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Error estimators and adaptivity for the neutron diffusion problem
05 Nuclear fuels (scientific, technical)
96/02694
Defuelling PFR
Nuclear Engineering Int., Mar. 1996, 41, (500), 21-22. Reports that when the Prototype Fast Reactor (PFR) located at Dounreay on the north coast of Scotland, ceased operation on 31 March 1994, it still contained almost 1/3 of the total number of sub-assemblies that had been through the 250 MWe reactor over its 20 year lifetime. To carry out the defuelling, which was completed in October 1995, ahead of schedule, AEA Technology had to take particular care to prevent any possibility of a criticality incident while achieving the quickest and most cost effective sequence for fuel removal possible.
96/02695 Design of particle bed reactors for the space nuclear thermal propulsion program Ludewig, H. et al., Progress in Nuclear Energy, 1996, 30, (1), 1-65. Describes the design for the particle bed reactor that the authors considered for the space nuclear thermal propulsion programme. The methods of analysis and their validation are outlined first. Monte Carlo methods were used for the physics analysis, several new algorithms were developed for the fluid dynamics, heat transfer and transient analysis, and commercial codes were used for the stress analysis.
96/02696 Diffusion theory methods for spatial kinetics calculations Sullon, T. M. and Aviles, B. N. Progress in Nuclear Energy, 1996, 30, (2), 119-182. Discusses the methods for solving the time-dependent neutron diffusion equation for nuclear reactor analysis. Techniques for treating the spatial variables, as well as techniques for performing the time integration, are described. A major advance made in the treatment of the spatial variables over the past 20 years has been the development of the transverse-integrated class of nodal methods, and thus these methods are described in considerable detail. Finally, results for selected standard benchmark problems that have been obtained using a variety of spatial kinetics rnethods are compared.
96/02697 Disposition of spent nuclear fuel using the modular helium reactor Richards, M. B. Energy, Apr. 1996,21, (4), 333-341. Unprocessed light water reactor (LWR) spent fuel may prove to be an unacceptable waste form for permanent geologic disposal because of serious technical and programmatic issues related to long-term proliferation risks and safeguards requirements, to long-term containment of radionuclides, and to undergound criticality. An alternative strategy using Modular Helium Reactors (MHRs) and coated-particle fuel technology would deal effectively with these issues, while generating significant revenues from the sale of electricity and demonstrating a meltdown-proof, advanced reactor design for future energy needs. The paper was submitted as a comment to the U.S. Department of Energy for determining the scope and content of the Environmental Impact Statement for the proposed Yucca Mountain geologic repository.
96/02698 studies
EFCC lobbies EC to fund East European fuel cycle
Barrett, R. Nuclear Engineering Int., Apr. 1996, 41, (501), p. 41. The European Fuel Cycle Consortium (EFCC) was formed by five West European countries in July 1993 to advise and assist the European Commission in the key areas of environmental and safety concern relating to Eastern Europe's fuel cycle plants and management of irradiated fuel. What has it achieved since it formed?
96/02699 The effect of strong anisotropic scattering on the critical sphere problem in neutron transport theory using a synthetic kernel Yildiz, C. and Alcan, E. Ann. Nucl. Energy, Oct. 1995,22, (10), 671-679. The effect of strong anisotropic scattering law on the variation of the critical radius in one-speed neutron transport theory is studied using a synthetic kernal. Numerical results for the critical radius are obtained and tabulated for selected illustrative cases. The results indicate that low-order Legendre approximation are sufficient to show the effect of anisotropic scattering on the variation of the critical radius.
96/02701
Evolutionary PWR constructed in 64 months
MPS, Modern Power Systems, Dec. 1995, 15, (12), 43, 45-46. Reports that at the end of March 1994, Yonggwang Unit 3 (Korea) entered commercial operation. The first-of-a-kind 1000 MW PWR, together with Yonggwang Unit 4, forms the basis of one of the most active nuclear construction programmes in the world. Construction lasted just 64 months.
