. You can think of A as a linear function taking Rm to Rm . We denote by AB the image of B under A

  14. Advanced Fuels Campaign FY 2011 Accomplishments Report

    SciTech Connect (OSTI)

    Not Listed

    2011-11-01T23:59:59.000Z

    One of the major research and development (R&D) areas under the Fuel Cycle Research and Development (FCRD) program is advanced fuels development. The Advanced Fuels Campaign (AFC) has the responsibility to develop advanced fuel technologies for the Department of Energy (DOE) using a science-based approach focusing on developing a microstructural understanding of nuclear fuels and materials. Accomplishments made during fiscal year (FY 20) 2011 are highlighted in this report, which focuses on completed work and results. The process details leading up to the results are not included; however, the technical contact is provided for each section. The order of the accomplishments in this report is consistent with the AFC work breakdown structure (WBS).

  15. Power transformers - Part 11: Dry-type transformers

    E-Print Network [OSTI]

    International Electrotechnical Commission. Geneva

    2004-01-01T23:59:59.000Z

    Applies to dry-type power transformers (including auto-transformers) having values of highest voltage for equipment up to and including 36 kV and at least one winding operating at greater than 1,1 kV. Applies to all construction technologies.

  16. PROBING DENSE NUCLEAR MATTER VIA NUCLEAR COLLISIONS

    E-Print Network [OSTI]

    Stocker, H.

    2012-01-01T23:59:59.000Z

    University of California. LBL-12095 Probing Dense NuclearMatter Nuclear Collisions* v~a H. Stocker, M.Gyulassy and J. Boguta Nuclear Science Division Lawrence

  17. Nuclear Facilities | Department of Energy

    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 on Delicious Rank EERE:Year in3.pdfEnergyDepartment of Energy Advanced1, 2014Nuclear Facilities Nuclear Facilities

  18. Nuclear Liability | Department of Energy

    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 on Delicious Rank EERE:Year in3.pdfEnergyDepartment of Energy Advanced1, 2014Nuclear FacilitiesNuclear

  19. Advanced gray rod control assembly

    DOE Patents [OSTI]

    Drudy, Keith J; Carlson, William R; Conner, Michael E; Goldenfield, Mark; Hone, Michael J; Long, Jr., Carroll J; Parkinson, Jerod; Pomirleanu, Radu O

    2013-09-17T23:59:59.000Z

    An advanced gray rod control assembly (GRCA) for a nuclear reactor. The GRCA provides controlled insertion of gray rod assemblies into the reactor, thereby controlling the rate of power produced by the reactor and providing reactivity control at full power. Each gray rod assembly includes an elongated tubular member, a primary neutron-absorber disposed within the tubular member said neutron-absorber comprising an absorber material, preferably tungsten, having a 2200 m/s neutron absorption microscopic capture cross-section of from 10 to 30 barns. An internal support tube can be positioned between the primary absorber and the tubular member as a secondary absorber to enhance neutron absorption, absorber depletion, assembly weight, and assembly heat transfer characteristics.

  20. Nuclear Energy

    ScienceCinema (OSTI)

    Godfrey, Anderw

    2014-05-23T23:59:59.000Z

    Andrew Godfrey describes CASL -- the Consortium for Advanced Simulation of Light Water Reactors--a multi-institutional effort led by the Department of Energy that's using high-performance

  1. Nuclear Energy

    SciTech Connect (OSTI)

    Godfrey, Anderw

    2014-04-10T23:59:59.000Z

    Andrew Godfrey describes CASL -- the Consortium for Advanced Simulation of Light Water Reactors--a multi-institutional effort led by the Department of Energy that's using high-performance

  2. Advanced Studies Institute

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

    Engineering Institute Advanced Studies Institute Contact Institute Director Charles Farrar (505) 663-5330 Email UCSD EI Director Michael Todd (858) 534-5951 Professional Staff...

  3. Advanced Reciprocating Engine Systems

    Broader source: Energy.gov [DOE]

    The Advanced Reciprocating Engine Systems (ARES) program is designed to promote separate but parallel engine development between the major stationary, gaseous fueled engine manufacturers in the...

  4. Advanced Propulsion Technology Strategy

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

    Alternative Sources) Hydrogen Time ADVANCED PROPULSION TECHNOLOGY STRATEGY DOWNSIZED TURBO GAS ENGINE CHEVROLET CRUZE 1.4L TURBO ECOTEC Downsized SIDI Turbo Boosting HCCI -...

  5. Advanced Fuel Cycle Initiative

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

    Working with INL Community Outreach Visitor Information Calendar of Events ATR National Scientific User Facility Center for Advanced Energy Studies Light Water Reactor...

  6. Advanced Fuel Cycle Program

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

    Working with INL Community Outreach Visitor Information Calendar of Events ATR National Scientific User Facility Center for Advanced Energy Studies Light Water Reactor...

  7. Advances in Physical Chemistry

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

    Hindawi Publishing Corporation Advances in Physical Chemistry Volume 2011, Article ID 907129, 18 pages doi:10.11552011907129 Review Article Contrast and Synergy between...

  8. Inversion of the star transform

    E-Print Network [OSTI]

    Fan Zhao; John C. Schotland; Vadim A. Markel

    2014-05-06T23:59:59.000Z

    We define the star transform as a generalization of the broken ray transform introduced by us in previous work. The advantages of using the star transform include the possibility to reconstruct the absorption and the scattering coefficients of the medium separately and simultaneously (from the same data) and the possibility to utilize scattered radiation which, in the case of the conventional X-ray tomography, is discarded. In this paper, we derive the star transform from physical principles, discuss its mathematical properties and analyze numerical stability of inversion. In particular, it is shown that stable inversion of the star transform can be obtained only for configurations involving odd number of rays. Several computationally-efficient inversion algorithms are derived and tested numerically.

