Effect of plasma shaping on performance in the national spherical torus experiment

被引:35
作者
Gates, D. A.
Maingi, R.
Menard, J.
Kaye, S.
Sabbagh, S. A.
Taylor, G.
Wilson, J. R.
Bell, M. G.
Bell, R. E.
Bernabei, S.
Bialek, J.
Biewer, T.
Blanchard, W.
Boedo, J.
Bush, C.
Carter, M. D.
Choe, W.
Crocker, N.
Darrow, D. S.
Davis, W.
Delgado-Aparicio, L.
Diem, S.
Ferron, J.
Field, A.
Foley, J.
Fredrickson, E. D.
Harvey, R.
Hatcher, R. E.
Heidbrink, W.
Hill, K.
Hosea, J. C.
Jarboe, T. R.
Johnson, D. W.
Kaita, R.
Kessel, C.
Kubota, S.
Kugel, H. W.
Lawson, J.
LeBlanc, B. P.
Lee, K. C.
Levinton, F.
Manickam, J.
Maqueda, R.
Marsala, R.
Mastrovito, D.
Mau, T. K.
Medley, S. S.
Meyer, H.
Mikkelsen, D. R.
Mueller, D.
机构
[1] Princeton Univ, Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[2] Columbia Univ, Dept Appl Phys, New York, NY 10027 USA
[3] Univ Calif San Diego, La Jolla, CA 92093 USA
[4] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[5] Korea Adv Inst Sci & Technol, Taejon 305701, South Korea
[6] Univ Calif Los Angeles, Los Angeles, CA 94524 USA
[7] Johns Hopkins Univ, Baltimore, MD 21218 USA
[8] Gen Atom Co, San Diego, CA 92186 USA
[9] UKAEA Euratom Fus Assoc, Abingdon OX14 3DB, Oxon, England
[10] CompX, Del Mar, CA 92014 USA
[11] Univ Calif Irvine, Irvine, CA 92967 USA
[12] Univ Washington, Seattle, WA 98195 USA
[13] Univ Calif Davis, Davis, CA 95616 USA
[14] Nova Photon, Princeton, NJ 08540 USA
[15] Univ Colorado, Boulder, CO 80309 USA
[16] Hiroshima Univ, Hiroshima 7398511, Japan
[17] MIT, Cambridge, MA 02139 USA
[18] Lawrence Livermore Natl Lab, Livermore, CA 94550 USA
[19] Univ Tokyo, Tokyo 1138654, Japan
[20] Univ Rochester, Rochester, NY 14627 USA
基金
英国工程与自然科学研究理事会;
关键词
D O I
10.1063/1.2198174
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
The National Spherical Torus Experiment (NSTX) has explored the effects of shaping on plasma performance as determined by many diverse topics including the stability of global magnetohydrodynamic (MHD) modes (e.g., ideal external kinks and resistive wall modes), edge localized modes (ELMs), bootstrap current drive, divertor flux expansion, and heat transport. Improved shaping capability has been crucial to achieving beta(t)similar to 40%. Precise plasma shape control has been achieved on NSTX using real-time equilibrium reconstruction. NSTX has simultaneously achieved elongation kappa similar to 2.8 and triangularity delta similar to 0.8. Ideal MHD theory predicts increased stability at high values of shaping factor S equivalent to q(95)I(p)/(aB(t)), which has been observed at large values of the S similar to 37[MA/(m center dot T)] on NSTX. The behavior of ELMs is observed to depend on plasma shape. A description of the ELM regimes attained as shape is varied will be presented. Increased shaping is predicted to increase the bootstrap fraction at fixed I-p. The achievement of strong shaping has enabled operation with 1 s pulses with I-p=1 MA, and for 1.6 s for I-p=700 kA. Analysis of the noninductive current fraction as well as empirical analysis of the achievable plasma pulse length as elongation is varied will be presented. Data are presented showing a reduction in peak divertor heat load due to increasing in flux expansion. (c) 2006 American Institute of Physics.
引用
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页数:7
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