Deuterium retention in tungsten under the combined influence of displacement damage and helium

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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Bibliographic Details
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:
tungsten
displacement damage
helium
deuterium retention
surface blistering
Online Access:https://doi.org/10.1088/1741-4326/ade31a
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https://doi.org/10.1088/1741-4326/ade31a

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