Plasma exposure behavior of re-deposited tungsten on structural materials of fusion reactors
Plasma exposure behavior of re-deposited tungsten on structural materials of fusion reactors
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聚变反应堆结构材料上再沉积钨的等离子体暴露行为
DOI：
10.1016/j.jnucmat.2017.03.001
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发表时间：
2017
影响因子：
3.1
通讯作者：
Luo Guang-Nan
中科院分区：
文献类型：
--
作者：
Xu Yu-Ping;Wang Jing;Zhou Hai-Shan;Liu Feng;Li Zeng-De;Li Xiao-Chun;Lu Tao;Liu Hao-Dong;Ding Fang;Mao Hong-Min;Zhao Ming-Zhong;Lin Chen-Guang;Luo Guang-Nan
为了评价再沉积钨(W)对熔合结构材料表面改性和氢同位素保留行为的影响，研究了磁控溅射制备的再沉积钨(W)样品在F82H钢、V-5Cr-5Ti合金和裸基体样品上的等离子体暴露行为。在2015年春季EAST运动中，所有样本都暴露于367次氘等离子体注射。等离子体辐照后，W层大面积脱落，剩余W层与衬底材料界面处出现大水泡。用热解吸光谱法对复镀W层样品的氘保留行为进行了表征，并与裸衬底样品进行了比较。
To evaluate the effects of re-deposited tungsten (W) on the surface modification and hydrogen isotope retention behavior of fusion structural materials, the plasma exposure behavior of re-deposited W samples prepared by magnetron sputtering on the F82H steel, the V-5Cr-5Ti alloy as well as bare substrate samples was investigated. All the samples were exposed to 367 shots of deuterium plasmas in the 2015 spring EAST campaign. After the plasma exposure, large area of W layer was exfoliated, while big blisters were found at the interface between the remaining W layer and the substrate materials. The deuterium retention behavior of the samples with re-deposited W layer was characterized by thermal desorption spectroscopy and compared with the bare substrate samples.