Fission Gas Release Behavior of High Burnup UO_2 Fuel under Reactivity Initiated Accident Conditions
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概要
- 論文の詳細を見る
- 社団法人 日本原子力学会の論文
- 1999-11-25
著者
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FUKETA Toyoshi
Japan Atomic Energy Agency
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SASAJIMA Hideo
Japan Atomic Energy Agency
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Uetsuka Hiroshi
Surface Chemistry Laboratory Kanagawa Academy Of Science And Technology Ksp East 404
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Uetsuka Hiroshi
Japan Atomic Energy Research Institute
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Uetsuka Hiroshi
Institute Of Materials Science University Of Tsukuba
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Uetsuka Hiroshi
Department Of Reactor Safety Research Japan Atomic Energy Research Institute
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Nakamura Jinichi
Department Of Reactor Safety Research Japan Atomic Energy Research Institute
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Fuketa T
Japan Atomic Energy Agency
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Uetsuka H
Department Of Reactor Safety Research Japan Atomic Energy Research Institute
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NAKAMURA Jinichi
Japan Atomic Energy Research Institute
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Nakamura Junichi
Japan Atomic Energy Research Institute
関連論文
- 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
- Thermal Conductivity Change in High Burnup MOX Fuel Pellet
- Evaluation of Initial Temperature Effect on Transient Fuel Behavior under Simulated Reactivity-Initiated Accident Conditions
- Oxidation of Fuel Rod under Dry Storage Condition
- 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
- Irradiated Fuel Behavior under Power Oscillation Conditions
- Behavior of YSZ based Rock-Like Oxide Fuels under Simulated RIA Conditions
- Decrease of Cesium Release from Irradiated UO_2 Fuel in Helium Atmosphere under Elevated Pressure of 1.0 MPa at Temperature up to 2,773K
- Enhancement of Cesium Release from Irradiated Fuel at Temperature above 2,800 K
- Influence of Pressure on Cesium Release from Irradiated Fuel at Temperatures up to 2,773K
- Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions
- Noncontact-Mode Atomic Force Microscopy Observation of α-Al_2O_3(0001) Surface
- Scanning Tunneling Microscopy Study of Surface Reconstructions of Rutile TiO_2(111)
- Structure-sensitivity of the Dynamics of CO Oxidation on Pd (111), Pd (110) and Polycrystalline Pd Surfaces : Infraed Chemiluminescence Study of the Product CO_2
- Infrared Chemiluminescence Study of Excited CO_2 Produced by Molecular - Beam CO Oxidation on Pt(111)
- 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
- 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
- Atomic Force Microscope Topography of Nickel-Affected MoS_2 Model Catalysts
- CO_2 Sensing Properties of La-loaded SnO_2 Thin Films Prepared by Sputtering
- 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
- Influence of Precipitated Hydride on the Fracture Behavior of Zircaloy Fuel Cladding Tube
- Ring Compression Ductility of High-Burnup Fuel Cladding after Exposure to Simulated LOCA Conditions
- Irradiated Fuel Behavior under Power Oscillation Conditions
- 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
- Irradiation studies of JAERI's fuel at Halden Reactor.