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Department of Reactor Safety Research, Japan Atomic Energy Researth Institute | 論文
- 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
- Intramembrane Signaling Mediated by Hydrogen-Bonding of Water and Carboxyl Groups in Bacteriohodopsin and Rodopsin^1
- 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
- Natural Convection Heat Transfer in the Horizontal Dry Storage System for the LWR Spent Fuel Assemblies
- Irradiation Behavior of Large Grain UO_2 Fuel Rod by Active Powder