96/02702 Grouping of HLW in partitioning for BIT (burning and/or transmutation) treatment with neutron reactors based on three criteria Kitamoto, M. and Kitamoto, A. Ann. Nucl. Energy, Nov. 1995,22, (11), 697-709. A grouping concept of HLW in partitioning for BIT (burning and/or transmutation) treatment by fission reactor was developed in order to improve the disposal in waste management from the safety aspect is described.
96/02703
Holtec International. HI-STAR and HI-STORM
Pennington, C. W. Nuclear Engineering Int., Apr. 1996,41, (501), p. 38. Describes the HI-STAR 100 and the HI-STORM 100 system for storage and transportation of spent fuels.
96/02704
How to move forward with the Alliance proposal
Ewart, F. Nuclear Engineering Int., Apr. 1996, 41, (501), p. 29. A short report on the study carried out by the European consortium 'Alliance' into the design of a new containment for the destroyed fourth reactor at Chernobyl.
96/02705
Lasers light the way
Nuclear Engineering lnt., Mar. 1996, 41, (500), p. 28. Reports that with the start of the campaign at Farley 2 in April 1992, Westinghouse has now put into service over 30,000 laser welded sleeves in six nuclear power plants.
96/02706 Light ion driven inertial confinement fusion Quintenz, J. P. et al., Progress in Nuclear Energy, 1996,30, (2), 183-242. Inertial Confinement Fusion (ICF) driven by intense beams of light ions offers the possibility for high gain target implosions. High gain implosions will be required to meet the United States' defense applications for rCF as well as to make an Inertial Fusion Energy (IFE) power plant an economically viable option for energy production in the 21st century. Progress in understanding the generation and focusing of intense light ion beams has resulted in record beam intensities. These beams have been used to heat the first ion-driven hohlraurns to provide favourable answers to key questions about the interation of these beams with matter. Describes the present state of the light ion ICF programme, its current limitations, and the prognosis for future advances. A successful research programme would lead to a commercially attractive fusion power plant.
96/02707 Mixed Oxide Fuel (MOX) exploitation and destruction in power reactors Proc. of the NATO Advanced Research Workshop, Obninsk, Russia, 16-19 Oct. 1994, Kluwer Academic Publishers Group, Dordrecht, $160.00, 1995.
96/02708 Modelling of fisson product release by re-entralnment due to bursting bubbles Unger, H. et al., Kerntechnik, Feb. 1996, 61, (1), 16-21. In the framework of nuclear safety analyzes, the code RESUS is being developed for the prediction of the release of droplets and low volatile radionuclides due to bubble bursting at liquid surfaces. The code consists of three independent submodules, each simulating important submechanisms of droplet generation. The mechanistic models are explained and results of RESUS calculations are presented. Profiles of bubbles resting at a phase interface are discussed in some detail. There is good agreement between calculated and experimentally observed shapes given in the literature.
96/02709
Nuclear power reactors in the world
15th Edition, Reference Data Series No.2, IAEA, Wien, AS.140.00, 1995, 78 pp.
96/02700 Error estimators and adaptlvity for the neutron diffusion problem
96/02710
Jatuff, F. E. Ann. Nucl. Energy, Dec. 1995,22, (12), 775-786. Object-Orientation (00) is a new alternative focus that can be used for the analysis of reactor physics problems, ovecoming some of the limits of other methods. The key features of an 00 focus is that we can recognize and preserve the natural hierarchy of the entities conforming the problem as a rule with considerable advantage insofar as the mathematical treatment is concerned. The second part of this work shows how the 00 focus shifts attention from the tasks or procedures to the data, avoiding extra approximation, and highlighting the two basic classes of objects defining the problem: a set of functions, and related set of operators.
96/02711 Optimal geometry for fuel solution sloshing based on the boundary perturbation theory
190 Fuel and Energy Abstracts May 1996
Nuclear research reactors in the world
8th Edition, Reference Data Series No.3, IAEA, Wien, AS200.00, 1995, /32 pp.
Yamamoto. T. and Basoglu, B. Ann. Nuc/. Energy, Oct. 1995, 22, (10), 649-658. Describes the development of a method which obtains an optimal geometry maximizing K'ff due to deformation of fuel solution sloshing.