  9. Competing effects of electronic and nuclear energy loss on microstructural evolution in ionic-covalent materials

    SciTech Connect (OSTI)

    Zhang, Yanwen [ORNL] [ORNL; Varga, Tamas [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL); Ishimaru, Dr. Manabu [Osaka University] [Osaka University; Edmondson, Dr. Philip [University of Oxford] [University of Oxford; Xue, Haizhou [University of Tennessee, Knoxville (UTK)] [University of Tennessee, Knoxville (UTK); Liu, Peng [University of Tennessee, Knoxville (UTK)] [University of Tennessee, Knoxville (UTK); Moll, Sandra [French Atomic Energy Commission (CEA), Centre de Saclay, Gif sur Yvette] [French Atomic Energy Commission (CEA), Centre de Saclay, Gif sur Yvette; Namavar, Fereydoon [University of Nebraska Medical Center] [University of Nebraska Medical Center; Hardiman, Chris [North Carolina State University] [North Carolina State University; Shannon, Prof. Steven [North Carolina State University] [North Carolina State University; Weber, William J [ORNL] [ORNL

    2014-01-01T23:59:59.000Z

    Ever increasing energy needs have raised the demands for advanced fuels and cladding materials that withstand the extreme radiation environments with improved accident tolerance over a long period of time. Ceria (CeO2) is a well known ionic conductor that is isostructural with urania and plutonia-based nuclear fuels. In the context of nuclear fuels, immobilization and transmutation of actinides, CeO2 is a model system for radiation effect studies. Covalent silicon carbide (SiC) is a candidate for use as structural material in fusion, cladding material for fission reactors, and an inert matrix for the transmutation of plutonium and other radioactive actinides. Understanding microstructural change of these ionic-covalent materials to irradiation is important for advanced nuclear energy systems. While displacements from nuclear energy loss may be the primary contribution to damage accumulation in a crystalline matrix and a driving force for the grain boundary evolution in nanostructured materials, local non-equilibrium disorder and excitation through electronic energy loss may, however, produce additional damage or anneal pre-existing defect. At intermediate transit energies where electronic and nuclear energy losses are both significant, synergistic, additive or competitive processes may evolve that affect the dynamic response of materials to irradiation. The response of crystalline and nanostructured CeO2 and SiC to ion irradiation are studied under different nuclear and electronic stopping powers to describe some general material response in this transit energy regime. Although fast radiation-induced grain growth in CeO2 is evident with no phase transformation, different fluence and dose dependence on the growth rate is observed under Si and Au irradiations. While grain shrinkage and amorphization are observed in the nano-engineered 3C SiC with a high-density of stacking faults embedded in nanosize columnar grains, significantly enhanced radiation resistance is attributed to stacking faults that promote efficient point defect annihilation. Moreover, competing effects of electronic and nuclear energy loss on the damage accumulation and annihilation are observed in crystalline 4H-SiC. Systematic experiments and simulation effort are needed to understand the competitive or synergistic effects.

  10. Advanced reactor safety research. Quarterly report, July-September 1981

    SciTech Connect (OSTI)

    Not Available

    1982-10-01T23:59:59.000Z

    Sandia National Laboratories, Albuquerque, New Mexico, is conducting the Advanced Reactor Safety Research Program on behalf of the US Nuclear Regulatory Commission (NRC). Sandia has been given the task to investigate seven major areas of interest which are intimately related to over-all NRC needs. These are: core debris behavior - inherent retention; containment analysis; elevated temperature design assessment; LMFBR accident delineation; advanced reactor core phenomenology; light water reactor (LWR) fuel damage phenomenology; and test and facility technology.

  11. Nuclear Counterterrorism

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2006-02-07T23:59:59.000Z

    The Order defines requirements for the protection of sensitive improvised nuclear device information and provides a framework to support DOE activities related to nuclear counterterrorism. (A supplemental DOE Manual, Control of and Access to Improvised Nuclear Device Information, provides requirements and procedures for protecting Sigma 20 information. The Manual is Official Use Only, and is not available on the Directives Portal. The point of contact for the Manual is Randall Weidman, NA-121.2, 202-586-4582.) Canceled by DOE O 457.1A

  12. Sandia National Laboratories: Advanced Simulation Computing: Research &

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0Energy Advanced Nuclear Energy The Advanced

  13. Sandia National Laboratories: Advanced Simulation Computing: Verification &

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0Energy Advanced Nuclear Energy The AdvancedValidation

  14. Countering Nuclear Terrorism and Trafficking | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Countering Nuclear Terrorism and Trafficking | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  15. Mapping complexity sources in nuclear power plant domains

    E-Print Network [OSTI]

    Sasangohar, Farzan

    Understanding the sources of complexity in advanced Nuclear Power Plant (NPP) control rooms and their effects on human reliability is critical for ensuring safe performance of both operators and the entire system. New ...

  16. Fuel Cycle Options for Optimized Recycling of Nuclear Fuel

    E-Print Network [OSTI]

    Aquien, A.

    The reduction of transuranic inventories of spent nuclear fuel depends upon the deployment of advanced fuels that can be loaded with recycled transuranics (TRU), and the availability of facilities to separate and reprocess ...

  17. Fuel cycle options for optimized recycling of nuclear fuel

    E-Print Network [OSTI]

    Aquien, Alexandre

    2006-01-01T23:59:59.000Z

    The accumulation of transuranic inventories in spent nuclear fuel depends on both deployment of advanced reactors that can be loaded with recycled transuranics (TRU), and on availability of the facilities that separate and ...

