| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Meeting Materials Challenges for the Future of Fusion Energy
|
| Presentation Title |
Responses of Dispersion-Strengthened Tungsten to High Heat Flux and High Fluence Helium Irradiation |
| Author(s) |
Xing Wang, Ashrakat Saefan, Chase Hargrove |
| On-Site Speaker (Planned) |
Xing Wang |
| Abstract Scope |
Tungsten (W) is a promising plasma-facing material with limited mechanical properties. Incorporating second-phase dispersoids into the W matrix has been demonstrated to be effective in suppressing grain growth and improving ductility. This work shows that dispersion phases can further improve the material’s tolerance to high heat flux and helium (He) irradiation. Dispersion-strengthened W (DSW) embedded with micro- or nano-sized TiC, ZrC, or TaC dispersoids was irradiated by 200 keV He ions up to a fluence of 4.5E17 ions/cm-2 at 850 °C. Large bubbles concentrated along grain boundaries in W, whereas few bubbles appeared near W-dispersoid interfaces unless there was compositional intermixing, suggesting these interfaces can act as defect sinks and inhibit bubble growth. Similar DSW samples were exposed to high heat flux up to 0.38 GW/m2 at room temperature, 400℃, and 1000℃, respectively. While pure W samples exhibited surface cracks, no obvious surface damage was observed on DSW sample surfaces. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Ceramics, Environmental Effects |