NAGASE Fumihisa | 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
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
Fracture Behavior of Irradiated Zircaloy-4 Cladding under Simulated LOCA Conditions
Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions
Behavior of 60 to 78MWd/kgU PWR Fuels under Reactivity-Initiated Accident Conditions
Behavior of Pre-hydrided Zircaloy-4 Cladding under Simulated LOCA Conditions
Investigation of Hydride Rim Effect on Failure of Zircaloy-4 Cladding with Tube Burst Test
Influence of Hydride Re-orientation on BWR Cladding Rupture under Accidental Conditions
Effect of Pre-Hydriding on Thermal Shock Resistance of Zircaloy-4 Cladding under Simulated Loss-of-Coolant Accident Conditions
Effect of Cooling History on Cladding Ductility under LOCA Conditions
Oxidation kinetics of Low-Sn Zircaloy-4 at the Temperature Range from 773 to 1, 573 K
B_4C/Zircaloy Reaction at Temperatures from 1, 173 to 1, 953 K
Oxidation kinetics of Low-Sn Zircaloy-4 at the Temperature Range from 773 to 1, 573 K
Influence of Hydride Re-orientation on BWR Cladding Rupture under Accidental Conditions

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