About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Develop of L12 Intermetallics Dispersive Steels for Nuclear Applications |
| Author(s) |
Ying Yang, Yanli Wang, Lia Amalia, Ke An, Weicheng Zhong |
| On-Site Speaker (Planned) |
Ying Yang |
| Abstract Scope |
All Generation IV nuclear reactor concepts aim to operate at higher temperatures than the current light water reactors, which requires the use of advanced materials that are not only mechanically robust at higher temperature but also can resist degradation after extensive neutron irradiation. Austenitic stainless steels are used in nuclear reactors because of their excellent mechanical properties at high temperatures, however, they are prone to volumetric swelling because of their more close-packed fcc crystal structure. Formation of nanoprecipitates in the fcc matrix can help to mitigate the swelling behavior. With the aid of computational thermodynamics and kinetics, a new family of L12 intermetallic dispersive steels (IDS) were recently developed at ORNL. These nanoprecipitates were formed through a conventional ingot-making method followed by a two-step solutioning and aging heat treatment. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
High-Temperature Materials, Nuclear Materials, Iron and Steel |