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Nuclear Engineering Laboratory, Toshiba Corp. | 論文
- Development of Molten Core Relocation Analysis Module MCRA in the Severe Accident Analysis Code SAMPSON
- Measurement of Electric-Dipole Moment by Polarization Laser Spectroscopy
- Measurement of Dipole-Moment in Atomic Transitions under Strong External Magnetic Field
- Optimization of Fuel Rod Enrichment Distribution to Minimize Rod Power Peaking throughout Life within BWR Fuel Assembly
- Decision-Making Support Systems for Reliability-Centered Maintenance
- Development of a Method for Evaluation of Pin-wise Power Distribution in Fuel Assemblies of Fast Reactors
- Thermal Hydraulic Behavior in Upper Plenum during Refill-Reflood Phase of BWR LOCA, (II) : Characteristics of Residual Two-Phase Pool in Upper Plenum
- Calculation of gamma-ray production cross sections at neutron energies of 1-20 MeV.
- Protective Oxide Film on Alloy X750 Formed in Air at 973K.
- General Corrosion of Materials under Simulated BWR Primary Water Conditions.
- Electrochemical Considerations Regarding General Corrosion of Materials in a BWR Primary Circuit.
- Nuclear Power Plant Operator Performance Analysis Using Training Simulators. Operator Performance under Abnormal Plant Conditions.:Operator Performance under Abnormal Plant Conditions
- A Finite Element Method for Contact Problems between Three-Dimensional Curved Bodies
- Proton irradiation creep of zirconium.
- Two-phase flow phenomena in broken recirculation line of BWR.
- Development of Computer Code SAFFRON for Evaluating Breached Pin Performance in FBR's.
- Basic Studies on Neutron Emission-Rate Method for Burnup Measurement of Spent Light-Water-Reactor Fuel Bundle.
- Fuel Pin and Subassembly Heterogeneity Effects on Burnup Characteristics in Large Fast Breeder Reactors.
- Development of reflux vapor trap for sodium cooled fast breeder reactor. (I). Basic performance tests.:Basic Performance Tests
- Investigation of effect of gas release on coolability of locally blocked LMFBR fuel subassemblies.