Ring Compression Ductility of High-Burnup Fuel Cladding after Exposure to Simulated LOCA Conditions
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概要
- 論文の詳細を見る
- 2011-11-01
著者
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CHUTO Toshinori
Japan Atomic Energy Agency
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Fuketa T
Japan Atomic Energy Agency
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NAGASE Fumihisa
Nuclear Safety Research Center, Japan Atomic Energy Agency
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FUKETA Toyoshi
Nuclear Safety Research Center, Japan Atomic Energy Agency
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Chuto Toshinori
Nuclear Safety Research Center Japan Atomic Energy Agency
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Nagase Fumihisa
Nuclear Safety Research Center Japan Atomic Energy Agency
関連論文
- Identification of Radial Position of Fission Gas Release in High-Burnup Fuel Pellets under RIA Conditions
- Optimized Ring Tensile Test Method and Hydrogen Effect on Mechanical Properties of Zircaloy Cladding in Hoop Direction
- Behavior of High Burn-up Fuel Cladding under LOCA Conditions
- Thermal Conductivity Change in High Burnup MOX Fuel Pellet
- Radionuclide Release from Mixed-Oxide Fuel under High Temperature at Elevated Pressure and Influence on Source Terms
- Proposal of Simplified Model of Radionuclide Release from Fuel under Severe Accident Conditions Considering Pressure Effect
- Effects of Fuel Oxidation and Dissolution on Volatile Fission Product Release under Severe Accident Conditions
- Releases of Cesium and Poorly Volatile Elements from UO_2 and MOX Fuels under Severe Accident Conditions
- Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions
- Fission Gas Release in BWR Fuel with a Burnup of 56GWd/t during Simulated Reactivity Initiated Accident (RIA) Condition
- Measurements of Crystal Lattice Strain and Crystallite Size in Irradiated UO_2 Pellet by X-ray Diffractometry
- Behavior of 60 to 78MWd/kgU PWR Fuels under Reactivity-Initiated Accident Conditions
- Fission Gas Release in Irradiated UO_2 Fuel at Burnup of 45GWd/t during Simulated Reactivity Initiated Accident (RIA) Condition
- Failure Thresholds of High Burnup BWR Fuel Rods under RIA Conditions
- Behavior of Irradiated ATR/MOX Fuel under Reactivity Initiated Accident Conditions
- Fission Gas Release Behavior of High Burnup UO_2 Fuel under Reactivity Initiated Accident Conditions
- Fission Gas Induced Cladding Deformation of LWR Fuel Rods under Reactivity Initiated Accident Conditions
- Hydrogen Generation during Cladding/Coolant Interactions under Reactivity Initiated Accident Conditions
- Effect of Cooling History on Cladding Ductility under LOCA Conditions
- Ring Compression Ductility of High-Burnup Fuel Cladding after Exposure to Simulated LOCA Conditions
- Ring Compression Ductility of High-Burnup Fuel Cladding after Exposure to Simulated LOCA Conditions