About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Chemistry for Molten Salt Systems
|
| Presentation Title |
Molten Chloride Fast Reactor Material Testing and Development |
| Author(s) |
Cody Falconer, Kasey DePoy, Ivan Mitchell, Jeff Koza-Reinders, Karl Britsch, Dani Campos, Caitlin Huotilainen, Melanie Lindsey |
| On-Site Speaker (Planned) |
Cody Falconer |
| Abstract Scope |
The molten chloride fast reactors are one of the many advanced reactor technologies under development. One unique feature of these reactors is their ability to utilize a liquid chloride-based fuel salt as well as a chloride-based coolant salt. Each salt presents its own complexities regarding both operation and compatibility with structures, systems, and components. A number of studies have focused on materials-salt interactions in chloride-based coolant salt mixtures, but there exists a significant knowledge gap in understanding material behavior and degradation in chloride-based fuel salt mixtures relevant to molten chloride fast reactors. This work presents the development of novel testing platforms for investigating material behavior in both coolant and fuel salt mixtures under natural circulation and forced flow conditions. Additionally, results from this testing will be presented providing a more complete comparison between the material compatibility in relevant chloride-based fuel and coolant salt mixtures. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Temperature Materials, Other |