About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-Based Composites for Nuclear Applications III
|
| Presentation Title |
Ion irradiation and mechanical properties of additively manufactured tungsten carbide for nuclear power applications in molten salt reactors |
| Author(s) |
Anissa Morgan, Kevin Lam, Joseph Latta, James Kelly, Chris Smyth, Elizabeth M. Getto |
| On-Site Speaker (Planned) |
Anissa Morgan |
| Abstract Scope |
Molten salt nuclear reactors (MSRs) are a type of Generation IV nuclear reactor which use molten fluoride or chloride salts as their primary coolant. Molten salts are extremely corrosive and limit the feasibility of using conventional nickel alloys. Lawrence Livermore National Laboratory (LLNL) has identified WC272, a proprietary tungsten carbide ceramic composite, as a structural material candidate for resisting molten salt corrosion. The goal of this project is to understand ion irradiation effects and mechanical properties of additively manufactured (AM) WC272 and a benchmark spark plasma sintered (SPS) WC272. Ion irradiations were performed with 14 MeV W5+ ions at 500C to 1 dpa and with 18 MeV C3+ to 1 dpa at 500C and 600C. Nanoindenting will be used to quantify a difference in hardness from irradiation, and to correlate to strength. Scanning transmission electron microscopy will be used to understand changes in the microstructure. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Mechanical Properties, Nuclear Materials, Ceramics |