ICONE11-36598 Conceptual Design of a Medium Scale Lead-Bismuth Cooled Fast Reactor
スポンサーリンク
概要
著者
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MIZUNO Tomoyasu
Japan Atomic Energy Agency
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Mizuno Tomoyasu
Japan Nuclear Cycle Development Institute
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Soman Yoshindo
Japan Nuclear Cycle Development Institute
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Tanji Mikio
Mitsubishi Heavy Industries Ltd.
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KONOMURA Mamoru
Japan Atomic Energy Agency (JAEA)
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ENUMA Yasuhiro
Japan Nuclear Cycle development institute, O-arai Engineering Center
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MITO Makoto
Advanced Reactor Technology Co., Ltd.
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Enuma Yasuhiro
Japan Nuclear Cycle Development Institute
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Mito Makoto
Advanced Reactor Technology Co. Ltd.
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Konomura Mamoru
Japan Nuclear Cycle Development Institute
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Konomura Mamoru
Japan Atomic Energy Agency
関連論文
- Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups
- Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups
- Progress on the Plant Design Concept of Sodium-Cooled Fast Reactor
- Irradiation Performance of Fast Reactor MOX Fuel Assemblies Irradiated to High Burnups
- ICONE11-36611 A comparative design study of Pb-Bi cooled reactor cores with forced and natural convection cooling
- ICONE11-36598 Conceptual Design of a Medium Scale Lead-Bismuth Cooled Fast Reactor
- A Case for Small Modular Fast Reactor
- Correlation among FBR core characteristics for various fuel compositions
- A Design Study of High Breeding Ratio Sodium Cooled Metal Fuel Core without Blanket Fuels