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Isogo Engineering Center, Toshiba Corp. | 論文
- Decision-Making Support Systems for Reliability-Centered Maintenance
- Safety Relief Valve Performance for Two-Phase Flow
- Development of Underwater Laser Cladding and Underwater Laser Seal Welding Techniques for Reactor Components
- Critical Power Experiments of Tight Fuel Rod Lattice for Light Water Reactors.
- Acceleration signal characteristics for loose part impact.
- Centrifugal pump behavior in steady and transient two-phase flow.
- Development of Computer Code SAFFRON for Evaluating Breached Pin Performance in FBR's.
- Boiling water reactor loss-of-coolant tests with two bundle loop. Examination of conservativeness for licensing analysis models using large break test data.:Examination of Conservativeness for Licensing Analysis Models Using Large Break Test Data
- Model-Based Temperature Noise Monitoring Methods for LMFBR Core Anomaly Detection.