| About this Abstract |
| Meeting |
2020 TMS Annual Meeting & Exhibition
|
| Symposium
|
Radiation Effects in Metals and Ceramics
|
| Presentation Title |
H-42: Evaluation of Bubble Layers in Single- and Poly-crystal Tungsten after Helium Exposure |
| Author(s) |
Daniel Morrall, Cierra DellaRova, Russell Doerner, Matthew Baldwin, Chad Parish |
| On-Site Speaker (Planned) |
Daniel Morrall |
| Abstract Scope |
Understanding the He (D-T) plasma surface interactions of tungsten, the primary candidate material for use as divertor, will be key to the future of fusion reactors. In order to evaluate the performance of the tungsten surface, we exposed both single- and poly-crystalline tungsten pucks to helium plasma at PISCES-A at UC-San Diego over a temperature range of ~300-600 K (polycrystalline) and ~873 K (001 single crystals), in order to study bubble formation and evolution. These temperatures were chosen to prevent surface morphology (i.e., nanofuzz) from forming. We found that in the polycrystalline tungsten samples, a thin, native oxide layer appeared to be co-located with the helium layer. We will draw conclusions about the interactions between oxide and helium layers. In the single crystals, we measured the bubble size, density, and morphology from ~1024 to 1026 He/m2. Nanoindentation was used to evaluate the influence on the near-surface mechanical properties. |
| Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |