Characterization of the plasma current quench during disruptions in the National Spherical Torus Experiment

被引：94

作者：

Gerhardt, S. P. ^{[1
]}

Menard, J. E. ^{[1
]}

机构：

[1] Princeton Plasma Phys Lab, Plainsboro, NJ USA

来源：

NUCLEAR FUSION | 2009年 / 49卷 / 02期

基金：

美国能源部;

关键词：

HALO CURRENTS; OPERATIONAL LIMITS; EXPERIMENT NSTX; MHD STABILITY; CHAPTER; TOKAMAK; JT-60U; JET; MITIGATION; MAGNITUDE;

D O I：

10.1088/0029-5515/49/2/025005

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 detailed analysis of the plasma current quench in the National Spherical Torus Experiment (Ono et al 2000 Nucl. Fusion 40 557) is presented. The fastest current quenches are fit better by a linear waveform than an exponential one. Area-normalized current quench times down to 0.4 ms m(-2) have been observed, compared with the minimum of the 1.7 ms m(-2) recommendation based on conventional aspect ratio tokamaks; as noted in previous ITPA studies, the difference can be explained by the reduced self-inductance at low aspect ratio and high elongation. The maximum instantaneous dI(P)/dt is often many times larger than the mean quench rate, and the plasma current before the disruption is often substantially less than the flat-top value. The poloidal field time derivative during the disruption, which is directly responsible for driving eddy currents, has been recorded at various locations around the vessel. The I(P) quench rate, plasma motion and magnetic geometry all play important roles in determining the rate of poloidal field change.

引用

页数：12

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