Advances in plasma-wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST

被引:49
|
作者
Wang, L. [1 ]
Guo, H. Y. [1 ,2 ]
Ding, F. [1 ]
Yu, Y. W. [1 ]
Yuan, Q. P. [1 ]
Xu, G. S. [1 ]
Wang, H. Q. [1 ,2 ]
Zhang, L. [1 ]
Ding, R. [1 ]
Xu, J. C. [1 ]
Liu, J. B. [1 ]
Zhang, B. [1 ]
Wu, K. [1 ]
Li, K. D. [1 ]
Duan, Y. M. [1 ]
Luo, Z. P. [1 ]
Wu, J. H. [1 ]
Zuo, G. Z. [1 ]
Sun, Z. [1 ]
Eldon, D. [2 ]
Leonard, A. W. [2 ]
Petrie, T. [2 ]
Hyatt, A. [2 ]
Humphreys, D. [2 ]
Thomas, D. [2 ]
Yang, Z. S. [1 ]
Chen, X. H. [1 ]
Feng, W. [1 ]
Chen, L. [1 ]
Meng, L. Y. [1 ]
Qian, X. Y. [1 ]
Liang, Y. [1 ,3 ]
Sang, C. F. [4 ]
Xiao, B. J. [1 ]
Luo, G-N [1 ]
Hu, J. S. [1 ]
Maingi, R. [5 ]
Zou, X. L. [6 ]
Qian, J. P. [1 ]
Gong, X. Z. [1 ]
Garofalo, A. M. [2 ]
Li, J. [1 ]
Wan, B. N. [1 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
[2] Gen Atom, POB 85608, San Diego, CA 92186 USA
[3] Assoc EURATOM FZ Julich, D-52425 Julich, Germany
[4] Dalian Univ Technol, Dalian 116024, Peoples R China
[5] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[6] CEA, IRFM, F-13108 St Paul Les Durance, France
基金
中国国家自然科学基金;
关键词
divertor; plasma-wall interaction; power and particle exhaust; tungsten sputtering; EAST; LITHIUM; PERFORMANCE; SOL;
D O I
10.1088/1741-4326/ab1ed4
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
A total power injection up to 0.3 GJ has been achieved in EAST long pulse H-mode operation of 101.2 s with an ITER-like water-cooled tungsten (W) mono-block divertor, which has steady-state power exhaust capability of 10 MWm(-2). The peak temperature of W target saturated at 12 s to the value T similar to 500 degrees C with a heat flux similar to 3.3 MW m(-2) being maintained during the discharge. By tailoring the 3D divertor plasma footprint through edge magnetic topology change, the heat load was broadly dispersed and thus peak heat flux and W sputtering were well controlled. Active feedback control of H-mode detachment with D-2 fuelling or divertor impurity seeding has been achieved successfully, with excellent compatibility with the core plasma performance. Active feedback control of radiative power utilizing neon seeding was achieved with f(rad) = 18%-41% in H-mode operation, exhibiting potential for heat flux reduction with divertor and edge radiation. This has been further demonstrated in DIII-D high beta(P) H-mode scenario within the joint DIII-D/EAST experiment using impurity seeding from the divertor volume. Steady-state particle control and impurity exhaust has been achieved for long pulse H-mode operation over 100 s with the W divertor by leveraging the effect of drifts and optimized divertor configuration, coupled with strong pumping and extensive wall conditioning. Approaches toward the reduction of divertor W sourcing, which is of crucial importance for a metal-wall tokamak, are also explored. These advances provide important experimental information on favourable core-edge integration for high power, long-pulse H-mode operation in EAST, ITER and CFETR.
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页数:11
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