Characterization of disruption halo current between ‘W-Like’ graphite divertor and ‘ITER-Like’ divertor structure on EAST tokamak

doi:10.1088/1361-6587/aba366

	Characterization of disruption halo current between ‘W-Like’ graphite divertor and ‘ITER-Like’ divertor structure on EAST tokamak
	Chen,D L 2; Granetz,R S 1; Zeng,L 2; Shen,B 2; Qian,J P 2; Liu,L 2; Xue,M M 2; Shi,T H 2; Wang,H H 2; Sun,Y W 2
刊名	Plasma Physics and Controlled Fusion
	2020-08-07
卷号	62
关键词	plasma disruption halo current lower hybrid wave vertical displacement event disruption mitigation
ISSN号	0741-3335
DOI	10.1088/1361-6587/aba366
通讯作者	Chen,D L() ; Shen,B()
英文摘要	Abstract The general characteristics of disruption halo currents, including current flowing paths between the components, are studied in the experiments of EAST tokamak with ‘W-Like’ graphite divertor and ‘ITER-like’ tungsten divertor. It is found that lower hybrid waves can efficiently reheat minor disruption plasma, this can drive plasma current for tens, or even hundreds, of milliseconds. The reheated plasma can lead to lower loop voltage and of course lower halo current. Additionally, it is confirmed that helium can not rapidly cool down plasmas with high thermal energy, but Argon can shut down plasma rapidly even with a little amount of gas. Until now no runaway electron plateau has been observed both in Argon and Helium mitigation experiments. The EAST disruption database shows that: (1) Larger loop voltage is driven in vertical displacement event disruptions than in major disruptions. (2) Halo currents decrease with the decrease of vertical displacement. (3) The boundary of IhIp0×TPF is 0.72, less than the limit shown in IDDB. The experimental results described here can help to improve the design of the planned upgrade of the EAST lower divertor, and provide physics information for the ITER divertor.
语种	英语
出版者	IOP Publishing
WOS记录号	IOP:0741-3335-62-9-ABA366
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/104935]
专题	中国科学院合肥物质科学研究院
通讯作者	Chen,D L; Shen,B
作者单位	1.MIT Plasma Science and Fusion Center, Cambridge, MA 02139, United States of America 2.Institute of Plasma Physics, Chinese Academy of Sciences, PO Box 1126, Hefei 230031, People’s Republic of China 3.School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230031, People’s Republic of China
推荐引用方式 GB/T 7714	Chen,D L,Granetz,R S,Zeng,L,et al. Characterization of disruption halo current between ‘W-Like’ graphite divertor and ‘ITER-Like’ divertor structure on EAST tokamak[J]. Plasma Physics and Controlled Fusion,2020,62.
APA	Chen,D L.,Granetz,R S.,Zeng,L.,Shen,B.,Qian,J P.,...&Xiao,B J.(2020).Characterization of disruption halo current between ‘W-Like’ graphite divertor and ‘ITER-Like’ divertor structure on EAST tokamak.Plasma Physics and Controlled Fusion,62.
MLA	Chen,D L,et al."Characterization of disruption halo current between ‘W-Like’ graphite divertor and ‘ITER-Like’ divertor structure on EAST tokamak".Plasma Physics and Controlled Fusion 62(2020).