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Institute of Nuclear Technology Articles

Research on Reliability Management Systems for Nuclear Power Plant
Analysis of Thermal Fatigue Events in Light Water Reactors
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
The Design of Advanced Generation of Event-base Emergency Operating Procedures

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