Effect of heavy ion pre-irradiation on blistering and deuterium retention in tungsten exposed to high-fluence deuterium plasma

doi:10.1016/j.jnucmat.2018.05.082

	Effect of heavy ion pre-irradiation on blistering and deuterium retention in tungsten exposed to high-fluence deuterium plasma
	Cheng, L; Wang, SW; Zhu, XL; Guo, WG; Liu, M; Lu, GH; Cao XZ(曹兴忠); Xu, C; Yuan, Y; Fu, EG
刊名	JOURNAL OF NUCLEAR MATERIALS
	2018
卷号	508 页码:395-402
ISSN号	0022-3115
DOI	10.1016/j.jnucmat.2018.05.082
文献子类	Article
英文摘要	Surface blistering and deuterium (D) retention of heavy ion pre-irradiated (1 dpa) tungsten (W) exposed to low-energy (40 eV) and high-flux (1-2 x 10(22) D/m(2)s) D plasma has been investigated with low fluence of 0.1 x 10(27) D/m(2) and a high fluence of 2.2 x 10(27) D/m(2). Surface morphology observations show that a large number of blisters are formed on the undamaged W after low-fluence exposure while the area density of the blister will have significantly increased and blister bursting will be triggered in the case of high-fluence exposure. In contrast, the heavy ion pre-irradiation noticeably reduces the area density of blisters for both low-and high-fluence exposures. The thermal desorption spectroscopy (TDS) shows that the total D retention in the pre-damaged W is greater than that of the undamaged sample, and this trend is more significant with increasing fluence/duration of D plasma exposure. The results of positron annihilation Doppler broadening spectrometry (PA-DBS) and TDS indicate that a large number of vacancy-type defects, especially those with a higher trapping energy of D, are induced by the heavy ion pre-irradiation. The increasing defects/D-trap sites may result in two outcomes, the D concentration will disperse at each blister nucleation site and D inward diffusion is enhanced and, therefore, lead to the mitigation of D-induced blistering and increase the D retention. In addition, combined with the enhanced D inward diffusion caused by increasing exposure duration, the D retention is therefore much higher in the pre-damaged W in the case of high-fluence exposure. (C) 2018 Elsevier B.V. All rights reserved.
电子版国际标准刊号	1873-4820
WOS关键词	HIGH-FLUX ; LOW-ENERGY ; POSITRON-ANNIHILATION ; DAMAGED TUNGSTEN
WOS研究方向	Materials Science ; Nuclear Science & Technology
语种	英语
WOS记录号	WOS:000439134500044
内容类型	期刊论文
源URL	[http://ir.ihep.ac.cn/handle/311005/286134]
专题	高能物理研究所_加速器中心高能物理研究所_多学科研究中心
作者单位	中国科学院高能物理研究所
推荐引用方式 GB/T 7714	Cheng, L,Wang, SW,Zhu, XL,et al. Effect of heavy ion pre-irradiation on blistering and deuterium retention in tungsten exposed to high-fluence deuterium plasma[J]. JOURNAL OF NUCLEAR MATERIALS,2018,508:395-402.
APA	Cheng, L.,Wang, SW.,Zhu, XL.,Guo, WG.,Liu, M.,...&Cao, XZ.(2018).Effect of heavy ion pre-irradiation on blistering and deuterium retention in tungsten exposed to high-fluence deuterium plasma.JOURNAL OF NUCLEAR MATERIALS,508,395-402.
MLA	Cheng, L,et al."Effect of heavy ion pre-irradiation on blistering and deuterium retention in tungsten exposed to high-fluence deuterium plasma".JOURNAL OF NUCLEAR MATERIALS 508(2018):395-402.