  18. In-situ Monitoring of Dynamic Phenomena during Solidification and Phase Transformation Processing

    SciTech Connect (OSTI)

    Clarke, Amy J. [Los Alamos National Laboratory; Cooley, Jason C. [Los Alamos National Laboratory; Morris, Christopher [Los Alamos National Laboratory; Merrill, Frank E. [Los Alamos National Laboratory; Hollander, Brian J. [Los Alamos National Laboratory; Mariam, Fesseha G. [Los Alamos National Laboratory; Patterson, Brian M. [Los Alamos National Laboratory; Imhoff, Seth D. [Los Alamos National Laboratory; Lee, Wah Keat [Brookhaven National Lab; Fezzaa, Kamel [Argonne National Lab; Deriy, Alex [Argonne NationalLbaoratory; Tucker, Tim J. [Los Alamos National Laboratory; Clarke, Kester D. [Los Alamos National Laboratory; Field, Robert D. [Los Alamos National Laboratory; Thoma, Dan J. [Los Alamos National Laboratory; Teter, David F. [Los Alamos National Laboratory; Beard, Timothy V. [Los Alamos National Laboratory; Hudson, Richard W. [Los Alamos National Laboratory; Freibert, Franz J. [Los Alamos National Laboratory; Korzekwa, Deniece R. [Los Alamos National Laboratory; Farrow, Adam M. [Los Alamos National Laboratory; Cross, Carl E. [Los Alamos National Laboratory; Mihaila, Bogdan [Los Alamos National Laboratory; Lookman, Turab [Los Alamos National Laboratory; Hunter, Abigail [Los Alamos National Laboratory; Choudhury, Samrat [Los Alamos National Laboratory; Karma, Alain [Northeastern University; Ott, Thomas J. Jr. [Los Alamos National Laboratory; Barker, Martha R. [Los Alamos National Laboratory; O'Neill, Finian [Former MST-6 Summer Student; Hill, Joshua [Former MST-6 Summer Student; Emigh, Megan G. [Los Alamos National Laboratory

    2012-07-30T23:59:59.000Z

    The purpose of this project is to: (1) Directly observe phase transformations and microstructure evolution using proton (and synchrotron x-ray) radiography and tomography; (2) Constrain phase-field models for microstructure evolution; (3) Experimentally control microstructure evolution during processing to enable co-design; and (4) Advance toward the MaRIE vision. Understand microstructure evolution and chemical segregation during solidification {yields} solid-state transformations in Pu-Ga.

  19. Nuclear-spectroscopy problems studied with neutrons

    SciTech Connect (OSTI)

    Raman, S.

    1982-01-01T23:59:59.000Z

    Nuclear spectroscopy with neutrons continues to have a major impact on the progress of nuclear science. Neutrons, being uncharged, are particularly useful for the study of low energy reactions. Recent advances in time-of-flight spectroscopy, as well as in the gamma ray spectroscopy following neutron capture, have permitted precision studies of unbound and bound nuclear levels and related phenomena. By going to new energy domains, by using polarized beams and targets, through the invention of new kinds of detectors, and through the general improvement in beam quantity and quality, new features of nuclear structure and reactions have been obtained that are not ony interesting per se but are also grist for old and new theory mills. The above technical advances have opened up new opportunities for further discoveries.

  20. Status of Iran's nuclear program and negotiations

    SciTech Connect (OSTI)

    Albright, David [President, Institute for Science and International Security (ISIS), 236 Massachusetts Avenue, NE 305, Washington, DC 20002 (United States)

    2014-05-09T23:59:59.000Z

    Iran's nuclear program poses immense challenges to international security. Its gas centrifuge program has grown dramatically in the last several years, bringing Iran close to a point where it could produce highly enriched uranium in secret or declared gas centrifuge plants before its breakout would be discovered and stopped. To reduce the risk posed by Iran's nuclear program, the P5+1 have negotiated with Iran short term limits on the most dangerous aspects of its nuclear programs and is negotiating long-term arrangements that can provide assurance that Iran will not build nuclear weapons. These long-term arrangements need to include a far more limited and transparent Iranian nuclear program. In advance of arriving at a long-term arrangement, the IAEA will need to resolve its concerns about the alleged past and possibly on-going military dimensions of Iran's nuclear program.

  1. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

    2008-03-01T23:59:59.000Z

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules—23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

  2. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert

    2007-04-01T23:59:59.000Z

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 26 cost modules—24 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, and high-level waste.

  3. Advanced Demand Responsive Lighting

    E-Print Network [OSTI]

    Advanced Demand Responsive Lighting Host: Francis Rubinstein Demand Response Research Center demand responsive lighting systems ­ Importance of dimming ­ New wireless controls technologies · Advanced Demand Responsive Lighting (commenced March 2007) #12;Objectives · Provide up-to-date information

  4. Kansas Advanced Semiconductor Project

    SciTech Connect (OSTI)

    Baringer, P.; Bean, A.; Bolton, T.; Horton-Smith, G.; Maravin, Y.; Ratra, B.; Stanton, N.; von Toerne, E.; Wilson, G.

    2007-09-21T23:59:59.000Z

    KASP (Kansas Advanced Semiconductor Project) completed the new Layer 0 upgrade for D0, assumed key electronics projects for the US CMS project, finished important new physics measurements with the D0 experiment at Fermilab, made substantial contributions to detector studies for the proposed e+e- international linear collider (ILC), and advanced key initiatives in non-accelerator-based neutrino physics.

