| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Meeting Materials Challenges for the Future of Fusion Energy
|
| Presentation Title |
Development of SiC Composite Blanket for Fusion |
| Author(s) |
Tatsuya Hinoki, Junyeab Lee, Fujio Shinoda, Taishi Sugiyama, Takaaki Koyanagi, Sosuke Kondo |
| On-Site Speaker (Planned) |
Tatsuya Hinoki |
| Abstract Scope |
The SiC composites are promising materials for fusion. The key issues are to fabricate large scale production with uniform structure and complicated shaping and to join with a W first wall. The objective is to develop the SiC composite blanket with a W first wall.
Flexible prepreg sheets including SiC fibers and matrix row materials were fabricated. The BN particle dispersion SiC composites were fabricated by liquid phase sintering with the stacked prepreg sheets. The B-11 will be used for commercialization. Ion irradiation at DuET, Kyoto Univ. and neutron irradiation at HFIR, ORNL were used to understand irradiation effects
No significant irradiation induced swelling and microstructural change were observed for BN particle dispersion SiC. SiC and W was joined by hot press. Degradation of the joining strength wasn’t observed following neutron irradiation. The composite box with a baffle inside was fabricated. It joined with W plates and SiC composite pipes. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Composites, Joining |