Plasma-facing components damage and its effects on plasma performance in EAST tokamak

doi:10.1016/j.fusengdes.2020.111616

HFCAS OpenIR

	Plasma-facing components damage and its effects on plasma performance in EAST tokamak
	Gao, Binfu 1,2; Ding, Rui1 ; Xie, Hai 1,3; Zeng, Long 1; Zhang, Ling1 ; Wang, Baoguo 2; Li, Changjun 1,2; Zhu, Dahuan1 ; Yan, Rong1 ; Chen, Junling1
	2020-07-01
发表期刊	FUSION ENGINEERING AND DESIGN
ISSN	0920-3796
通讯作者	Ding, Rui(rding@ipp.ac.cn)
摘要	During the tokamak operations, plasma-wall interactions (PWI) can severely damage the plasma-facing cornponents (PFCs), which will lead to degradation of plasma performance due to radiation losses by the impurities released from the damaged PFCs surfaces. The PFCs damage and its effects on the plasma performance are studied experimentally for the EAST tokamak. Substantial dusts were generated from the hot spots at the guard limiter of LHCD antenna and the tungsten (W) melting processes from the W upper divertor, which results in disruption due to high radiation losses. Two methods can be effectively used to recover the plasma discharges after tungsten melting induced disruptions, reducing the auxiliary heating power or moving away the position of strike point from the melting site. Statistics analysis indicate that about 12.0 % and 38.3 % of disruptions were due to severe impurity burst from the strong PWI processes in 2017 and 2018 campaign, respectively. In 2018 campaign, the plasma disruption due to tungsten impurity burst is about 26.3 %, which is much higher than 4.8 % in 2017 campaign. This is due to the higher auxiliary heating power, larger misalignment on W PFCs and the new W guard limiter. The main features on the effects of PFC damage on plasma operation are shown.
关键词	Hot spot W melting Disruptions Radiation EAST tokamak
DOI	10.1016/j.fusengdes.2020.111616
关键词[WOS]	GUARD LIMITER
收录类别	SCI
语种	英语
资助项目	National Key Research and Development Program of China[2017YFE0301300] ; National Key Research and Development Program of China[2017YFE0300500] ; National Key Research and Development Program of China[2017YFA0402500] ; National Nature Science Foundation of China[11675218] ; National Nature Science Foundation of China[11575244] ; National Nature Science Foundation of China[11861131010] ; CASHIPS Director's Fund[BJPY2019B01] ; Key Research Program of Frontier Sciences of CAS[ZDBS-LY-SLH010]
项目资助者	National Key Research and Development Program of China ; National Nature Science Foundation of China ; CASHIPS Director's Fund ; Key Research Program of Frontier Sciences of CAS
WOS研究方向	Nuclear Science & Technology
WOS类目	Nuclear Science & Technology
WOS记录号	WOS:000540064300009
出版者	ELSEVIER SCIENCE SA
引用统计	被引频次：24[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.hfcas.ac.cn:8080/handle/334002/103052
专题	中国科学院合肥物质科学研究院
通讯作者	Ding, Rui
作者单位	1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China 2.Univ Sci & Technol China, Hefei 230031, Peoples R China 3.Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China
第一作者单位	中科院等离子体物理研究所
通讯作者单位	中科院等离子体物理研究所
推荐引用方式 GB/T 7714	Gao, Binfu,Ding, Rui,Xie, Hai,et al. Plasma-facing components damage and its effects on plasma performance in EAST tokamak[J]. FUSION ENGINEERING AND DESIGN,2020,156.
APA	Gao, Binfu.,Ding, Rui.,Xie, Hai.,Zeng, Long.,Zhang, Ling.,...&Chen, Junling.(2020).Plasma-facing components damage and its effects on plasma performance in EAST tokamak.FUSION ENGINEERING AND DESIGN,156.
MLA	Gao, Binfu,et al."Plasma-facing components damage and its effects on plasma performance in EAST tokamak".FUSION ENGINEERING AND DESIGN 156(2020).