スポンサーリンク
Department Of Reactor Safety Research Japan Atomic Energy Research Institute | 論文
- Oxidation of Fuel Rod under Dry Storage Condition
- 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
- 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
- Probabilistic Fracture Mechanics Analyses of Reactor Pressure Vessel under PTS Transients
- ICONE11-36081 PROBABILISTIC FRACTURE MECHANICS ANALYSES OF RPV UNDER SOME PTS TRANSIENTS
- Sensitivity Analysis of Failure Probability on PTS Benchmark Problems of Pressure Vessel Using a Probabilistic Fracture Mechanics Analysis Code
- 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 Irradiated UO_2 Fuel at Burnup of 45GWd/t during Simulated Reactivity Initiated Accident (RIA) Condition
- 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
- Mechanical Energy Generation during High Burnup Fuel Failure under Reactivity Initiated Accident Conditions
- Effect of Absorbed Hydrogen on the Stress Corrosion Cracking (SCC) Susceptibility of Unirradiated Zircaloy Cladding
- Crack Opening Area of Pressurized Pipe for Leak-before-Break Evaluation