About this Abstract |
| Meeting |
2027 TMS Annual Meeting & Exhibition
|
| Symposium
|
Transmutation Effects in Materials in Fission, Fusion, and Spallation Environments
|
| Presentation Title |
Radiation Effects in Oxide Dispersion Strengthened Alloys and Implications on Transmutation Gas Management |
| Author(s) |
Samara Michelle Levine, Steven J. Zinkle, David T. Hoelzer, Arunodaya Bhattacharya |
| On-Site Speaker (Planned) |
Samara Michelle Levine |
| Abstract Scope |
Oxide dispersion strengthened (ODS) alloys are advanced structural materials for fission and fusion systems, engineered with a high density of fine oxide particles to enhance high temperature mechanical performance and manage transmutation gases, particularly hydrogen and helium. This presentation provides an overview of radiation damage mechanisms in ODS alloys, with a focus on nano-dispersoid degradation and radiation-enhanced or -induced precipitation at high doses. Neutron irradiation data on ballistic dissolution, amorphization, and matrix-particle interface modification of dispersoids will be presented, including case studies of alloys PM2000 and MA957. A comparative analysis across multiple ODS variants will highlight the role of initial dispersoid chemistry, structure, and size distribution in governing irradiation response. The implications of dispersoid degradation and phase instability will be discussed in relation to key performance challenges, including cavity swelling, helium embrittlement at low and high temperatures, and tritium retention. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Iron and Steel |