SCDAP/RELAP5 Analysis of Station Blackout with Pump Seal LOCA in Surry Plant
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概要
- 論文の詳細を見る
- 1995-06-25
著者
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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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SUGIMOTO Jun
Severe Accident Research Laboratory, Japan Atomic Energy Research Institute
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HIDAKA Akihide
Sever Accident Research Laboratory, Department of Reactor Safety Research, Japan Atomic Energy Resea
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SODA Kunihisa
Sever Accident Research Laboratory, Department of Reactor Safety Research, Japan Atomic Energy Resea
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Sugimoto J
Japan Atomic Energy Res. Inst.
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Sugimoto Jun
Severe Accident Research Laboratory Department Of Reactor Sefety Research Japan Atomic Energy Resear
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Soda Kunihisa
Sever Accident Research Laboratory Department Of Reactor Safety Research Japan Atomic Energy Researc
関連論文
- Numerical Analysis of Jet Injection Behavior for Fuel-Coolant Interaction using Particle Method
- Evaluation of High Temperature Tensile and Creep Properties of Light Water Reactor Coolant Piping Materials for Severe Accident Analyses
- 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
- Analysis of WITCH/LINER Experiments on Heat Transfer between Gas-agitated Steel Melt and Vertical Wall
- 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
- 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