| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Elucidating Microstructural Evolution Under Extreme Environments
|
| Presentation Title |
Effect of Irradiation on the Microstructure of Oxide Dispersion Strengthened HT-9 Alloy |
| Author(s) |
Sohail Shah, Xinchang Zhang, Lin Shao, Andrew Gorman, Cheng Sun, Mukesh Bachhav |
| On-Site Speaker (Planned) |
Sohail Shah |
| Abstract Scope |
Oxide dispersion-strengthened (ODS) ferritic-martensitic steels are a promising material group for advanced nuclear systems due to their high temperature strength, high swelling resistance and excellent irradiation tolerance. Nano powders of Y2O3 (30-45 nm), La2O3 (10-100 nm), and CeO2 (10-30 nm) from US Research Nanomaterials Inc. were obtained to be dispersed into the Fe-Cr matrix. Microstructural evolution of HT9 self-irradiated to damage levels of 200 dpa at temperatures ranging from 400 °C to 600 °C are studied. Ion irradiation introduces defect imbalances due to injected interstitial effect which can reduce Cr diffusion and suppress carbide formation. The effect of irradiation on nano-oxide particle stability as well as defect interaction with solute will be studied. Additionally, its effects on segregation to interfaces/defects will be presented. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Iron and Steel, Nuclear Materials, |