About this Abstract |
| Meeting |
2027 TMS Annual Meeting & Exhibition
|
| Symposium
|
Transmutation Effects in Materials in Fission, Fusion, and Spallation Environments
|
| Presentation Title |
Advances in Oxide Dispersion Strengthened (ODS) Steel Manufacturing for Nuclear Applications |
| Author(s) |
Alice E. Appleby, Arunodaya Bhattacharya |
| On-Site Speaker (Planned) |
Alice E. Appleby |
| Abstract Scope |
Complex irradiation extremes inside nuclear reactors drive microstructural changes that degrade thermo-mechanical performance of structural materials. ODS steels were developed to mitigate irradiation-induced degradation mechanisms and improve creep strength, through fine yttrium-based nano-dispersoids that act as sinks for point-defects and transmutation gases. These dispersoids also pin grain boundaries, enhancing Hall-Petch strengthening and reducing grain boundary sliding. Their effectiveness depends strongly on size and number density, both governed by the manufacturing route. However, powder-metallurgy based manufacturing of ODS relies on mechanical alloying which has several drawbacks - carbon contamination, reduced sphericity, high internal stresses, and limited scalability. Scalability particularly constraints wider deployment of ODS steels for nuclear applications. At University of Birmingham, alternative powder processing, consolidation, and joining approaches are being developed to support near-net shape ODS processing and address scalability. Here, we will present advances in improving scalability, near-net shaping and performance of ODS steels benchmarked against conventional manufacturing routes. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Process Technology, Additive Manufacturing |