  5. NUCLEAR PLANT OPERATIONS AND

    E-Print Network [OSTI]

    Pázsit, Imre

    NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: neutron flux, cur- rent noise, vibration diagnostics: Swedish Nuclear Powe

  6. Space Nuclear

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

    Space Nuclear Today the INL is preparing to assist with the Multi-Mission RTG (MMRTG). The INL is assigned the final assembly and testing of the RTG for the project which is...

  7. Nuclear Golf

    E-Print Network [OSTI]

    Hacker, Randi; Tsutsui, William

    2006-12-06T23:59:59.000Z

    Broadcast Transcript: Pay no attention to that nuclear warhead behind the 18th hole; just shout "Fore!" and drive your Titleist down the fairway. In a development that is bizarre even by North Korean standards, the country ...

  8. Nuclear Hydrogen

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

    Hydrogen High temperature options for nuclear generation of hydrogen on a commercial basis are several years in the future. Thermo-chemical water splitting has been proven to be...

  9. Nuclear forces

    SciTech Connect (OSTI)

    Machleidt, R. [Department of Physics, University of Idaho, Moscow, Idaho 83844 (United States)

    2013-06-10T23:59:59.000Z

    These lectures present an introduction into the theory of nuclear forces. We focus mainly on the modern approach, in which the forces between nucleons emerge from low-energy QCD via chiral effective field theory.

  10. Formal Transformations and WSL Martin Ward

    E-Print Network [OSTI]

    Singer, Jeremy

    Formal Transformations and WSL Part Two Martin Ward STRL Senior Research Fellow Royal Society of Transformations #12;Types of Transformations A Syntactic Transformation changes the syntax of the program but preserves the exact sequence of operations carried out by the program. Many restructuring transformations

  11. Transformer Efficiency Assessment - Okinawa, Japan

    SciTech Connect (OSTI)

    Thomas L. Baldwin; Robert J. Turk; Kurt S. Myers; Jake P. Gentle; Jason W. Bush

    2012-05-01T23:59:59.000Z

    The US Army Engineering & Support Center, Huntsville (USAESCH), and the US Marine Corps Base (MCB), Okinawa, Japan retained Idaho National Laboratory (INL) to conduct a Transformer Efficiency Assessment of “key” transformers located at multiple military bases in Okinawa, Japan. The purpose of this assessment is to support the Marine Corps Base, Okinawa in evaluating medium voltage distribution transformers for potential efficiency upgrades. The original scope of work included the MCB providing actual transformer nameplate data, manufacturer’s factory test sheets, electrical system data (kWh), demand data (kWd), power factor data, and electricity cost data. Unfortunately, the MCB’s actual data is not available and therefore making it necessary to de-scope the original assessment. Note: Any similar nameplate data, photos of similar transformer nameplates, and basic electrical details from one-line drawings (provided by MCB) are not a replacement for actual load loss test data. It is recommended that load measurements are performed on the high and low sides of transformers to better quantify actual load losses, demand data, and power factor data. We also recommend that actual data, when available, be inserted by MCB Okinawa where assumptions have been made and then the LCC analysis updated. This report covers a generalized assessment of modern U.S. transformers in a three level efficiency category, Low-Level efficiency, Medium-Level efficiency, and High-Level efficiency.

  12. Transformer Efficiency Assessment - Okinawa, Japan

    SciTech Connect (OSTI)

    Thomas L. Baldwin; Robert J. Turk; Kurt S. Myers; Jake P. Gentle; Jason W. Bush

    2012-08-01T23:59:59.000Z

    The US Army Engineering & Support Center, Huntsville (USAESCH), and the US Marine Corps Base (MCB), Okinawa, Japan retained Idaho National Laboratory (INL) to conduct a Transformer Efficiency Assessment of “key” transformers located at multiple military bases in Okinawa, Japan. The purpose of this assessment is to support the Marine Corps Base, Okinawa in evaluating medium voltage distribution transformers for potential efficiency upgrades. The original scope of work included the MCB providing actual transformer nameplate data, manufacturer’s factory test sheets, electrical system data (kWh), demand data (kWd), power factor data, and electricity cost data. Unfortunately, the MCB’s actual data is not available and therefore making it necessary to de-scope the original assessment. Note: Any similar nameplate data, photos of similar transformer nameplates, and basic electrical details from one-line drawings (provided by MCB) are not a replacement for actual load loss test data. It is recommended that load measurements are performed on the high and low sides of transformers to better quantify actual load losses, demand data, and power factor data. We also recommend that actual data, when available, be inserted by MCB Okinawa where assumptions have been made and then the LCC analysis updated. This report covers a generalized assessment of modern U.S. transformers in a three level efficiency category, Low-Level efficiency, Medium-Level efficiency, and High-Level efficiency.

  13. DNA UPTAKE BY TRANSFORMABLE BACTERIA

    SciTech Connect (OSTI)

    LACKS,S.A.

    1999-09-07T23:59:59.000Z

    The various processes of DNA uptake by cells can be categorized as: viral DNA entry, conjugation, or transformation. Within each category, a variety of mechanisms have been found. However, considerable similarities occur among the different mechanisms of conjugation and, especially, transformation. All of these natural mechanisms of DNA transfer are quite elaborate and involve multiple protein components, as the case may be, of the virus, the donor cell, and the recipient cell. The mechanisms of viral infection and conjugation will be discussed mainly with respect to their relevance to transformation.

  14. Transformer modeling in power systems

    SciTech Connect (OSTI)

    Ma, J.; Dawalibi, F.P. [Safe Engineering Services and Technologies Ltd., Montreal, Quebec (Canada)

    1999-11-01T23:59:59.000Z

    A practical and accurate method of modeling various transformers in power systems using a general circuit model approach is described in this paper. The advantage of the new approach is that it can model transformers along with a complex circuit network, while avoiding the use of symmetrical components, unlike other approaches. The transformer modeling technique introduced in this paper is very useful to accurately determine fault current distribution in a power system and electromagnetic interference on pipelines and communication lines installed in a right-of-way consisting of transmission lines operating at different voltages.

