About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Chemistry for Molten Salt Systems
|
| Presentation Title |
Treatment of Molten Fluoride Salt-Exposed Graphite: Cleaning Made Simple |
| Author(s) |
Yina Huang, Guiqiu Zheng, David Sprouster, Lance Snead |
| On-Site Speaker (Planned) |
Yina Huang |
| Abstract Scope |
To ensure chemical stability in storage and transportation containers, graphite waste from Fluoride-cooled High-temperature Reactors (FHRs) requires treatment to remove residual fluorides and beryllium before disposal. This study demonstrates a simple, effective cleaning method for modern fine-grained nuclear graphite exposed to molten FLiBe salt under neutron irradiation. A straightforward soaking in deionized water successfully removed near-surface salt, confirmed through cross-sectional scanning electron microscopy, energy-dispersive spectroscopy mapping, and X-ray diffraction. Additional in situ electrochemical monitoring and ex situ fluorometer assays validated this approach. Post-cleaning analyses confirm the process effectively decontaminates graphite surfaces exposed to FLiBe during irradiation, offering a practical solution for FHR graphite waste management. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Other, |