INSS JOURNAL7 2000
Institute of Social Research Articles
- Study on the Improvement of Working Environment at Night in Maintenance Works at Nuclear Power Plants
- Causal Model of Safety-checking Action of the Staff of Nuclear Power Plants and the Organizational Climate
- Research on People's Attitudes Caused by the Difference of the Refuse Collection Rule
- Effects of the Criticality Accident at Tokai - mura on the Public's Attitude to Nuclear Power Generation
- Public Opinion about Nuclear Power Generation and Its Formation Factors after the JCO Accident
- A Study on the Image of Leaders in charge of Negotiation and Construction of NIMBY Facilities
Institute of Nuclear Technology Articles
- Research on Reliability Management Systems for Nuclear Power Plant
- Microstructural Evolution in Reactor Pressure Vessel Steel under Neutron Irradiation
- Microstructural Evolution in Reactor Pressure Vessel Steel under Neutron Irradiation
- Study of 316 Stainless Steel Swelling Due to Neutron Irradiation
- Swelling of SUS 304 and SUS 316 Stainless Steels under Heavy Ion Irradiation
- Research on Crack Growth Rate of Primary Water Stress Corrosion Cracking （PWSCC）of MA600 Alloy
- Development of Crack Propagation Simulation Model Considering the Interaction of Multiple Cracks
- Study on Thermal Aging Mechanism of Cast Duplex Stainless Steel
- Development of Ultrasonic Inspection Techniques for Cast Stainless Steel
- Non-Destructive Evaluation of Thermal Aging of Cast Duplex Stainless Steel
- Estimation of Residual Stress Distribution of Alloy600/SUS304 Dissimilar Weld Joint
- Flow-induced Vibration of a Circular Cylinder
- Corrective Actions to Gas Accumulation in Safety Injection System Pipings of PWRs and Gas Void Detection Method
- Relationship between Pressure and the Amount of Leak from a Check Valve when jammed with Foreign Objects
- Development of Method for Detecting Signs Deterioration in Insulator of High-Voltage Motors（2） －Test Results of a New On-line Partial Discharge Monitor for High- Voltage Motors in Nuclear Power Stations－
- Evaluation of Nuclear Power Plant Component Failure Probability and Core Damage Probability using Simplified PSA Model
- Study on Communicating Risk Information Obtained from PSA Within Nuclear Power Plants
- Study on the Methodology for Predicting and Preventing Errors to Improve Reliability of Maintenance Task in Nuclear Power Plant 花
- The Design of Advanced Generation of Event-base Emergency Operating Procedures