96/02694
Defuelling PFR
Nuclear Engineering Int., Mar. 1996, 41, (500), 21-22. Reports that when the Prototype Fast Reactor (PFR) located at Dounreay on the north coast of Scotland, ceased operation on 31 March 1994, it still contained almost 1/3 of the total number of sub-assemblies that had been through the 250 MWe reactor over its 20 year lifetime. To carry out the defuelling, which was completed in October 1995, ahead of schedule, AEA Technology had to take particular care to prevent any possibility of a criticality incident while achieving the quickest and most cost effective sequence for fuel removal possible.
96/02695 Design of particle bed reactors for the space nuclear thermal propulsion program Ludewig, H. et al., Progress in Nuclear Energy, 1996, 30, (1), 1-65. Describes the design for the particle bed reactor that the authors considered for the space nuclear thermal propulsion programme. The methods of analysis and their validation are outlined first. Monte Carlo methods were used for the physics analysis, several new algorithms were developed for the fluid dynamics, heat transfer and transient analysis, and commercial codes were used for the stress analysis.
96/02696 Diffusion theory methods for spatial kinetics calculations Sullon, T. M. and Aviles, B. N. Progress in Nuclear Energy, 1996, 30, (2), 119-182. Discusses the methods for solving the time-dependent neutron diffusion equation for nuclear reactor analysis. Techniques for treating the spatial variables, as well as techniques for performing the time integration, are described. A major advance made in the treatment of the spatial variables over the past 20 years has been the development of the transverse-integrated class of nodal methods, and thus these methods are described in considerable detail. Finally, results for selected standard benchmark problems that have been obtained using a variety of spatial kinetics rnethods are compared.
96/02697 Disposition of spent nuclear fuel using the modular helium reactor Richards, M. B. Energy, Apr. 1996,21, (4), 333-341. Unprocessed light water reactor (LWR) spent fuel may prove to be an unacceptable waste form for permanent geologic disposal because of serious technical and programmatic issues related to long-term proliferation risks and safeguards requirements, to long-term containment of radionuclides, and to undergound criticality. An alternative strategy using Modular Helium Reactors (MHRs) and coated-particle fuel technology would deal effectively with these issues, while generating significant revenues from the sale of electricity and demonstrating a meltdown-proof, advanced reactor design for future energy needs. The paper was submitted as a comment to the U.S. Department of Energy for determining the scope and content of the Environmental Impact Statement for the proposed Yucca Mountain geologic repository.
96/02698 studies
EFCC lobbies EC to fund East European fuel cycle
Barrett, R. Nuclear Engineering Int., Apr. 1996, 41, (501), p. 41. The European Fuel Cycle Consortium (EFCC) was formed by five West European countries in July 1993 to advise and assist the European Commission in the key areas of environmental and safety concern relating to Eastern Europe's fuel cycle plants and management of irradiated fuel. What has it achieved since it formed?
96/02699 The effect of strong anisotropic scattering on the critical sphere problem in neutron transport theory using a synthetic kernel Yildiz, C. and Alcan, E. Ann. Nucl. Energy, Oct. 1995,22, (10), 671-679. The effect of strong anisotropic scattering law on the variation of the critical radius in one-speed neutron transport theory is studied using a synthetic kernal. Numerical results for the critical radius are obtained and tabulated for selected illustrative cases. The results indicate that low-order Legendre approximation are sufficient to show the effect of anisotropic scattering on the variation of the critical radius.
96/02701
Evolutionary PWR constructed in 64 months
MPS, Modern Power Systems, Dec. 1995, 15, (12), 43, 45-46. Reports that at the end of March 1994, Yonggwang Unit 3 (Korea) entered commercial operation. The first-of-a-kind 1000 MW PWR, together with Yonggwang Unit 4, forms the basis of one of the most active nuclear construction programmes in the world. Construction lasted just 64 months.