  15. Mineral Transformation and Biomass Accumulation Associated With

    E-Print Network [OSTI]

    Hubbard, Susan

    Mineral Transformation and Biomass Accumulation Associated With Uranium Bioremediation at Rifle transformation and biomass accumulation, both of which can alter the flow field and potentially bioremediation to understand the biogeochemical processes and to quantify the biomass and mineral transformation/ accumulation

  16. Transforms for the Motion Compensation Residual

    E-Print Network [OSTI]

    Kamisli, Fatih

    The Discrete-Cosine-Transform (DCT) is the most widely used transform in image and video compression. Its use in image compression is often justified by the notion that it is the statistically optimal transform for first-order ...

  17. TRANSFORMING ACADEMIA Historical Developments, Contemporary Perspectives and

    E-Print Network [OSTI]

    Li, Mo

    ISyE 8803A TRANSFORMING ACADEMIA Historical Developments, Contemporary Perspectives independence and this organizational structure represent the first major transformation of academia. These characteristics of academia have persisted for over 900 years and seem immutable. Yet, notable transformations

  18. Ancilla Approximable Quantum State Transformations

    E-Print Network [OSTI]

    Andreas Blass; Yuri Gurevich

    2014-03-30T23:59:59.000Z

    We consider the transformations of quantum states obtainable by a process of the following sort. Combine the given input state with a specially prepared initial state of an auxiliary system. Apply a unitary transformation to the combined system. Measure the state of the auxiliary subsystem. If (and only if) it is in a specified final state, consider the process successful, and take the resulting state of the original (principal) system as the result of the process. We review known information about exact realization of transformations by such a process. Then we present results about approximate realization of finite partial transformations. We consider primarily the issue of approximation to within a specified positive epsilon, but we also address the question of arbitrarily close approximation.

  19. advanced ceramics advanced: Topics by E-print Network

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

    . . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

  20. RETHINKING THE FUTURE GRID: INTEGRATED NUCLEAR-RENEWABLE ENERGY SYSTEMS

    SciTech Connect (OSTI)

    S.M. Bragg-Sitton; R. Boardman

    2014-12-01T23:59:59.000Z

    The 2013 electricity generation mix in the United States consisted of ~13% renewables (hydropower, wind, solar, geothermal), 19% nuclear, 27% natural gas, and 39% coal. In the 2011 State of the Union Address, President Obama set a clean energy goal for the nation: “By 2035, 80 percent of America’s electricity will come from clean energy sources. Some folks want wind and solar. Others want nuclear, clean coal and natural gas. To meet this goal we will need them all.” The U.S. Department of Energy (DOE) Offices of Nuclear Energy (NE) and Energy Efficiency and Renewable Energy (EERE) recognize that “all of the above” means that we are called to best utilize all available clean energy sources. To meet the stated environmental goals for electricity generation and for the broader energy sector, there is a need to transform the energy infrastructure of the U.S. and elsewhere. New energy systems must be capable of significantly reducing environmental impacts in an efficient and economically viable manner while utilizing both hydrocarbon resources and clean energy generation sources. The U.S. DOE is supporting research and development that could lead to more efficient utilization of clean energy generation sources, including renewable and nuclear options, to meet both grid demand and thermal energy needs in the industrial sector. A concept being advanced by the DOE-NE and DOE-EERE is tighter coupling of nuclear and renewable energy sources in a manner that better optimizes energy use for the combined electricity, industrial manufacturing, and the transportation sectors. This integration concept has been referred to as a “hybrid system” that is capable of apportioning thermal and electrical energy to first meet the grid demand (with appropriate power conversion systems), then utilizing excess thermal and, in some cases, electrical energy to drive a process that results in an additional product. For the purposes of the present work, the hybrid system would integrate two or more energy resources to generate two or more products, one of which must be an energy commodity, such as electricity or transportation fuel. Subsystems would be integrated ‘‘behind’’ the electrical transmission bus and would be comprised of two or more energy conversion subsystems that have traditionally been separate or isolated. Energy flows would be dynamically apportioned as necessary to meet grid demand via a single, highly responsive connection to the grid that provides dispatchable electricity while capital-intensive generation assets operate at full capacity. Candidate region-specific hybrid energy systems selected for further study and figures of merit that will be used to assess system performance will be presented.

  1. The Adoption of Advanced Fuel Cycle Technology Under a Single Repository Policy

    SciTech Connect (OSTI)

    Paul Wilson

    2009-11-02T23:59:59.000Z

    Develops the tools to investiage the hypothesis that the savings in repository space associated with the implementation of advanced nuclear fuel cycles can result in sufficient cost savings to offset the higher costs of those fuel cycles.

  2. Amendment 1 - Dry-type power transformers

    E-Print Network [OSTI]

    International Electrotechnical Commission. Geneva

    1986-01-01T23:59:59.000Z

    Specifies requirements for dry-type power transformers (including auto-transformers) having values of highest voltage for equipment up to and including 36 kV. The following small and special dry-type transformers are not covered by this standard: -instrument transformers (covered by IEC 60185 and 60186); -transformers for static convertors (covered by IEC 60084, 60119 and 60146). Where IEC standards do not exist for other special transformers, this standard may be applicable as a whole or in part.

