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Nuclear Power Engineering Corporation | 論文
- Analysis on Pipe Rupture of Steam Condensation Line at Hamaoka-1, (II) Hydrogen Combustion and Pipe Deformation
- Analysis on Pipe Rupture of Steam Condensing Line at Hamaoka-1, (I) Accumulation of Non-condensable Gas in a Pipe
- Severe Accident Analysis Code SAMPSON Improvement for IMPACT Project(Special Issue on International Conference on Power and Energy System)
- ICONE11-36048 Development of Boiling Transition Analysis Code TCAPE-INS/B based on Mechanistic Methods for BWR Fuel Bundles : Models and verification with the boiling transition experimental data
- The Multi-Fluid Multi-Phase Subchannel Analysis Code KAMUI for Subassembly Accident Analysis of an LMFR
- ICONE11-36086 DEVELOPMENT OF RECYCLING TECHNIQUES FOR NUCLEAR POWER PLANT DECOMMISSIONING WASTE USING DROSS-FILLED PACKAGING TECHNIQUE
- ICONE11-36480 The Technical Development on Residual Radioactivity Measurement during Decommissioning
- Analysis of International Standard Problem No. 45, QUENCH06 Test as FZK by Detailed Severe Accidents Analysis Code, IMPACT/SAMPSON
- Void Fraction Distribution in BWR Fuel Assembly and Evaluation of Subchannel Code.
- Comparison of sodium evaporations measured under condition of fog formation.
- A Water Radiolysis Code for the Irradiation Loop System