About this Abstract |
| Meeting |
2027 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Chemistry for Molten Salt Systems
|
| Presentation Title |
Corrosion compatibility of candidate structural alloys in static molten FLiBe relevant for fusion reactors |
| Author(s) |
Debashish Sur, Severine Cambier, Adam Willoughby, Tracie Lowe, Rishi Pillai |
| On-Site Speaker (Planned) |
Debashish Sur |
| Abstract Scope |
Molten fluoride salts such as FLiBe (LiF–BeF2) are promising candidates for tritium breeding and heat transfer in fusion reactors, but corrosion of structural materials remains a major challenge. This study investigates the corrosion behavior of reduced activation ferritic-martensitic steels and Ni-based alloys (for no-activation regions of the fusion reactor) in purified FLiBe between the temperatures of 500-650◦C. F82H and Hastelloy-N were found to show a mass loss compared to 304H at 500 ◦C after 500 h in purified FLiBe. Coupled thermodynamic–kinetic analyses of the salt–alloy system was employed to quantify corrosion rates in static systems as a function of salt impurities, redox control, alloy composition, microstructure, time and temperature. These results provide quantitative guidance for material selection and salt management in fusion blanket and heat exchanger systems and motivate further validation under flowing, non-isothermal, and irradiated conditions. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Environmental Effects, High-Temperature Materials, Nuclear Materials |