| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Friction Stir Welding and Processing XII
|
| Presentation Title |
Post-Irradiation Examination of High-dose Ion Irradiated Friction Stir Welding (FSW) MA956 ODS Alloy |
| Author(s) |
Yu Lu, Ramprashad Prabhakaran, Yaqiao Wu, Megha Dubey, Lin Shao |
| On-Site Speaker (Planned) |
Yu Lu |
| Abstract Scope |
Oxide dispersion strengthened (ODS) alloys are candidate cladding materials for the next generation advanced nuclear reactors due to their excellent resistance to irradiation damage and superior mechanical properties. However, conventional weld method would lead to agglomeration of fine oxide particles and result in loss of strength. Friction stir welding (FSW) is a solid-state joining technique that does not require melting at the joint interface. FSW was used to weld MA956 in a bead-on-plate configuration and higher weld efficiency was obtained. In this study, parent and friction stir welded MA956 were ion irradiated to different doses (2.5, 50 and 100 dpa) with Fe2+ at 320°C. Post-irradiation characterizations were performed using scanning transmission electron microscopy, atom probe tomography and nanoindentation techniques. With combination of these techniques, the microstructure evolution and mechanical property change of parent and friction stir welded MA956 after irradiation were examined and compared in detail. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, |