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Japan Nuclear Energy Safety Organization | 論文
- Development of Thermodynamic Database for U-Zr-Fe-O-B-C-FPs System
- Experimental and Numerical Study of Liquid Metal Boiling in a System of Parallel Bundles under Natural Circulation Conditions
- Analysis of Measured Isotopic Compositions of High-Burnup BWR MOX Fuel
- Neutronics Analysis of Full MOX BWR Core Simulation Experiments FUBILA
- Effect of the Major Parameters on Pu Accumulation Predicted Using Several Numerical Codes for PUREX Solvent Extraction Process
- Analysis of Core Physics Experiments on Fresh and Irradiated PWR UO_2 Fuels in the REBUS Program
- Experiment and Modeling for Solvent Leaching from Paint Matrix Considering Equilibrium
- The late Professor Takahiro Hagiwara : His career with earthquake prediction
- Effect of Pu-Rich Agglomerate in MOX Fuel on a Lattice Calculation
- Thermodynamic Analysis for Molten Corium Stratification Test MASCA with Ionic Liquid U-Zr-Fe-O-B-C-FPs Database
- Thermal-Hydraulic Analysis for Inversely Stratified Molten Corium in Lower Vessel
- Research Program to Elucidate Outside-in Failure of High Burnup Fuel Cladding
- Correlation among FBR core characteristics for various fuel compositions
- 原子力安全確保のための課題について(安全安心社会の実現〜現在の取り組みと将来への道標〜)
- Statistical Safety Evaluation of BWR Turbine Trip Scenario Using Coupled Neutron Kinetics and Thermal Hydraulics Analysis Code SKETCH-INS/TRACE5.0
- 原子力安全確保のための課題について
- Analysis of SHE critical experiments by neutronic design codes for experimental very high temperature reactor.
- Integrated On-line Plant Monitoring System for HTTR with Neural Networks