| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Chemistry for Molten Salt Systems
|
| Presentation Title |
Redox control measurement in sodium, beryllium, uranium bearing salt |
| Author(s) |
Nagihan Karakaya, Amanda Leong, Jinsuo Zhang |
| On-Site Speaker (Planned) |
Nagihan Karakaya |
| Abstract Scope |
In a molten salt nuclear reactor system, maintaining proper redox potential is crucial for mitigating corrosion of structural materials. This study provides a way of measuring upper and lower limits of redox potential control in sodium, beryllium, uranium-bearing molten fluoride salt environment. Upper limit of redox control measured with chromium metal dissolution from structural material, and lower limit is set as maximum solubility of trifluorides in the system. Therefore, the safe operation of molten salt reactor can be managed respect to the upper and lower limits measured. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, |