| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments II
|
| Presentation Title |
Evaluating Compatibility of Structural Materials for a FLiBe Fusion Breeder Blanket |
| Author(s) |
Rishi Pillai, Marie Romedenne, Monica Gehrig, Adam Willoughby, Paul Humrickhouse |
| On-Site Speaker (Planned) |
Rishi Pillai |
| Abstract Scope |
Molten salt FLiBe (2LiF-BeF2) tritium breeder blankets for fusion reactors require structural materials with the ability to withstand neutron activation, corrosion and degradation in mechanical properties. The close proximity between the nominal melting temperature of FLiBe (460°C) and the maximum operating temperature (550°C) for candidate materials (e.g., reduced activation ferritic/martensitic (RAFM) steels) is a critical challenge. In the current work, the efficacy of Ni and W coatings on RAFM steel substrates in mitigating corrosion during exposure in a customized FLiBe salt composition with a reduced melting point was evaluated. Uncoated and coated RAFM steel specimens were exposed to FLiBe between 450-550°C for up to 1000h. A combination of neutronic/activation analyses and coupled thermodynamic kinetic modeling was employed to predict the impact of the coating thickness, time, temperature and salt exposure on heat and activated waste production, tritium breeding ratios and corrosion attack. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
High-Temperature Materials, Environmental Effects, Modeling and Simulation |