  3. Coupled diffusional/displacive transformations

    E-Print Network [OSTI]

    Mujahid, Shafiq Ahmad

    ), TRIP steels (transformation in- duced plasticity), ausforming steels (plastically deformed austenite prior to quenching) and dual phase steels (a mixture of ferrite + martensite obtained by quenching from the 1+ Q' field). a c b d Figure 1... Supersaturated Ferrite Plates 137 v Abstract The displacive transformation of austenite to ferrite in steels containing both substitutional and interstitial elements has been studied. The aim was to establish the conditions under which plates of the product phase...

  4. Technological Transfer from Research Nuclear Reactors to New Generation Nuclear Power Reactors

    SciTech Connect (OSTI)

    Radulescu, Laura ['Horia Hulubei' National Institute of Nuclear Physics and Engineering, PO BOX MG-6, Bucharest 077125 (Romania); Pavelescu, Margarit [Academy of Romanian Scientists, Bucharest (Romania)

    2010-01-21T23:59:59.000Z

    The goal of this paper is the analysis of the technological transfer role in the nuclear field, with particular emphasis on nuclear reactors domain. The presentation is sustained by historical arguments. In this frame, it is very important to start with the achievements of the first nuclear systems, for instant those with natural uranium as fuel and heavy water as moderator, following in time through the history until the New Generation Nuclear Power Reactors.Starting with 1940, the accelerated development of the industry has implied the increase of the global demand for energy. In this respect, the nuclear energy could play an important role, being essentially an unlimited source of energy. However, the nuclear option faces the challenges of increasingly demanding safety requirements, economic competitiveness and public acceptance. Worldwide, a significant amount of experience has been accumulated during development, licensing, construction, and operation of nuclear power reactors. The experience gained is a strong basis for further improvements. Actually, the nuclear programs of many countries are addressing the development of advanced reactors, which are intended to have better economics, higher reliability, improved safety, and proliferation-resistant characteristics in order to overcome the current concerns about nuclear power. Advanced reactors, now under development, may help to meet the demand for energy power of both developed and developing countries as well as for district heating, desalination and for process heat.The paper gives historical examples that illustrate the steps pursued from first research nuclear reactors to present advanced power reactors. Emphasis was laid upon the fact that the progress is due to the great discoveries of the nuclear scientists using the technological transfer.

  5. On the broken ray transform

    E-Print Network [OSTI]

    Joonas Ilmavirta

    2014-09-26T23:59:59.000Z

    This PhD thesis studies the broken ray transform, a generalization of the geodesic X-ray transform where geodesics are replaced with broken rays that reflect on a part of the boundary. The fundamental question is whether this transform is injective. We employ four different methods to approach this question, and each of them gives interesting results. Direct calculation can be used in a ball, where the geometry is particularly simple. If the reflecting part of the boundary is (piecewise) flat, a reflection argument can be used to reduce the problem to the usual X-ray transform. In some geometries one can use broken rays near the boundary to determine the values of the unknown function at the reflector, and even construct its Taylor series. One can also use energy estimates -- which in this context are known as Pestov identities -- to show injectivity in the presence of one convex reflecting obstacle. Many of these methods work also on Riemannian manifolds. We also discuss the periodic broken ray transform, where the integrals are taken over periodic broken rays. The broken ray transform and its periodic version have applications in other inverse problems, including Calder\\'on's problem and problems related to spectral geometry. A more detailed abstract can be found in the PDF file. This version only contains the introductory parts of the thesis. The full thesis also contains five articles.

  6. Fact Sheet: Energy Storage Technology Advancement Partnership...

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

    Technology Advancement Partnership (October 2012) Fact Sheet: Energy Storage Technology Advancement Partnership (October 2012) The Energy Storage Technology Advancement Partnership...

  7. The Industrial Transformation of Subarctic Canada

    E-Print Network [OSTI]

    Mathoor, Vineeth

    2011-01-01T23:59:59.000Z

    in the subarctic region of Canada. The role of scientificTransformation of Subarctic Canada By Liza Piper Reviewed byTransformation of Subarctic Canada. Vancouver, BC: UBC

  8. Energy Department Finalizes Loan Guarantee for Transformational...

    Office of Environmental Management (EM)

    Transformational Rooftop Solar Project Energy Department Finalizes Loan Guarantee for Transformational Rooftop Solar Project September 30, 2011 - 3:37pm Addthis Washington D.C. -...

  9. Investigation of Mineral Transformations in Wet Supercritical...

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

    Mineral Transformations in Wet Supercritical CO2 by Electron Microscopy. Investigation of Mineral Transformations in Wet Supercritical CO2 by Electron Microscopy. Abstract: The...

  10. Mineralogical transformations controlling acid mine drainage...

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

    Mineralogical transformations controlling acid mine drainage chemistry. Mineralogical transformations controlling acid mine drainage chemistry. Abstract: The role of Fe(III)...

  11. Marketing and Market Transformation | Department of Energy

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

    and Market Transformation Marketing and Market Transformation Presents how going green will grow your business, as well as how programs can overcome appraisal challenges....

  12. Sandia National Laboratories: Solar Market Transformation

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

    Transformation * photovoltaic * Photovoltaics * PV * Renewable Energy * SAND 2011-4654W * Solar Energy * Solar Market Transformation * Solar Research Comments are closed. Renewable...

  13. Building America Expert Meeting: Transforming Existing Buildings...

    Energy Savers [EERE]

    Transforming Existing Buildings through New Media--An Idea Exchange Building America Expert Meeting: Transforming Existing Buildings through New Media--An Idea Exchange This report...

  14. 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.

