Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels

Abstract

A statistical model for austenitic stainless steels for predicting the effect of pressurized water reactor (PWR) environments on fatigue life for a range of temperatures and strain rates is developed based on analysis of available material data from USA, Europe, and Japan. Only fatigue data from polished specimens of wrought material tested under strain control were considered. Hollow specimens were not treated in the final calculations. The fatigue life correction factors were defined as the ratio of life in water at 300 °C (572 °F) (reference conditions) to that in water at service conditions. The model is recommended for predicting fatigue lives that are 103–105 cycles.