Deuterium retention in tungsten under the combined influence of displacement damage and helium
Accurate predictions of hydrogen isotope/tritium inventory in tungsten (W), used as a plasma-facing material in fusion reactors, can reduce the uncertainty associated with the self-sustaining fuel cycle. It is well-established that displacement damage generally enhances deuterium (D) retention in W,...
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| Main Authors: | Ting Wang, Xiu-Li Zhu, Mengchong Ren, Yue Yuan, Wangguo Guo, Shiwei Wang, Long Cheng, Di Hu, Yuhao Li, Guang-Hong Lu |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
IOP Publishing
2025-01-01
|
| Series: | Nuclear Fusion |
| Subjects: | |
| Online Access: | https://doi.org/10.1088/1741-4326/ade31a |
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