  15. Nuclear Data Evaluations for Americium Isotopes

    SciTech Connect (OSTI)

    Kawano, T.; Talou, P.; Chadwick, M.B.; MacFarlane, R.E.; Young, P.G. [T-16 Nuclear Physics, Los Alamos National Laboratory (United States)

    2005-05-24T23:59:59.000Z

    Recent upgrades of 241Am, 242mAm, and 240Am nuclear data in the keV - 30-MeV range are described. The new evaluation takes advantage of recent measurements and advances in calculational modeling methods. The model calculations are especially important for the nuclear data of americium isotopes, because few measurements are available. The nuclear-model code GNASH is extensively used for our evaluations. The new evaluations are given for total, fission, capture (n, 2n), and (n, 3n) reaction cross sections, and vp for 241Am and 242mAm. A new evaluation for 240Am is also given by expanding our modeling feasibility.

  16. Nuclear materials safeguards for the future

    SciTech Connect (OSTI)

    Tape, J.W.

    1995-12-31T23:59:59.000Z

    Basic concepts of domestic and international safeguards are described, with an emphasis on safeguards systems for the fuel cycles of commercial power reactors. Future trends in institutional and technical measures for nuclear materials safeguards are outlined. The conclusion is that continued developments in safeguards approaches and technology, coupled with institutional measures that facilitate the global management and protection of nuclear materials, are up to the challenge of safeguarding the growing inventories of nuclear materials in commercial fuel cycles in technologically advanced States with stable governments that have signed the nonproliferation treaty. These same approaches also show promise for facilitating international inspection of excess weapons materials and verifying a fissile materials cutoff convention.

  17. Search Asia Advanced Search

    E-Print Network [OSTI]

    Asia Times Search Asia Times Advanced Search Southeast Asia Malaysia tackles illegal logging:52:14 AM Search #12;Asia Times illegal logging," he said, adding that nine Malaysians had been arrested

  18. Search Asia Advanced Search

    E-Print Network [OSTI]

    Asia Times Search Asia Times Advanced Search Southeast Asia Indonesia looks to curb log smuggling.html (1 of 2)9/4/2007 12:59:34 PM Search #12;Asia Times No material from Asia Times Online may

  19. Advanced Review Geometry optimization

    E-Print Network [OSTI]

    Schlegel, H. Bernhard

    Advanced Review Geometry optimization H. Bernhard Schlegel Geometry optimization is an important part of most quantum chemical calcu- lations. This article surveys methods for optimizing equilibrium geometries, lo- cating transition structures, and following reaction paths. The emphasis is on optimizations

  20. Advanced Materials | More Science | ORNL

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

    Advanced Materials SHARE Advanced Materials ORNL has the nation's most comprehensive materials research program and is a world leader in research that supports the development of...

  1. Renewable Chemicals and Advanced Biofuels

    Broader source: Energy.gov [DOE]

    Afternoon Plenary Session: Current Trends in the Advanced Bioindustry Advanced Biofuels & Policy—Brett Lund, Executive Vice President, General Counsel and Secretary, Gevo Inc.

  2. Foiling the Flu Bug Global Partnerships for Nuclear Energy

    E-Print Network [OSTI]

    1 1663 Foiling the Flu Bug Global Partnerships for Nuclear Energy Dark Universe Mysteries WILL NOT NEED TESTING Expanding Nuclear Energy the Right Way GLOBAL PARTNERSHIPS AND AN ADVANCED FUEL CYCLE sense.The Laboratory is operated by Los Alamos National Security, LLC, for the Department of Energy

  3. Mysteries of the lightest nuclear systems R. Lazauskas,

    E-Print Network [OSTI]

    Boyer, Edmond

    NF,..), however nuclear binding energies being strongly correlated does not permit to form a fullMysteries of the lightest nuclear systems R. Lazauskas, CEA DAM/DIF/DPTA/SPN, B.P. 12, Bruy In this contribution current advances and challenge in low energy few- nucleon scattering problem are discussed. Some

  4. UN Security Council: Iran violating ban on nuclear weapons programs

    E-Print Network [OSTI]

    UN Security Council: Iran violating ban on nuclear weapons programs 7 September 2011 Denouncement comes after International Atomic Energy Agency submits a report claiming Iran continues to make advances weaponization of its nuclear program. The United States, Germany, France and Britain joined forces in exposing

  5. Nuclear Physics

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls |Navy Nuclear NavyNuclear Physics

  6. Nuclear Structure

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls |NavyNuclear Speed-Dating Nuclear

  7. Nuclear Forensics

    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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchives Events/NewsYouNuclearNuclear Forensics

  8. INEEL/EXT-04-02506 2 Decision-Makers' Forum on a Unified Strategy for Nuclear Energy

    E-Print Network [OSTI]

    INEEL/EXT-04-02506 #12;2 Decision-Makers' Forum on a Unified Strategy for Nuclear Energy The Need deliver new nuclear energy systems and reestablish U.S. leadership in nuclear energy development, or imperatives. Each imperative contributes to answer the following question: To advance nuclear energy

  9. Nuclear reactor engineering: Reactor systems engineering. Fourth edition, Volume Two

    SciTech Connect (OSTI)

    Glasstone, S.; Sesonske, A.

    1994-12-31T23:59:59.000Z

    This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. Extensively updated, the fourth edition includes new materials on reactor safety and risk analysis, regulation, fuel management, waste management and operational aspects of nuclear power. This volume contains the following: the systems concept, design decisions, and information tools; energy transport; reactor fuel management and energy cost considerations; environmental effects of nuclear power and waste management; nuclear reactor safety and regulation; power reactor systems; plant operations; and advanced plants and the future.

