Gas jet disruption mitigation studies on Alcator C-Mod and DIII-D

被引:73
作者
Granetz, R. S. [1 ]
Hollmann, E. M.
Whyte, D. G.
Izzo, V. A.
Antar, G. Y.
Bader, A.
Bakhtiari, M.
Biewer, T.
Boedo, J. A.
Evans, T. E.
Hutchinson, I. H.
Jernigan, T. C.
Gray, D. S.
Groth, M.
Humphreys, D. A.
Lasnier, C. J.
Moyer, R. A.
Parks, P. B.
Reinke, M. L.
Rudakov, D. L.
Strait, E. J.
Terry, J. L.
Wesley, J.
West, W. P.
Wurden, G.
Yu, J.
机构
[1] MIT, Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA
[2] Univ Calif San Diego, FERP, La Jolla, CA 92093 USA
[3] Univ Wisconsin, Dept Engn Phys, Madison, WI 53706 USA
[4] Gen Atom Co, San Diego, CA 92186 USA
[5] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[6] Lawrence Livermore Natl Lab, Livermore, CA 94550 USA
[7] Los Alamos Natl Lab, Los Alamos, NM 87545 USA
关键词
D O I
10.1088/0029-5515/47/9/003
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
High-pressure noble gas jet injection is a mitigation technique which potentially satisfies the requirements of fast response time and reliability, without degrading subsequent discharges. Previously reported gas jet experiments on DIII-D showed good success at reducing deleterious disruption effects. In this paper, results of recent gas jet disruption mitigation experiments on Alcator C-Mod and DIII-D are reported. Jointly, these experiments have greatly improved the understanding of gas jet dynamics and the processes involved in mitigating disruption effects. In both machines, the sequence of events following gas injection is observed to be quite similar: the jet neutrals stop near the plasma edge, the edge temperature collapses and large MHD modes are quickly destabilized, mixing the hot plasma core with the edge impurity ions and radiating away the plasma thermal energy. High radiated power fractions are achieved, thus reducing the conducted heat loads to the chamber walls and divertor. A significant (2x or more) reduction in halo current is also observed. Runaway electron generation is small or absent. These similar results in two quite different tokamaks are encouraging for the applicability of this disruption mitigation technique to ITER.
引用
收藏
页码:1086 / 1091
页数:6
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