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

Gerhardt, S.P., Menard, J.E., and the NSTX Research Team

Princeton University. Plasma Physics Laboratory.

关键词: Nstx;    Eddy Currents;    Current Quench;    70 Plasma Physics And Fusion Technology;    Geometry;   

DOI  :  10.2172/948737
RP-ID  :  PPPL-4372
RP-ID  :  DE-ACO2-76CHO3073
RP-ID  :  948737

美国|英语

来源: UNT Digital Library

【 摘 要 】

A detailed analysis of the plasma current quench in the National Spherical Torus Experiment [M.Ono, et al Nuclear Fusion 40, 557 (2000)] is presented. The fastest current quenches are fit better by a linear waveform than an exponential one. Area-normalized current quench times down to .4 msec/m2 have been observed, compared to the minimum of 1.7 msec/m2 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 dIp/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 Ip quench rate, plasma motion, and magnetic geometry all play important roles in determining the rate of poloidal field change.