Comparative modeling studies of carbon and tungsten impurity transport in the boundary plasma of EAST with a partially detached divertor condition

doi:10.1016/j.nme.2022.101259

	Comparative modeling studies of carbon and tungsten impurity transport in the boundary plasma of EAST with a partially detached divertor condition
	Xu, Guoliang 2; Wang, Hui 1,2; Ding, Rui 2; Liu, Xiaoju 2; Si, Hang 2; Zhu, Dahuan 2; Yan, Rong 2; Hai, Ran 3; Xie, Hai 2; Chen, Junling 2
刊名	NUCLEAR MATERIALS AND ENERGY
	2022-10-01
卷号	33
DOI	10.1016/j.nme.2022.101259
通讯作者	Ding, Rui(rding@ipp.ac.cn)
英文摘要	The source and leakage of both C and W are comparatively studied for a partially detached divertor operation condition on EAST. Based on the EAST experiments, sequential SOLPS-DIVIMP simulations are carried out to study the transport of intrinsic impurities in the boundary plasma. Carbon distribution from the fluid SOLPS simulation is in good agreement with the impurity tracing results from the Monte-Carlo DIVIMP simulation. The impurity leakage processes from the divertor target to the core plasma are quantitatively analyzed and divided into three parts: the prompt redeposition, the divertor screening, and the main SOL screening. Under the partially detached divertor condition, W has a higher prompt redeposition rate and a weaker cross-field transport from the main SOL to the core region than C. However, the strong parallel impurity transport from the divertor region to the main SOL makes the total leakage rate of W two times higher than that of C. The impurity velocity gained from the ion temperature gradient force in both the near-SOL detached region and the far-SOL attached region is evaluated. The relatively higher ion temperature gradient velocity of W in the attached region is the main reason for the higher divertor leakage rate than C, and the strong W source in the far-SOL makes the leakage from the attached region more significant.
资助项目	National MCF Energy R&D Program of China[2022YFE03180100] ; National MCF Energy R&D Program of China[2019YFE03080100] ; National Natural Science Foundation of China[12022511] ; National Natural Science Foundation of China[12005143] ; National Natural Science Foundation of China[12005142] ; National Natural Science Foundation of China[12075283] ; Key Research Program of Frontier Sciences, CAS[ZDBS-LY-SLH010] ; Science Foundation of Institute of Plasma Physics, Chinese Academy[DSJJ-2021-02] ; Collaborative Innovation Program of Hefei Science Center Chinese Academy of Sciences[2020HSC-CIP015]
WOS关键词	DIII-D ; FACING COMPONENTS ; ASDEX UPGRADE ; EROSION ; DEPOSITION ; BEHAVIOR ; LAYER ; FLOW
WOS研究方向	Nuclear Science & Technology
语种	英语
出版者	ELSEVIER
WOS记录号	WOS:000862873900002
资助机构	National MCF Energy R&D Program of China ; National Natural Science Foundation of China ; Key Research Program of Frontier Sciences, CAS ; Science Foundation of Institute of Plasma Physics, Chinese Academy ; Collaborative Innovation Program of Hefei Science Center Chinese Academy of Sciences
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/129271]
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.Univ Sci & Technol China, Sci Isl Branch, Grad Sch, Hefei 230026, Peoples R China 2.Chinese Acad Sci, Inst Plasma Phys, Hefei Inst Phys Sci, Hefei 230031, Peoples R China 3.Dalian Univ Technol, Sch Phys, Key Lab Mat Modificat Laser Ion & Electron Beams, Dalian 116024, Peoples R China
推荐引用方式 GB/T 7714	Xu, Guoliang,Wang, Hui,Ding, Rui,et al. Comparative modeling studies of carbon and tungsten impurity transport in the boundary plasma of EAST with a partially detached divertor condition[J]. NUCLEAR MATERIALS AND ENERGY,2022,33.
APA	Xu, Guoliang.,Wang, Hui.,Ding, Rui.,Liu, Xiaoju.,Si, Hang.,...&Chen, Junling.(2022).Comparative modeling studies of carbon and tungsten impurity transport in the boundary plasma of EAST with a partially detached divertor condition.NUCLEAR MATERIALS AND ENERGY,33.
MLA	Xu, Guoliang,et al."Comparative modeling studies of carbon and tungsten impurity transport in the boundary plasma of EAST with a partially detached divertor condition".NUCLEAR MATERIALS AND ENERGY 33(2022).