Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
4921209 | Fusion Engineering and Design | 2016 | 4 Pages |
Abstract
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.
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Authors
Hai-Shan Zhou, Yu-Ping Xu, Ning-Bo Sun, Ying-Chun Zhang, Yasuhisa Oya, Ming-Zhong Zhao, Hong-Min Mao, Fang Ding, Feng Liu, Guang-Nan Luo, EAST contributors EAST contributors,