First results of the use of a continuously flowing lithium limiter in high performance discharges in the EAST device

被引:91
作者
Hu, J. S. [1 ]
Zuo, G. Z. [1 ]
Ren, J. [1 ]
Yang, Q. X. [1 ]
Chen, Z. X. [1 ]
Xu, H. [1 ]
Zakharov, L. E. [2 ]
Maingi, R. [3 ]
Gentile, C. [3 ]
Meng, X. C. [1 ,4 ]
Sun, Z. [1 ]
Xu, W. [1 ]
Chen, Y. [1 ]
Fan, D. [1 ]
Yan, N. [1 ]
Duan, Y. M. [1 ]
Yang, Z. D. [1 ]
Zhao, H. L. [1 ]
Song, Y. T. [1 ]
Zhang, X. D. [1 ]
Wan, B. N. [1 ]
Li, J. G. [1 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
[2] LiWallFusion, PO 2391, Princeton, NJ 08543 USA
[3] Princeton Univ, Princeton Plasma Phys Lab, POB 451, Princeton, NJ 08543 USA
[4] Hunan Univ, Dept Appl Phys, Changsha 410082, Hunan, Peoples R China
关键词
lithium; flowing liquid limiter; plasma facing material; EAST; TOKAMAK; REGIME;
D O I
10.1088/0029-5515/56/4/046011
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
As an alternative choice of solid plasma facing components (PFCs), flowing liquid lithium can serve as a limiter or divertor PFC and offers a self-healing surface with acceptable heat removal and good impurity control. Such a system could improve plasma performance, and therefore be attractive for future fusion devices. Recently, a continuously flowing liquid lithium (FLiLi) limiter has been successfully designed and tested in the EAST superconducting tokamak. A circulating lithium layer with a thickness of < 0.1 mm and a flow rate similar to 2 cm(3) s(-1) was achieved. A novel in-vessel electro-magnetic pump, working with the toroidal magnetic field of the EAST device, was reliable to control the lithium flow speed. The flowing liquid limiter was found to be fully compatible with various plasma scenarios, including high confinement mode plasmas heated by lower hybrid waves or by neutral beam injection. It was also found that the controllable lithium emission from the limiter was beneficial for the reduction of recycling and impurities, for the reduction of divertor heat flux, and in certain cases, for the improvement of plasma stored energy, which bodes well application for the use of flowing liquid lithium PFCs in future fusion devices.
引用
收藏
页数:14
相关论文
共 35 条
[1]   First experiments with lithium limiter on FTU [J].
Apicella, M. L. ;
Mazzitelli, G. ;
Ridolfini, V. Pericoll ;
Lazarev, V. ;
Alekseyev, A. ;
Vertkov, A. ;
Zagorski, R. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 363 :1346-1351
[2]   Dependence of the L-H transition on X-point geometry and divertor recycling on NSTX [J].
Battaglia, D. J. ;
Chang, C. S. ;
Kaye, S. M. ;
Kim, K. ;
Ku, S. ;
Maingi, R. ;
Bell, R. E. ;
Diallo, A. ;
Gerhardt, S. ;
LeBlanc, B. P. ;
Menard, J. ;
Podesta, M. .
NUCLEAR FUSION, 2013, 53 (11)
[3]   Plasma response to lithium-coated plasma-facing components in the National Spherical Torus Experiment [J].
Bell, M. G. ;
Kugel, H. W. ;
Kaita, R. ;
Zakharov, L. E. ;
Schneider, H. ;
LeBlanc, B. P. ;
Mansfield, D. ;
Bell, R. E. ;
Maingi, R. ;
Ding, S. ;
Kaye, S. M. ;
Paul, S. F. ;
Gerhardt, S. P. ;
Canik, J. M. ;
Hosea, J. C. ;
Taylor, G. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2009, 51 (12)
[4]   Edge transport and turbulence reduction with lithium coated plasma facing components in the National Spherical Torus Experiment [J].
