面向等离子体材料钨中氘/氦滞留行为的研究进展<sup>*</sup>

doi:10.11896/j.issn.1005-023X.2017.09.015

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Abstract Tungsten (W) as a plasma facing material (PFM) in the service process is not only affected by the plasma with high heat load, but also bombarded by the high-fluence particles such as deuterium (D), tritium (T), helium (He) and high-energy neutrons which produced by D-T fusion reaction. The retention and blister formation of D, T and He in tungsten are still one of the key issues needed to be solved in the fusion reactor. The correlation between the retention or blister formation and the irradiation conditions are reviewed to briefly elucidate the service performance and strengthening mechanism of W. The performance of W can be effectively improved by reducing the amount of D/He retention or inhibiting blister formation. Further study of the relationship between the retention behavior and irradiation defects are still needed to construct the correspondence between the macroscopic thermal desorption behavior and the microscopic state of D/He. These kinds of studies will provide theoretical supports for seeking suitable ways to enhance the service performance of W.

Key words： tungsten deuterium helium retention blister formation

Published: 03 May 2018

CLC number:	TL62+.7
	TB31

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	Articles by authors
	WANG Wei
	YE Xiaoqiu
	CHEN Chang'an
	LI Qiang
	JIN Wei
	YANG Yongbin
	GAO Tao

Cite this article:

WANG Wei,YE Xiaoqiu,CHEN Chang'an, et al. Research Progress on the Retention Behavior of Deuterium/Helium in Tungsten as a Plasma Facing Material[J]. Materials Reports, 2017, 31(9): 112-117.

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http://www.mater-rep.com/EN/10.11896/j.issn.1005-023X.2017.09.015 OR http://www.mater-rep.com/EN/Y2017/V31/I9/112

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