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Nuclear Safety Research Center, Japan Atomic Energy Agency | 論文
- Identification of Radial Position of Fission Gas Release in High-Burnup Fuel Pellets under RIA Conditions
- Optimized Ring Tensile Test Method and Hydrogen Effect on Mechanical Properties of Zircaloy Cladding in Hoop Direction
- Behavior of High Burn-up Fuel Cladding under LOCA Conditions
- Thermal Conductivity Change in High Burnup MOX Fuel Pellet
- Benchmark Critical Experiments and FP Worth Evaluation for a Heterogeneous System of Uranium Fuel Rods and Uranium Solution Poisoned with Pseudo-Fission-Product Elements
- Nuclear Criticality Safety Evaluation of a Mixture of MOX, UO_2 and Additive in the Most Conservative Concentration Distribution
- Measurement of Neutron Dose under Criticality Accident Conditions at TRACY Using TLDs
- Evaluation of Containment Failure Probability by Ex-Vessel Steam Explosion in Japanese LWR Plants
- Real Time α Value Measurement with Feynman-α Method Utilizing Time Series Data Acquisition on Low Enriched Uranium System
- Kinetic Parameter β_/l Measurement on Low Enriched Uranyl Nitrate Solution with Single Unit Cores (600φ, 280T,800φ) of STACY
- REIDAC : A Software Package for Retrospective Dose Assessment in Internal Contamination with Radionuclides
- 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
- ROSA/AP600 Testing : Facility Modifications and Initial Test Results
- A New Importance Measure for Sensitivity Analysis
- Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions
- Small-scale Experiment on Subcooled Water Jet Injection into Molten Alloy by Using Fluid Temperature-Phase Coupled Measurement and Visualization
- Benchmark Critical Experiments of a Heterogeneous System of Uranium Fuel Rods and Uranium Solution Poisoned with Gadolinium, and Application of Their Results to JACS Validation
- Fission Gas Release in BWR Fuel with a Burnup of 56GWd/t during Simulated Reactivity Initiated Accident (RIA) Condition
- Behavior of 60 to 78MWd/kgU PWR Fuels under Reactivity-Initiated Accident Conditions