Canik, J. M. ;
Maingi, R. ;
Kubota, S. ;
Ren, Y. ;
Bell, R. E. ;
Callen, J. D. ;
Guttenfelder, W. ;
Kugel, H. W. ;
LeBlanc, B. P. ;
Osborne, T. H. ;
Soukhanovskii, V. A. .
PHYSICS OF PLASMAS, 2011, 18 (05)
[5]  
Coenen J. W., 2014, PHYS SCR T, V159, P7
[6]   Overview of plasma-material interaction experiments on EAST employing MAPES [J].
Ding, Fang ;
Luo, Guang-Nan ;
Pitts, Richard A. ;
Litnovsky, Andrey ;
Gong, Xianzu ;
Ding, Rui ;
Mao, Hongmin ;
Zhou, Haishan ;
Wampler, William R. ;
Stangeby, Peter C. ;
Carpentier, Sophie ;
Hellwig, Maren ;
Yan, Rong ;
Ashikawa, Naoko ;
Fukumoto, Masakatsu ;
Katayama, Kazunari ;
Wang, Wenzhang ;
Wang, Huiqian ;
Chen, Liang ;
Wu, Jing ;
Chen, Jinling ;
Liu, Songlin ;
Xie, Chunyi .
JOURNAL OF NUCLEAR MATERIALS, 2014, 455 (1-3) :710-716
[7]   Recent advances in long-pulse high-confinement plasma operations in Experimental Advanced Superconducting Tokamak [J].
Guo, H. Y. ;
Li, J. ;
Wan, B. N. ;
Gong, X. Z. ;
Liang, Y. F. ;
Xu, G. S. ;
Zhang, X. D. ;
Ding, S. Y. ;
Gan, K. F. ;
Hu, J. S. ;
Hu, L. Q. ;
Liu, S. C. ;
Qian, J. P. ;
Sun, Y. W. ;
Wang, H. Q. ;
Wang, L. ;
Xia, T. Y. ;
Xiao, B. J. ;
Zeng, L. ;
Zhao, Y. P. ;
Denner, P. ;
Ferron, J. R. ;
Garofalo, A. M. ;
Holcomb, C. T. ;
Hyatt, A. W. ;
Jackson, G. L. ;
Loarte, A. ;
Maingi, R. ;
Menard, J. E. ;
Rack, M. ;
Solomon, W. M. ;
Xu, X. Q. ;
Van Zeeland, M. ;
Zou, X. L. .
PHYSICS OF PLASMAS, 2014, 21 (05)
[8]   New Steady-State Quiescent High-Confinement Plasma in an Experimental Advanced Superconducting Tokamak [J].
Hu, J. S. ;
Sun, Z. ;
Guo, H. Y. ;
Li, J. G. ;
Wan, B. N. ;
Wang, H. Q. ;
Ding, S. Y. ;
Xu, G. S. ;
Liang, Y. F. ;
Mansfield, D. K. ;
Maingi, R. ;
Zou, X. L. ;
Wang, L. ;
Ren, J. ;
Zuo, G. Z. ;
Zhang, L. ;
Duan, Y. M. ;
Shi, T. H. ;
Hu, L. Q. .
PHYSICAL REVIEW LETTERS, 2015, 114 (05)
[9]   An overview of lithium experiments on HT-7 and EAST during 2012 [J].
Hu, J. S. ;
Ren, J. ;
Sun, Z. ;
Zuo, G. Z. ;
Yang, Q. X. ;
Li, J. G. ;
Mansfield, D. K. ;
Zakharov, L. E. ;
Ruzic, D. N. .
FUSION ENGINEERING AND DESIGN, 2014, 89 (12) :2875-2885
[10]   Investigation of lithium as plasma facing materials on HT-7 [J].
Hu, J. S. ;
Zuo, G. Z. ;
Li, J. G. ;
Luo, N. C. ;
Zakharov, L. E. ;
Zhang, L. ;
Zhang, W. ;
Xu, P. .
FUSION ENGINEERING AND DESIGN, 2010, 85 (06) :930-934