Deuterium retention in molten salt electrodeposition tungsten coatings

•We investigate D retention in electrodeposition W coatings.•W coatings are exposed to D plasmas in the EAST tokamak.•A cathodic current density dependence on D retention is found.•Electrodeposition W exhibits lower D retention than VPS-W. Molten salt electrodeposition is a promising technology to m...

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Bibliographic Details
Published in:Fusion engineering and design 2016-12, Vol.113, p.265-268
Main Authors: Zhou, Hai-Shan, Xu, Yu-Ping, Sun, Ning-Bo, Zhang, Ying-Chun, Oya, Yasuhisa, Zhao, Ming-Zhong, Mao, Hong-Min, Ding, Fang, Liu, Feng, Luo, Guang-Nan
Format: Article
Language:English
Subjects:
EAST tokamak
Graphite
Hydrogen isotopes
Molten salt electrodeposition
Retention
Tungsten coating
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Summary:•We investigate D retention in electrodeposition W coatings.•W coatings are exposed to D plasmas in the EAST tokamak.•A cathodic current density dependence on D retention is found.•Electrodeposition W exhibits lower D retention than VPS-W. Molten salt electrodeposition is a promising technology to manufacture the first wall of a fusion reactor. Deuterium (D) retention behavior in molten salt electrodeposition tungsten (W) coatings has been investigated by D-plasma exposure in the EAST tokamak and D-ion implantation in an ion beam facility. Tokamak exposure experiments demonstrate that coatings prepared with lower current density exhibit less D retention and milder surface damage. Deuterium-ion implantation experiments indicate the D retention in the molten salt electrodeposition W is less than that in vacuum plasma spraying W and polycrystalline W.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2016.07.023