| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
2023 Technical Division Student Poster Contest
|
| Presentation Title |
SPG-48: Corrosion Control of Structural Materials for 4th Gen Nuclear Reactors |
| Author(s) |
Krishna Moorthi Sankar, Preet M Singh |
| On-Site Speaker (Planned) |
Krishna Moorthi Sankar |
| Abstract Scope |
One of the major issues in the design of Molten Salt Nuclear Reactors (MSRs) is the significant corrosion of structural materials in the coolant salts such as FLiNaK. The corrosion depends on the redox potential of the system, which in-turn depends on the type and amount of impurities present in the molten salt as well as the alloy composition of the structural material. In this study, corrosion behavior of selected Ni and Fe based alloys were studied in molten FLiNaK at 700 oC. Different redox control methods such as salt purification to remove impurities, addition of active elements as corrosion inhibitors, and electrochemical redox control were tested to understand their effect on this corrosion. This presentation will discuss our results on the viability and effectiveness of various corrosion control methods in molten FLiNaK salt under MSR conditions. |
| Proceedings Inclusion? |
Undecided |
| Keywords |
Nuclear Materials, High-Temperature Materials, Other |