96/02702 Grouping of HLW in partitioning for BIT (burning and/or transmutation) treatment with neutron reactors based on three criteria Kitamoto, M. and Kitamoto, A. Ann. Nucl. Energy, Nov. 1995,22, (11), 697-709. A grouping concept of HLW in partitioning for BIT (burning and/or transmutation) treatment by fission reactor was developed in order to improve the disposal in waste management from the safety aspect is described.
96/02703
Holtec International. HI-STAR and HI-STORM
Pennington, C. W. Nuclear Engineering Int., Apr. 1996,41, (501), p. 38. Describes the HI-STAR 100 and the HI-STORM 100 system for storage and transportation of spent fuels.
96/02704
How to move forward with the Alliance proposal
Ewart, F. Nuclear Engineering Int., Apr. 1996, 41, (501), p. 29. A short report on the study carried out by the European consortium 'Alliance' into the design of a new containment for the destroyed fourth reactor at Chernobyl.
96/02705
Lasers light the way
Nuclear Engineering lnt., Mar. 1996, 41, (500), p. 28. Reports that with the start of the campaign at Farley 2 in April 1992, Westinghouse has now put into service over 30,000 laser welded sleeves in six nuclear power plants.
96/02706 Light ion driven inertial confinement fusion Quintenz, J. P. et al., Progress in Nuclear Energy, 1996,30, (2), 183-242. Inertial Confinement Fusion (ICF) driven by intense beams of light ions offers the possibility for high gain target implosions. High gain implosions will be required to meet the United States' defense applications for rCF as well as to make an Inertial Fusion Energy (IFE) power plant an economically viable option for energy production in the 21st century. Progress in understanding the generation and focusing of intense light ion beams has resulted in record beam intensities. These beams have been used to heat the first ion-driven hohlraurns to provide favourable answers to key questions about the interation of these beams with matter. Describes the present state of the light ion ICF programme, its current limitations, and the prognosis for future advances. A successful research programme would lead to a commercially attractive fusion power plant.
96/02707 Mixed Oxide Fuel (MOX) exploitation and destruction in power reactors Proc. of the NATO Advanced Research Workshop, Obninsk, Russia, 16-19 Oct. 1994, Kluwer Academic Publishers Group, Dordrecht, $160.00, 1995.
96/02708 Modelling of fisson product release by re-entralnment due to bursting bubbles Unger, H. et al., Kerntechnik, Feb. 1996, 61, (1), 16-21. In the framework of nuclear safety analyzes, the code RESUS is being developed for the prediction of the release of droplets and low volatile radionuclides due to bubble bursting at liquid surfaces. The code consists of three independent submodules, each simulating important submechanisms of droplet generation. The mechanistic models are explained and results of RESUS calculations are presented. Profiles of bubbles resting at a phase interface are discussed in some detail. There is good agreement between calculated and experimentally observed shapes given in the literature.
96/02709
Nuclear power reactors in the world
15th Edition, Reference Data Series No.2, IAEA, Wien, AS.140.00, 1995, 78 pp.
96/02700 Error estimators and adaptlvity for the neutron diffusion problem
96/02710
Jatuff, F. E. Ann. Nucl. Energy, Dec. 1995,22, (12), 775-786. Object-Orientation (00) is a new alternative focus that can be used for the analysis of reactor physics problems, ovecoming some of the limits of other methods. The key features of an 00 focus is that we can recognize and preserve the natural hierarchy of the entities conforming the problem as a rule with considerable advantage insofar as the mathematical treatment is concerned. The second part of this work shows how the 00 focus shifts attention from the tasks or procedures to the data, avoiding extra approximation, and highlighting the two basic classes of objects defining the problem: a set of functions, and related set of operators.
96/02711 Optimal geometry for fuel solution sloshing based on the boundary perturbation theory
190 Fuel and Energy Abstracts May 1996
Nuclear research reactors in the world
8th Edition, Reference Data Series No.3, IAEA, Wien, AS200.00, 1995, /32 pp.
Yamamoto. T. and Basoglu, B. Ann. Nuc/. Energy, Oct. 1995, 22, (10), 649-658. Describes the development of a method which obtains an optimal geometry maximizing K'ff due to deformation of fuel solution sloshing.