About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Chemistry for Molten Salt Systems
|
| Presentation Title |
Molten Chloride Fast Reactor Fuel Salt Redox Potential at Equilibrium |
| Author(s) |
D. Nathanael Gardner, Randall Chiu, Michael Borrello, Peter Hosemann, Raluca O. Scarlat |
| On-Site Speaker (Planned) |
Randall Chiu |
| Abstract Scope |
Advanced molten salt reactor designs employ actinide fueled chloride and fluoride salts. These salts are commonly eutectic compositions of uranium and secondary cations, such as eutectic NaCl-UCl3. During reactor operation, due to continuous burnup, fission product buildup, fission product containing fuel removal, and refueling, the reactor fuel salt composition reaches an equilibrium state. This salt at equilibrium, containing fission products and a different NaCl:UCl3 ratio than the initial fuel salt, can potentially have different thermophysical and thermochemical properties than the initial composition. This work measures the thermophysical and electrochemical properties of a NaCl-UCl3 fuel salt before and after the addition of expected fission products. This work also seeks to determine what fission products are soluble at the conditions of redox control by uranium speciation. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Energy Conversion and Storage, High-Temperature Materials |