Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years

doi:10.1007/s10894-021-00290-9

HFCAS OpenIR

	Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years
	Wang, L.1 ; Xu, G. S.1; Hu, J. S.1; Li, K. D.1; Yuan, Q. P.1; Liu, J. B.1; Ding, F.1 ; Yu, Y. W.1; Luo, Z. P.1; Xu, J. C.1; Meng, L. Y.1; Wu, K.1; Zhang, B.1 ; Chen, M. W.1; Deng, G. Z.1; Liu, X. J.1; Yang, Z. S.1; Liu, X.1 ; Liu, S. C.1; Ding, R.1 ; Zuo, G. Z.1; Sun, Z.1 ; Wu, J. H.1; Cao, B.1 ; Zhang, Y.1 ; Duan, Y. M.1; Zhang, L.1 ; Qian, X. Y.1; Li, A.1 ; Chen, L.1 ; Jia, M. N.1; Si, H.1 ; Xia, T. Y.1; Sun, Y. W.1; Chen, Y. P.1; Li, Q.1; Luo, G. N.1; Yao, D. M.1; Xiao, B. J.1; Gong, X. Z.1; Zhang, X. D.1; Wan, B. N.1; Wang, H. Q.2; Guo, H. Y.2; Eldon, D.2; Garofalo, A. M.2; Liang, Y.3; Xu, S.3; Sang, C. F.4; Wang, D. Z.4; Dai, S. Y.4; Sun, J. Z.4; Ding, H. B.4; Maingi, R.5; Gan, K. F.5; Zou, X. L.6; Du, H. L.7
	2021-06-01
发表期刊	JOURNAL OF FUSION ENERGY
ISSN	0164-0313
通讯作者	Wang, L.(lwang@ipp.ac.cn)
摘要	Active control of the excessively high heat and particle fluxes on the divertor target plates is of fundamental importance to the steady state operation of tokamaks, especially for fusion reactors. A series of experiments have been carried out on this critical issue to relieve the plasma-wall interactions in the experimental advanced superconducting tokamak (EAST) in the last ten years, not only contributing to the long pulse operation of EAST itself, but also providing physical understandings and potential techniques to the next-generation devices like ITER. We have characterized the power deposition pattern and broadened the divertor footprint width effectively. The plasma-wetted area is actively handled using either 3-dimentional edge magnetic topology or advanced plasma equilibrium, thereby peak heat flux around the strike point is reduced. Active control of detachment or radiation compatible with core plasma performance has progressed significantly in very recent years, with a series of active feedback control modules developed and utilized successfully, based on the divertor physics advances with both experiments and simulation. The upper divertor of EAST was upgraded from graphite to active water-cooling ITER-like tungsten in 2014, exhibiting much enhanced heat removal capability. As for the particle exhaust including both fueling and impurity particles, in addition to wall conditioning and impurity source control, the efficiency of particle flux exhaust is optimized by making full use of the divertor closure and the plasma drifts in both scrape-off layer and divertor volume. These heat and particle exhaust advances contribute greatly to a series of EAST achievements like H-mode operation over 100 s. A brief near-term plan on the integrated control of divertor plasma-wall interactions in long-time scale will also be introduced, aiming to provide favorable divertor operation solution for ITER and CFETR.
关键词	Divertor Heat flux Particle exhaust Active control EAST
DOI	10.1007/s10894-021-00290-9
收录类别	SCI
语种	英语
资助项目	National Key R&D Program of China[2017YFE0301300] ; National Key R&D Program of China[2017YFA0402500] ; National Key R&D Program of China[2019YFE03030000] ; Institute of Energy, Hefei Comprehensive National Science Center[GXXT-2020-004] ; National Natural Science Foundation of China[11922513] ; National Natural Science Foundation of China[U19A20113] ; National Natural Science Foundation of China[11905255] ; Key Research Program of Frontier Sciences (CAS)[QYZDBSSW-SLH001] ; K. C. Wong Education Foundation ; AHNSF[1808085J07] ; Users with Excellence Project of Hefei Science Center CAS[2018HSC-UE008]
项目资助者	National Key R&D Program of China ; Institute of Energy, Hefei Comprehensive National Science Center ; National Natural Science Foundation of China ; Key Research Program of Frontier Sciences (CAS) ; K. C. Wong Education Foundation ; AHNSF ; Users with Excellence Project of Hefei Science Center CAS
WOS研究方向	Nuclear Science & Technology
WOS类目	Nuclear Science & Technology
WOS记录号	WOS:000636746300001
出版者	SPRINGER
引用统计	被引频次：12[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/334002/121604
专题	中国科学院合肥物质科学研究院
通讯作者	Wang, L.
作者单位	1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 2.Gen Atom, POB 85608, San Diego, CA 92186 USA 3.Forschungszentrum Julich, Inst Energie & Klimaforsch Plasmaphys, Partner Trilateral Euregio Cluster TEC, D-52425 Julich, Germany 4.Dalian Univ Technol, Dalian 116024, Peoples R China 5.Princeton Plasma Phys Lab, Princeton, NJ 08543 USA 6.IRFM, F-13108 St Paul Les Durance, France 7.Southwestern Inst Phys, Chengdu 610041, 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	Wang, L.,Xu, G. S.,Hu, J. S.,et al. Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years[J]. JOURNAL OF FUSION ENERGY,2021,40.
APA	Wang, L..,Xu, G. S..,Hu, J. S..,Li, K. D..,Yuan, Q. P..,...&Du, H. L..(2021).Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years.JOURNAL OF FUSION ENERGY,40.
MLA	Wang, L.,et al."Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years".JOURNAL OF FUSION ENERGY 40(2021).