About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Chemistry for Molten Salt Systems
|
| Presentation Title |
Wettability of Molten Fluoride Fuel Salts in the Presence of Corrosion and Fission Products |
| Author(s) |
Brij Bhagat, Siheng Ren, Jinsuo Zhang |
| On-Site Speaker (Planned) |
Brij Bhagat |
| Abstract Scope |
Understanding the time evolution of material properties is a critical topic in the development of molten salt reactor (MSR) technology. Graphite, an important moderator material, is subject to physical and chemical degradation amid extended fluoride salt exposure. How do corrosion and fission products, which leach into molten salts throughout reactor operation, affect the salts' interactions with graphite? This study compares the wettability of three NaF-KF-UF4 formulations on a graphite substrate: one clean, one containing corrosion products, and one containing fission products. Contact angle measurements, taken using the sessile drop method, provide insight into the extent to which interactions like infiltration and chemical attack may occur at the salt-graphite interface. Preliminary observations suggest that even low concentrations of corrosion products may affect salt wettability. The results of this study will clarify the role of corrosion and fission in reducing MSR lifespan and may inform future material selection and reactor design strategies. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Phase Transformations, Other |