About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Transmutation Effects in Fusion Reactor Materials: Critical Challenges & Path Forward
|
Presentation Title |
Critical Evaluation of High Temperature Helium Embrittlement Phenomena in Structural Materials |
Author(s) |
Steven J. Zinkle, Zehui Qi, Arunodaya Bhattacharya |
On-Site Speaker (Planned) |
Steven J. Zinkle |
Abstract Scope |
Ductility reductions associated with growth of grain boundary cavities in mechanically strained He-containing materials at high temperatures (HTHE) is widely recognized as a serious issue in reactor structural materials. Extensive HTHE studies have been performed on austenitic stainless steels and provide a good mechanistic understanding of the importance of parameters such as strain rate, test temperature, overall helium content, and He trapping at nanoscale matrix precipitates. Limited experimental studies on ferritic/martensitic steels have generally reported less significant HTHE effects compared to austenitic (face centered cubic, FCC) stainless steels and Ni alloys. Potential causes of this reported difference in HTHE susceptibility between FCC and BCC alloys will be critically assessed, and recommendations for near-term research to objectively evaluate HTHE sensitivity will be outlined. The crucial roles of helium generation per unit time (rather than He/dpa) and performing application-relevant slow strain rate testing for assessing HTHE susceptibility will be discussed. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Characterization, High-Temperature Materials |