Effects of pressurized water reactor environment and cyclic loading parameters on the low cycle fatigue behavior of 304L stainless steel

Aleks Vainionpää, Tommi Seppänen, Zaiqing Que (Corresponding Author)

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Abstract

Austenitic stainless steels used in light water reactor coolant environments are susceptible to environmentally assisted fatigue due to non-monotonic loading conditions, primarily associated with load-follow, thermal transients, or intermittent plant shutdowns and start-ups. This study investigates the effects of a high-temperature pressurized water reactor (PWR) water environment and cyclic loading parameters on the low cycle fatigue behavior of austenitic 304L stainless steel. Prolonged exposure to a PWR environment and cyclic loading conditions such as a lower strain rate or a higher fraction of slow strain rate enhances the initiation and accelerates the crack growth rate of fatigue cracks, resulting in decreased fatigue life. The deformation-induced α'-martensite is observed in proximity to fatigue crack tips primarily in specimens tested in simulated PWR primary water, while cellular dislocation structures are more frequently observed near crack tips in specimens tested in high-temperature air. The deformation-induced martensitic transformation from γ-austenite to α'-martensite, occurring via the precursor ε-martensite phase, contributes to the accelerated fatigue crack growth rate in a PWR environment with hydrogen.
Original languageEnglish
Article number108231
JournalInternational Journal of Fatigue
Volume182
DOIs
Publication statusPublished - May 2024
MoE publication typeA1 Journal article-refereed

Funding

This study has received funding from VTT and partly from Finnish SAFIR2028 (National Nuclear Safety and Waste Management Research Programme 2023-2028) LOAD project (Long-term Operation on Aging and environmental Degradation of nuclear reactor materials) and the Euratom research and training program 2019–2020 under grant agreement No 945300 (INCEFA-SCALE). Part of the specimens were from the Finnish Research Programme on Nuclear Power Plant Safety projects SAFIR 2022 FEVAS and SAFIR 2018 FOUND.

Keywords

  • Austenitic stainless steel
  • Deformation-induced martensitic transformation
  • Environmentally assisted fatigue
  • Low cycle fatigue
  • Pressurized water reactor

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