About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Metallic Fuels - Design, Fabrication, and Characterization
|
| Presentation Title |
Metal Fuel Performance in Sodium Fast Reactors: Post-Irradiation Examination and Innovative Experiments |
| Author(s) |
Tiankai Yao, Colby Jensen, Douglas L. Porter |
| On-Site Speaker (Planned) |
Tiankai Yao |
| Abstract Scope |
The United States Department of Energy has a longstanding history in the development of sodium-cooled fast reactor, notably through the Experimental Breeder Reactor-Ⅱ and the Fast Flux Test Facility reactors. Metal fuel was utilized as driver fuel and tested under off-normal reactor conditions. To help address the increasing industry’s needs to qualify metal fuel for advanced reactor applications, the Office of Nuclear Energy Advanced Fuel Campaign program is providing scientific basis through post-irradiation examination and post-testing characterization, aimed at improving the understanding of metal fuel performance. This paper discusses our recent progress for several metallic fuel pins from the metallic fuel materials library, as well as new irradiation experiments conducted at the Transient Reactor Test Facility and the Advanced Test Reactor. |
| Proceedings Inclusion? |
Planned: |