Sawtooth control using electron cyclotron current drive in ITER demonstration plasmas in DIII-D

被引:39
|
作者
Chapman, I. T. [1 ]
La Haye, R. J. [2 ]
Buttery, R. J. [2 ]
Heidbrink, W. W. [3 ]
Jackson, G. L. [2 ]
Muscatello, C. M. [3 ]
Petty, C. C. [2 ]
Pinsker, R. I. [2 ]
Tobias, B. J. [4 ]
Turco, F. [5 ]
机构
[1] Euratom CCFE Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] Gen Atom Co, San Diego, CA 92186 USA
[3] Univ Calif Irvine, Irvine, CA 92697 USA
[4] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[5] Columbia Univ, Dept Appl Phys & Appl Math, New York, NY USA
关键词
INTERNAL KINK MODE; STABILITY; SAWTEETH; TOKAMAK; STABILIZATION; OSCILLATIONS; ROTATION; PERIOD; ALPHA; ECCD;
D O I
10.1088/0029-5515/52/6/063006
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
Sawtooth control using electron cyclotron current drive (ECCD) has been demonstrated in ITER-like plasmas with a large fast ion fraction, wide q = 1 radius and long uncontrolled sawtooth period in DIII-D. The sawtooth period is minimized when the ECCD resonance is just inside the q = 1 surface. Sawtooth destabilization using driven current inside q = 1 avoids the triggering of performance-degrading neoclassical tearing modes (NTMs), even at much higher pressure than required in the ITER baseline scenario. Operation at beta(N) = 3 without 3/2 or 2/1 NTMs has been achieved in ITER demonstration plasmas when sawtooth control is applied using only modest ECCD power. Numerical modelling qualitatively confirms that the achieved driven current changes the local magnetic shear sufficiently to compensate for the stabilizing influence of the energetic particles in the plasma core.
引用
收藏
页数:8
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