NAGASE Fumihisa | Nuclear Safety Research Center, Japan Atomic Energy Agency

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概要

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著作論文

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
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
Behavior of 60 to 78MWd/kgU PWR Fuels 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

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