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Institute of Nuclear Safety System | 論文
- Measurement of Leakage Neutron Spectra from a Spherical Pile of Zirconium Irradiated with 14MeV Neutrons and Validation of Its Nuclear Data
- Measurement of Leakage Neutron Spectra from a Spherical Pile of Niobium Bombarded with 14MeV Neutrons and Validation of Its Nuclear Data
- Numerical Simulation of Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels
- Segregation Behavior Induced by Various Particle Irradiations in Austenitic Stainless Steels
- Calculation of Gamma Induced Displacement Cross-sections of Iron Considering Positron Contribution and Using Standard Damage Model
- Development of Micro Tensile Testing Method in an FIB System for Evaluating Grain Boundary Strength
- Microstructural Characterization of SCC Crack Tip and Oxide Film for SUS 316 Stainless Steel in Simulated PWR Primary Water at 320℃
- Modeling and Validation of In-Vessel Debris Cooling during LWR Severe Accident
- Effects of Liquid Properties on CCFL in a Scaled-Down Model of a PWR Hot Leg
- Correlation for countercurrent flow limitation in a PWR hot leg
- Detection of Cavitation States with Microphone Placed Outside Pipe Components
- Influence of Local Flow Field on Flow Accelerated Corrosion Downstream from an Orifice
- Numerical Simulation of Water Temperature in a Spent Fuel Pit during the Shutdown of Its Cooling Systems
- Evaluation of Heat Loss and Water Temperature in a Spent Fuel Pit
- Calculation of Gamma Induced Displacement Cross-sections of Iron Considering Positron Contribution and Using Standard Damage Model
- One-Region Model Predicting Water Temperature and Level in a Spent Fuel Pit during Loss of All AC Power Supplies
- Correlation between Flow Accelerated Corrosion and Wall Shear Stress Downstream from an Orifice
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels