Host: The Japan Society of Mechanical Engineers
Name : [in Japanese]
Date : November 25, 2025 - November 29, 2025
As part of the fitness-for-service evaluation for Light Water Reactor structural components, evaluating crack growth due to the superposition of SCC (Stress Corrosion Cracking) and fatigue is sometimes required. However, it is difficult to predict the sequence in which the sustained loads that induce SCC crack growth and the cyclic loads that cause fatigue crack growth will be applied. This study investigates the influences of various loading sequences on crack growth using the SCC and fatigue crack growth evaluation equations specified in the JSME Codes for Nuclear Power Generation Facilities. Furthermore, it discusses how the loading sequence should be considered to ensure a conservative crack growth evaluation.
