| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Meeting Materials Challenges for the Future of Fusion Energy
|
| Presentation Title |
High Throughput Self-Ion Irradiation and Characterization of Pure Tungsten |
| Author(s) |
Nicholas Bernard Crnkovich, Nathan Curtis, Zilong Hua, Adrien Couet |
| On-Site Speaker (Planned) |
Nicholas Bernard Crnkovich |
| Abstract Scope |
Tungsten is the leading candidate for first wall materials in fusion applications due to its high melting point, thermal conductivity, and low sputtering yield. However, its thermal conductivity and ductility degrade under irradiation, limiting its lifespan. This study irradiated pure tungsten at various doses, temperatures, and dose rates up to 50 dpa, using self-ion irradiation with a high-throughput ion-irradiation beamline, and characterized it using high-throughput techniques. Automated nanoindentation and focused ion beam trenching assessed mechanical property changes and void swelling. A thermal conductivity microscope (TCM) was used to measure the change in thermal conductivity of the irradiated regions. This TCM uses spatial and frequency domain thermoreflectance to probe the irradiated layer for thermal diffusivity and conductivity with tens of microns resolution. These techniques yield rapid and nondestructive results of the degradation of tungsten under irradiation and provides a good benchmark for the rapid development of novel first wall materials. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Environmental Effects, Characterization |