FUKETA Toyoshi | 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
Stress Intensity Factor at the Tip of Cladding Incipient Crack in RIA-Simulating Experiments for High-Burnup PWR Fuels
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
Evaluation of Initial Temperature Effect on Transient Fuel Behavior under Simulated Reactivity-Initiated Accident Conditions
Clad-to-Coolant Heat Transfer in NSRR Experiments
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
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
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
Hydrogen Generation during Cladding/Coolant Interactions under Reactivity Initiated Accident Conditions
Behavior of Pre-hydrided Zircaloy-4 Cladding under Simulated LOCA Conditions
Thermal Stress Analysis of High-Burnup LWR Fuel Pellet Pulse-Irradiated in Reactivity-Initiated Accident Conditions
Analysis of MOX Fuel Behavior in Halden Reactor by FEMAXI-6 Code
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
Influence of Cladding-Peripheral Hydride on Mechanical Fuel Failure under Reactivity-Initiated Accident Conditions
Effect of Cladding Surface Pre-oxidation on Rod Coolability under Reactivity Initiated Accident Conditions
RANNS Code Analysis on the Local Mechanical Conditions of Cladding of High Burnup Fuel Rods under PCMI in RIA-Simulated Experiments in NSRR
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
Influence of Hydride Re-orientation on BWR Cladding Rupture under Accidental Conditions

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