Surface blistering and deuterium retention behaviors in pure and ZrC-doped tungsten exposed to deuterium plasma

Surface blistering and deuterium (D) retention behaviors in pure tungsten (W) and 0.5 wt% ZrC-doped W alloy (WZC) exposed to D plasma have been investigated as a function of incident D fluence up to 2.6 × 10 25  D m −2 . Surface observations show that large-sized blisters (∼8–10 μ m) and a few small...

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Bibliographic Details
Published in:Nuclear fusion 2021-04, Vol.61 (4), p.46026
Main Authors: Zhang, Xue-Xi, Qiao, Li, Zhang, Hong, Li, Yu-Hong, Wang, Peng, Liu, Chang-Song
Format: Article
Language:English
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Summary:Surface blistering and deuterium (D) retention behaviors in pure tungsten (W) and 0.5 wt% ZrC-doped W alloy (WZC) exposed to D plasma have been investigated as a function of incident D fluence up to 2.6 × 10 25  D m −2 . Surface observations show that large-sized blisters (∼8–10 μ m) and a few small blisters (
ISSN:0029-5515
1741-4326
DOI:10.1088/1741-4326/abdfda