About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Special Topics in Nuclear Materials: Reproducibility and Uncertainty; Hydrogen Effects; Space and Microreactor Systems
|
| Presentation Title |
Hydrogen Retention in Neutron-Irradiated Tungsten and Tungsten-Rhenium Alloys |
| Author(s) |
Weicheng Zhong, Yuji Hatano, Takaaki Koyanagi, Yutai Katoh |
| On-Site Speaker (Planned) |
Weicheng Zhong |
| Abstract Scope |
Tungsten and tungsten-rhenium alloys are key plasma-facing material candidates for fusion reactors. This study investigates hydrogen retention in neutron-irradiated W and W-Re alloys to evaluate the role of Re in post-irradiation hydrogen retention in tungsten alloys. Samples were irradiated at ~300-1100 °C to doses up to 1 dpa, and the effect of Re on hydrogen retention and desorption behavior was examined. In particular, W and W-5%Re were simultaneously exposed to neutron irradiation and hydrogen gas environment (14.2 Torr) at ~300-400 °C, enabling investigation of both individual and synergistic effects of neutron damage and hydrogen interaction. W-Re alloys exhibit lower hydrogen retention than pure W, suggesting that Re alters defect evolution and reduces trapping quantity. Hydrogen retention and desorption behaviors are correlated with microstructural defect characterization to identify dominant trapping mechanisms. The mechanisms behind this reduction in W-Re alloys, along with the effects of simultaneous exposure conditions on defect formation, will be discussed. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, |