About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
|
| Presentation Title |
Static corrosion of SS316H in Purified NaF-KF-UF4-UF3 |
| Author(s) |
Ding Zhao, Siheng Ren, Jaewoo Park, Amanda Leong, Jinsuo Zhang |
| On-Site Speaker (Planned) |
Ding Zhao |
| Abstract Scope |
With the widespread application of SS316H in molten slat reactors (MSRs), understanding and controlling its corrosion remain pressing challenges. In this study, the corrosion behavior of SS316H in purified NaF-KF-UF4-UF3 molten salt was investigated. The static corrosion was controlled by adjusting the redox potential through varying the UF4/UF3 ratio from 10 to 60 in the purified salt. Three SS316H specimens were immersed in individual born nitric crucibles for 240 hours at 700 ℃, with salt collected intermittently to monitor dynamic changes in corrosion product. SEM/EDS was employed to examine the corrosion behavior of SS316H exposed to FUNaK. Chromium(Cr) depletion in the salt-affected regions was used to assess the salt-attack depth. Segregation of Cr and molybdenum(Mo) was observed both in the bulk and at the interface, which is caused by the salt attack/heat treatment. The results demonstrate that low UF4/UF3 ratio in FUNaK salt effectively mitigates the corrosion of SS316H specimens. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
High-Temperature Materials, Nuclear Materials, |