| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Chemistry for Molten Salt Systems
|
| Presentation Title |
Advanced Corrosion Barrier Design for Molten Salt Reactors |
| Author(s) |
Sumit Bhattacharya, Yinbin Miao, Abdellatif M. Yacout |
| On-Site Speaker (Planned) |
Sumit Bhattacharya |
| Abstract Scope |
Molten salt reactors (MSRs), pivotal in Generation IV nuclear technologies, enhance safety with features like no loss-of-coolant accidents and low-pressure operations. However, a significant challenge for MSR deployment is the corrosion susceptibility of conventional structural alloys such as HASTELLOY® or 316L stainless steel in harsh environments involving molten salts with fuel components and low-melting-point fission products. To address this, Argonne National Laboratory has designed a nickel-molybdenum (Ni-Mo) based advanced corrosion barrier. This coating effectively protects against molten salts, impurities, and solid fission products while maintaining integrity at high temperatures. Our solution leverages existing and proposed structural materials by enhancing their resistance to corrosion, making them cost-effective despite their inadequacies when used alone. We will discuss advancements in refining these barrier designs and their long-term protective capabilities against fluoride/chloride-based salts, as well as their resistance to thermal cycling and radiation exposure, which are crucial for safeguarding heat exchangers in MSR environments. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Surface Modification and Coatings, Thin Films and Interfaces, Nuclear Materials |