Lithium as a Plasma Facing Component to Optimize the Edge Plasma

被引：0
|
作者：
Maingi, R. [1 ]
Majeski, R. [1 ]
Menard, J. E. [1 ]
Jaworski, M. A. [1 ]
Kaita, R. [1 ]
机构：
[1] Princeton Plasma Phys Lab, POB 451, Princeton, NJ 08543 USA
来源：
2015 IEEE 26TH SYMPOSIUM ON FUSION ENGINEERING (SOFE) | 2015年
关键词：
plasma facing components; impurities; lithium; energy confinement; power exhaust; ITER; DIVERTOR; TOKAMAK; REGIME;
D O I：
暂无
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The use of lithium to coat plasma-facing components (PFCs) or serve directly as liquid PFCs has resulted in energy confinement improvement in several devices. Coupled with the demonstrated ability of liquid Li to exhaust high power fluxes, the use of Li could resolve the two leading problems of high-Z PFCs. The effect of Li in NSTX, EAST, and DIII-D is compared, and common features are identified. A compact spherical tokamak-based Fusion Nuclear Science Facility design could deliver an attractive neutral wall loading for materials testing, with Li PFCs enabling access to the required high confinement scenarios.
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页数：5
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