| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
|
| Presentation Title |
High Temperature Liquid Lithium Corrosion |
| Author(s) |
Bradley A. Young, Junliang Liu, Harry Myers, Martha Simmonds, Alex Leide, Chris Grovenor, David Armstrong |
| On-Site Speaker (Planned) |
Bradley A. Young |
| Abstract Scope |
Recent headlines from fusion technologies are extremely promising and the projected timescales of commercial devices are comparable to next-generation fission technologies. Natural, molten lithium at 750-850K is proposed as a tritium breeding and heat exchanger material for multiple fusion devices and a suitable containment material is needed. Reliable corrosion data of materials in lithium over this temperature range is scarce.
We have developed simple methods for exposing candidate materials to pure liquid lithium for extended periods, and for subsequent evaluation and analysis. The performance of steels, SiC/SiC composite, and ceramic coatings (including TaC and Erbia) have been assessed via quantitative and qualitative methods. Our observations, in contrast to some of the literature, show that significant corrosion occurs on all these materials after relatively short exposures. We will discuss these results, mechanisms of liquid metal corrosion, and suggest next steps to qualify materials for use in fusion devices. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Surface Modification and Coatings, Composites |