The physics of tokamak start-up

被引:61
|
作者
Mueller, D. [1 ]
机构
[1] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
关键词
HEATING ASSISTED STARTUP; DIII-D; CURRENT DRIVE; PLASMA; SUSTAINMENT; TORUS; DISCHARGE; ITER;
D O I
10.1063/1.4804416
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
Tokamak start-up on present-day devices usually relies on inductively induced voltage from a central solenoid. In some cases, inductive startup is assisted with auxiliary power from electron cyclotron radio frequency heating. International Thermonuclear Experimental Reactor, the National Spherical Torus Experiment Upgrade and JT60, now under construction, will make use of the understanding gained from present-day devices to ensure successful start-up. Design of a spherical tokamak (ST) with DT capability for nuclear component testing would require an alternative to a central solenoid because the small central column in an ST has insufficient space to provide shielding for the insulators in the solenoid. Alternative start-up techniques such as induction using outer poloidal field coils, electron Bernstein wave start-up, coaxial helicity injection, and point source helicity injection have been used with success, but require demonstration of scaling to higher plasma current. (C) 2013 AIP Publishing LLC.
引用
收藏
页数:10
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