  10. Overview of Nuclear Energy: Present and Projected Use

    SciTech Connect (OSTI)

    Alexander Stanculescu

    2011-09-01T23:59:59.000Z

    Several factors will influence the contribution of nuclear energy to the future energy mix. Among them, the most important are the degree of global commitment to greenhouse gas reduction, continued vigilance in safety and safeguards, technological advances, economic competitiveness and innovative financing arrangements for new nuclear power plant constructions, the implementation of nuclear waste disposal, and, last but not least, public perception, information and education. The paper presents an overview of the current nuclear energy situation, possible development scenarios, of reactor technology, and of non-electric applications of nuclear energy.

  11. Overview of nuclear energy: Present and projected use

    SciTech Connect (OSTI)

    Stanculescu, Alexander [Idaho National Laboratory 2525 North Fremont Avenue, Idaho Falls, Idaho 83415 (United States)

    2012-06-19T23:59:59.000Z

    Several factors will influence the contribution of nuclear energy to the future energy mix. Among them, the most important are the degree of global commitment to greenhouse gas reduction, continued vigilance in safety and safeguards, technological advances, economic competitiveness and innovative financing arrangements for new nuclear power plant constructions, the implementation of nuclear waste disposal, and, last but not least, public perception, information and education. The paper presents an overview of the current nuclear energy situation, possible development scenarios, of reactor technology, and of non-electric applications of nuclear energy.

  12. Examination of the legal mechanisms to regulate advanced fision reactors

    SciTech Connect (OSTI)

    Brinig, M.F.; Repici, D.J.

    1988-12-01T23:59:59.000Z

    The George Mason University School of Law (GMUSL) located in Northern Virginia, and its subcontractor, The John Francis Company, Inc., of Fairfax, Virginia, conducted a study for the Department of Energy's Office of Nuclear Energy which examined the legal mechanisms for the regulation of advanced fision reactors. This report presents the research and findings conducted under that study.

  13. Nuclear Energy Density Optimization

    E-Print Network [OSTI]

    M. Kortelainen; T. Lesinski; J. Moré; W. Nazarewicz; J. Sarich; N. Schunck; M. V. Stoitsov; S. Wild

    2010-05-27T23:59:59.000Z

    We carry out state-of-the-art optimization of a nuclear energy density of Skyrme type in the framework of the Hartree-Fock-Bogoliubov (HFB) theory. The particle-hole and particle-particle channels are optimized simultaneously, and the experimental data set includes both spherical and deformed nuclei. The new model-based, derivative-free optimization algorithm used in this work has been found to be significantly better than standard optimization methods in terms of reliability, speed, accuracy, and precision. The resulting parameter set UNEDFpre results in good agreement with experimental masses, radii, and deformations and seems to be free of finite-size instabilities. An estimate of the reliability of the obtained parameterization is given, based on standard statistical methods. We discuss new physics insights offered by the advanced covariance analysis.

  14. Density Functional Theory Approach to Nuclear Fission

    E-Print Network [OSTI]

    N. Schunck

    2013-01-20T23:59:59.000Z

    The Skyrme nuclear energy density functional theory (DFT) is used to model neutron-induced fission in actinides. This paper focuses on the numerical implementation of the theory. In particular, it reports recent advances in DFT code development on leadership class computers, and presents a detailed analysis of the numerical accuracy of DFT solvers for near-scission calculations.

  15. Nuclear Nonproliferation Programs | ORNL

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

    Nuclear Nonproliferation Programs SHARE Nuclear Nonproliferation Programs image Oak Ridge National Laboratory covers the entire spectrum of nuclear nonproliferation work, from...

  16. NUCLEAR PROXIMITY FORCES

    E-Print Network [OSTI]

    Randrup, J.

    2011-01-01T23:59:59.000Z

    One might summarize of nuclear potential energy has beendegree of freedom) for the nuclear interaction between anyUniversity of California. Nuclear Proximity Forces 'I< at

  17. Global Nuclear Security

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

    Global Nuclear Security Both DOE and the National Nuclear Security Administration are working to reduce the risk of nuclear proliferation and provide technologies to improve...

  18. Advanced Manufacturing for a U.S. Clean Energy Economy (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-03-01T23:59:59.000Z

    This fact sheet is an overview of the U.S. Department of Energy's Advanced Manufacturing Office. Manufacturing is central to our economy, culture, and history. The industrial sector produces 11% of U.S. gross domestic product (GDP), employs 12 million people, and generates 57% of U.S. export value. However, U.S. industry consumes about one-third of all energy produced in the United States, and significant cost-effective energy efficiency and advanced manufacturing opportunities remain unexploited. As a critical component of the National Innovation Policy for Advanced Manufacturing, the U.S. Department of Energy's (DOE's) Advanced Manufacturing Office (AMO) is focused on creating a fertile environment for advanced manufacturing innovation, enabling vigorous domestic development of transformative manufacturing technologies, promoting coordinated public and private investment in precompetitive advanced manufacturing technology infrastructure, and facilitating the rapid scale-up and market penetration of advanced manufacturing technologies.

  19. Methods for manufacturing porous nuclear fuel elements for high-temperature gas-cooled nuclear reactors

    DOE Patents [OSTI]

    Youchison, Dennis L. (Albuquerque, NM); Williams, Brian E. (Pocoima, CA); Benander, Robert E. (Pacoima, CA)

    2010-02-23T23:59:59.000Z

    Methods for manufacturing porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's). 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, a thin coating of nuclear fuel may be deposited inside of a highly porous skeletal structure made, for example, of reticulated vitreous carbon foam.

  20. Porous nuclear fuel element for high-temperature gas-cooled nuclear reactors

    DOE Patents [OSTI]

    Youchison, Dennis L. (Albuquerque, NM); Williams, Brian E. (Pacoima, CA); Benander, Robert E. (Pacoima, CA)

    2011-03-01T23:59:59.000Z

    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.