A review of lithium application for the plasma-facing material in EAST Tokamak

被引:3
|
作者
Hu, J. S. [1 ,2 ]
Li, L. [1 ]
Zuo, G. Z. [1 ]
Sun, Z. [3 ]
Xu, W. [1 ,4 ]
Meng, X. C. [1 ,4 ]
Li, C. L. [1 ,4 ]
Tang, Z. L. [1 ]
Sun, J. Z. [5 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, HFIPS, Hefei 230031, Anhui, Peoples R China
[2] CAS Key Lab Photovolta & Energy Conservat Mat, Hefei 230031, Anhui, Peoples R China
[3] Princeton Univ, Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[4] Inst Energy, Hefei Comprehens Natl Sci Ctr, Hefei 230026, Anhui, Peoples R China
[5] Dalian Univ Technol, Sch Phys & Optoelect Technol, Dalian 116024, Liaoning, Peoples R China
关键词
Lithium; Plasma-facing material; Tokamak; EAST; STIMULATED RAMAN-SCATTERING; FINITE-BANDWIDTH DRIVER; SPACE-TIME FLUCTUATIONS; PARAMETRIC-INSTABILITIES; TEMPERATURE; IGNITION; LASERS; BACKSCATTER; GENERATION; INTENSITY;
D O I
10.1007/s41614-023-00114-7
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 a low-Z material, lithium is widely tested and used in tokamak devices for particle recycling and impurity control to improve plasma performance. Lithium application as plasma-facing materials via different methods, such as coating, injection and flowing liquid limiter, has been investigated more than 10 years on EAST. This paper presents the development of the lithium techniques applied on EAST, and reviews the progresses on the investigation of its interaction with plasma and its effects on the improvement on the plasma performances. In addition, this paper further discusses the potential applications of lithium technique in future fusion devices.
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页数:53
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