Enhancement of Cesium Release from Irradiated Fuel at Temperature above 2,800 K
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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
- 2002-03-25
著者
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NAKAMURA Takehiko
Japan Atomic Energy Agency
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Hidaka A
Japan Atomic Energy Res. Inst. Ibaraki
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Hidaka Akihide
Department Of Reactor Safety Research Japan Atomic Energy Researth Institute
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Hidaka Akihide
Japan Atomic Energy Research Institute
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Kudo Tamotsu
Japan Atomic Energy Agency
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Kudo Tamotsu
Japan Atomic Energy Research Institute
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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 Takehiko
Department of Reactor Safety Research, Japan Atomic Energy Research Institute
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Uetsuka H
Department Of Reactor Safety Research Japan Atomic Energy Research Institute
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Hidaka Akihide
Japan Atomic Energy Agency
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Nakamura Takehiko
Japan Atomic Energy Research Institute
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Nakamura Takehiko
Department Of Reactor Safety Research Japan Atomic Energy Research Institute
関連論文
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- Effect of Microstructure on Failure Behavior of Light Water Reactor Coolant Piping under Severe Accident Conditions
- Vapor Condensation and Thermophoretic Aerosol Deposition of Cesium Iodide in Horizontal Thermal Gradient Pipes
- Enhancement of CsI Aerosol Size in Superheated Steam in Reactor Piping under Severe Accidents
- Experimental and Analytical Study on the Behavior of Cesium Iodide Aerosol/Vapor Deposition onto Inner Surface of Pipe Wall under Sever Accident Conditions
- 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
- SCDAP/RELAP5 Analysis of Station Blackout with Pump Seal LOCA in Surry Plant
- 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
- Outcome of VEGA Program on Radionuclide Release from Irradiated Fuel under Severe Accident Conditions
- Irradiated Fuel Behavior under Power Oscillation Conditions
- Behavior of YSZ based Rock-Like Oxide Fuels under Simulated RIA Conditions
- Rock-Like Oxide Fuels and Their Burning in LWRs
- Interhemispheric Chronic Subdural Hematoma : Case Report
- 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
- Optical Investigation of Fast Pulsed Discharge on Surface of Ceramics for Environmental Applications
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- Infrared Chemiluminescence Study of Excited CO_2 Produced by Molecular - Beam CO Oxidation on Pt(111)
- 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
- 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
- High Power Transient Characteristics and Capability of NSRR
- Irradiated Fuel Behavior under Power Oscillation Conditions
- Oxidation kinetics of Low-Sn Zircaloy-4 at the Temperature Range from 773 to 1, 573 K