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Institute of Nuclear Technology Articles

Analysis of High Performance and Events & Incidents in Nuclear Power Plants in the United States of America
Database Construction Using Hyperlink of Reliability Block Diagram and Operating Experiences of Emergency Diesel Generators for Nuclear Power Plants
A Study on the Method for Estimating the Life Time of O-Rings Made of NBR Used in Sealing Air Operating Cylinders
Evaluation of Deterioration of Insulators in High-Voltage Motors by Partial Discharge
Investigation of Evaluation Method of Cavitation Behavior by an Accelerometer Mounted on Outer Surface of Piping
Influence of Grain Boundary Sliding and Carbide Precipitation on IGSCC Susceptibility of SUS 316 under Hydrogenated High Temperature Water
Influence of Temperature on Primary Water Stress Corrosion Cracking of Alloy 600 Weld Metals
Influence of Thermal Aging on Primary Water Stress Corrosion Cracking of Cast Duplex Stainless Steel (Second Report) ― Consideration on Fractography after Slow Strain Rate Technique ―
Analysis of IGSCC Crack Tip and Oxide Film on SUS 316 Generated under High Temperature Water
Material Property Changes During Post-Irradiation Annealing and Their Effects on IASCC
A Simulation on Growth of Multiple Small Cracks under Stress Corrosion
Microstructural Evolution in A533B Steels under Electron Irradiation
Influence of Crystal Structure on Ultrasonic Incident Angle and Defect Detection Sensitivity for Ultrasonic Inspection of Cast Stainless Steel
Estimation of Charpy Notch Toughness for Thermal Aging Specimens of Cast Duplex Stainless Steel Using Thermalelectric Power Measurement
Study on Effectiveness Evaluation of Severe Accident Management
Improvement of Dose Evaluation Method for Employees at Severe Accident
Analysis to Verify Effectiveness of Alternative Cooling Method in Case of Loss of RHR Function during Mid-Loop Operation

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