Austenitic stainless steels are widely used in the internals of pressurised water reactors (PWRs) due to their good mechanical properties and corrosion resistance. However, when exposed to a simulated PWR environment they can exhibit a significant enhancement of fatigue crack growth rates (FCGRs) compared to specimens tested in air. This study is separated into two parts; with the first part focused on the analysis of specimens subjected to more plant realistic waveforms. Comparisons of different methods to evaluate crack growth rates (CGRs) highlighted a 1:1 relationship between striation spacing and CGRs, which gives confidence in this method to be used on specimens where in-situ crack monitoring is not practical. The second part of the work was focused on the effect of temperature on fatigue in a simulated PWR environment, with a particular focus on temperatures less than 150 °C. The crack growth results highlighted a difference in fatigue behaviour above and below 150 °C, with an ‘upturn’ in the CGR below 150 °C. Microstructural analysis showed that α’-martensite formed in crack growth stages conducted at low temperatures (T
- EAF
- Corrosion Fatigue
- Fatigue
- Stainless Steel
Mechanistic Studies of Fatigue in Austenitic Stainless Steels in a Pressurised Water Reactor Primary Coolant
Howe, B. (Author). 9 Aug 2024
Student thesis: Phd