About this Abstract |
| Meeting |
2027 TMS Annual Meeting & Exhibition
|
| Symposium
|
Radiation Effects in Solid-State Materials: An SMD Symposium Honoring William J Weber
|
| Presentation Title |
Radiation-induced Cr segregation in high purity Fe-Cr alloys after proton irradiations |
| Author(s) |
Yajie Zhao, Yao Li, Siwei Chen, Steven J. Zinkle |
| On-Site Speaker (Planned) |
Yajie Zhao |
| Abstract Scope |
Ferritic–martensitic steels are promising structural materials for fission and fusion reactor applications. Radiation-induced solute segregation (RIS) at grain boundaries (GBs) can influence their mechanical integrity and corrosion resistance. Prior studies of Cr RIS at GBs in Fe-Cr model and engineering alloys have reported both Cr enrichment and depletion, but the cause of this variable behavior is unclear. This work systematically investigates radiation-induced Cr redistribution at GBs in high-purity Fe-Cr alloys containing 3-18% Cr. Specimens were irradiated with 800 keV protons to a mid-range dose of 0.35 dpa at 300 and 500 °C (total irradiation depth of ~5 µm). GB compositions after irradiation were characterized by STEM-EDS mapping throughout and beyond the irradiated region. Cr enrichment was observed over most of the irradiated depth for all grain boundaries examined at both temperatures, whereas Cr depletion occurred within ~1 µm of the surface after irradiation at 500 °C. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Iron and Steel, Characterization |