About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Vacancy Engineering in Metals and Alloys
|
| Presentation Title |
Grain boundary migration during irradiation and oxidation of alloys |
| Author(s) |
Emmanuelle A. Marquis, Daniele Fatto Offidani, Konnor Walter |
| On-Site Speaker (Planned) |
Emmanuelle A. Marquis |
| Abstract Scope |
Structural alloys to be used in energy applications, including nuclear reactors, can be subjected to a range of conditions such as radiation and/or corrosive media at intermediate to elevated temperatures. The resulting microstructural changes are controlled by long-range diffusion. Consequently, they depend on the behavior of crystalline point and extended defects including grain boundaries acting as fast diffusion paths. We will discuss observations where grain boundary migration appears to result from unbalanced defect and solute transport: 1) in alloys that were ion-irradiated at intermediate temperatures where irradiation-induced grain boundary migration results from the flow of point defects created during irradiation; and 2) in alloys subjected to corrosive processes where diffusion-induced grain boundary migration plays a significant role in the development of solute-depleted sub-surface microstructures. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Phase Transformations, Nuclear Materials, High-Temperature Materials |