Analyses of Burnup at plutonium Spots in Uranium-Plutonium Mixed Oxide Fuels in Light Water Reactors by Neutron Transport and Burnup Calculations
スポンサーリンク
概要
- 論文の詳細を見る
- Atomic Energy Society of Japanの論文
- 1997-06-25
著者
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SASAHARA Akihiro
Nuclear Technology Research Laboratory, Central Research Institute of Electric Power Industry
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MATSUMURA Tetsuo
Material Science Research Laboratory, Central Research Institute of Electric Power Industry
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Kameyama Takanori
Central Research Institute of Electric Power Industry
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Sasahara Akihiro
Nuclear Technology Research Laboratory Central Research Institute Of Electric Power Industry
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Sasahara Akihiro
Central Research Institute Of Electric Power Industry
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Matsumura Tetsuo
Material Science Research Laboratory Central Research Institute Of Electric Power Industry
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Matsumura Tetsuo
Central Research Institute Of Electric Power Industry
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Kameyama Takanori
Central Res. Inst. Of Electric Power Ind.
関連論文
- Chemical Isotopic Analysis of Fission Products in PWR-MOX Spent Fuels and Computational Evaluation Using JENDL, ENDF/B, JEF, and JEFF
- Development of Calculation Technique for Iterated Fission Probability and Reactor Kinetic Parameters Using Continuous-Energy Monte Carlo Method
- Analyses of Burnup at plutonium Spots in Uranium-Plutonium Mixed Oxide Fuels in Light Water Reactors by Neutron Transport and Burnup Calculations
- Isotopic Analysis of Actinides and Fission Products in LWR High-Burnup UO_2 Spent Fuels and its Comparison with Nuclide Composition Calculated Using JENDL, ENDF/B, JEF and JEFF
- Neutron and Gamma Ray Source Evaluation of LWR High Burn-up UO_2 and MOX Spent Fuels
- Development of Calculation Technique for Iterated Fission Probability and Reactor Kinetic Parameters Using Continuous-Energy Monte Carlo Method
- ICONE11-36273 CORE AND CORE-INTERNAL DESIGN FOR INTEGRATED MODULAR WATER REACTOR (IMR)
- Proposal of Direct Calculation of Kinetic Parameters β_ and Λ Based on Continuous Energy Monte Carlo Method