About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
A New Design Approach Towards Environmental Cracking Resistant Stainless Steel in Nuclear Environments |
| Author(s) |
Xiaoyuan Lou, Jingfan Yang |
| On-Site Speaker (Planned) |
Xiaoyuan Lou |
| Abstract Scope |
Environmental cracking, including irradiation-assisted stress corrosion cracking (IASCC) and stress corrosion cracking (SCC) of austenitic stainless steel, affect the structural integrity of nuclear reactor systems. Over the past 40 years, significant progress has been made regarding the fundamental understandings of these phenomena in high temperature water systems. Strategies, including water chemistry control, weld residual stress management, steel sensitization management, high Cr alloy design, etc., have been implemented. This talk highlights our approach to rethink this grain boundary related phenomenon and revolutionize the design of radiation and cracking resistant stainless steel for nuclear environments. An austenitic stainless steel with superior SCC, IASCC, radiation hardening and oxidation resistances can simultaneously achieved, demonstrating performance beyond the best Ni alloy in the market. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Additive Manufacturing, Iron and Steel, Nuclear Materials |