Surface blistering and deuterium retention behaviors in pure and ZrC-doped tungsten exposed to deuterium plasma
Zhang,Xue-Xi1,2; Qiao,Li2; Zhang,Hong2; Li,Yu-Hong1; Wang,Peng2; Liu,Chang-Song3
刊名Nuclear Fusion
2021-03-17
卷号61
关键词W W-ZrC alloy D plasma surface blistering D retention
ISSN号0029-5515
DOI10.1088/1741-4326/abdfda
通讯作者Li,Yu-Hong() ; Wang,Peng()
英文摘要AbstractSurface 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 × 1025?D?m?2. Surface observations show that large-sized blisters (~8–10 μm) and a few small blisters (<2 μm) are formed on the W samples. For WZC, the surface of the samples is covered by a high density of small blisters (<1 μm), and no blister larger than 2 μm is found. Cross section views show that the large-sized blisters originate from subsurface grain boundaries, and the small blisters originate from intra-granular cavities at depths much closer to the surface. The intra-granular blisters are preferentially formed on the grains with a normal direction close to [111] for both types of sample. The inter-granular blisters formed in pure W are significantly suppressed in WZC, and the fluence threshold for blister formation in WZC is lower than that in W. The D depth distributions indicate that the implanted D is mainly retained in the near-surface region of WZC and W. Besides, a higher and broader D peak is observed at a depth of between 0.1–0.25 μm in WZC, but the intensity and width of the D peak is lower and thinner in W. The desorption spectra of WZC shift to the lower temperature side as compared to W, and the total retained D amount in WZC and W is comparable in the fluence range of 2.8 × 1024–2.6 × 1025?D?m?2.
资助项目National key R&D project of China[2017YFE0302500] ; National Natural Science Foundation of China[11875305] ; National Natural Science Foundation of China[11735015] ; National Natural Science Foundation of China[11775102]
WOS研究方向Physics
语种英语
出版者IOP Publishing
WOS记录号IOP:0029-5515-61-4-ABDFDA
资助机构National key R&D project of China ; National Natural Science Foundation of China
内容类型期刊论文
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/120702]  
专题中国科学院合肥物质科学研究院
通讯作者Li,Yu-Hong; Wang,Peng
作者单位1.School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000, China
2.State Key Laboratory of Solid Lubrication, Lanzhou Institute of Chemical Physics, Chinese Academy of Sciences, Lanzhou 730000, China
3.Key Laboratory of Materials Physics, Institute of Solid State Physics, Chinese Academy of Sciences, Hefei 230031, China
推荐引用方式
GB/T 7714
Zhang,Xue-Xi,Qiao,Li,Zhang,Hong,et al. Surface blistering and deuterium retention behaviors in pure and ZrC-doped tungsten exposed to deuterium plasma[J]. Nuclear Fusion,2021,61.
APA Zhang,Xue-Xi,Qiao,Li,Zhang,Hong,Li,Yu-Hong,Wang,Peng,&Liu,Chang-Song.(2021).Surface blistering and deuterium retention behaviors in pure and ZrC-doped tungsten exposed to deuterium plasma.Nuclear Fusion,61.
MLA Zhang,Xue-Xi,et al."Surface blistering and deuterium retention behaviors in pure and ZrC-doped tungsten exposed to deuterium plasma".Nuclear Fusion 61(2021).
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