Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups
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概要
- 論文の詳細を見る
- 2010-08-01
著者
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Uwaba Tomoyuki
Japan Atomic Energy Agency
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Sogame Motomu
Japan Atomic Energy Agency
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Ito Masahiro
Japan Atomic Energy Agency
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MIZUNO Tomoyasu
Japan Atomic Energy Agency
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DONOMAE Takako
Japan Atomic Energy Agency
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KATSUYAMA Kozo
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
- Reduction in Degree of Absorber-Cladding Mechanical Interaction by Shroud Tube in Control Rods for the Fast Reactor
- Irradiation Performance of Fast Reactor MOX Fuel Assemblies Irradiated to High Burnups
- Development of a FBR Fuel Bundle-duct Interaction Analysis Code-BAMBOO Analysis Model and Verification by Phenix High Burn-up Fuel Subassemblies
- 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
- Retention and Release of Tritium in B_4C Irradiated as Control Rod of Fast Breeder Reactor
- Reduction in Degree of Absorber-Cladding Mechanical Interaction by Shroud Tube in Control Rods for the 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