スポンサーリンク
Nuclear Safety Research Center, Japan Atomic Energy Agency | 論文
- Criticality Safety Benchmark Experiment on 10% Enriched Uranyl Nitrate Solution Using a 28-cm-Thickness Slab Core
- Effect of Cooling History on Cladding Ductility under LOCA Conditions
- Development of Safety Assessment Code for Decommissioning of Nuclear Facilities : (DecDose)
- In-pile Experiment in JMTR on the Radiation Induced Surface Activation (RISA) Effect on Flow-boiling Heat Transfer
- Effect of Correlations of Component Failures and Cross-Connections of EDGs on Seismically Induced Core Damages of a Multi-Unit Site
- 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
- Fluctuation of the Neutron Multiplication Factor Induced by an Oscillation of the Fuel Solution System
- Ring Compression Ductility of High-Burnup Fuel Cladding after Exposure to Simulated LOCA Conditions
- Ring Compression Ductility of High-Burnup Fuel Cladding after Exposure to Simulated LOCA Conditions
- A simple method for estimating the structure temperatures and the cesium revaporization inside the reactor pressure vessel (2) Feasibility study for the Fukushima Daiichi Nuclear Power Plant (Fukushima NPP Accident Related)
- Verification of FEMAXI-7 code by using irradiation test in Halden reactor for He-pressurization effect on FGR of BWR fuels under power transient
- A simple method for estimating the structure temperatures and the cesium revaporization inside the reactor pressure vessel : II : Feasibility study for the Fukushima Daiichi Nuclear Power Plant
- A simple method for estimating the structure temperatures and the cesium revaporization inside the reactor pressure vessel : I : Basic concepts and model descriptions for the Fukushima Daiichi Nuclear Power Plant
- Effect of Higher-Harmonic Flux in Exponential Experiment for Subcriticality Measurement
- Review of Five Investigation Committees' Reports on the Fukushima Dai-ichi Nuclear Power Plant Severe AccidentFocusing on Accident Progression and Causes
- A Water Radiolysis Code for the Irradiation Loop System