Exploration of spherical torus physics in the NSTX device

被引：356
|
作者：
Ono, M
Kaye, SM
Peng, YKM
Barnes, G
Blanchard, W
Carter, MD
Chrzanowski, J
Dudek, L
Ewig, R
Gates, D
Hatcher, RE
Jarboe, T
Jardin, SC
Johnson, D
Kaita, R
Kalish, M
Kessel, CE
Kugel, HW
Maingi, R
Majeski, R
Manickam, J
McCormack, B
Menard, J
Mueller, D
Nelson, BA
Nelson, BE
Neumeyer, C
Oliaro, G
Paoletti, F
Parsells, R
Perry, E
Pomphrey, N
Ramakrishnan, S
Raman, R
Rewoldt, G
Robinson, J
Roquemore, AL
Ryan, P
Sabbagh, S
Swain, D
Synakowski, EJ
Viola, M
Williams, M
Wilson, JR
机构：
[1] Princeton Univ, Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[2] Oak Ridge Natl Lab, Oak Ridge, TN USA
[3] Univ Washington, Seattle, WA 98195 USA
[4] Columbia Univ, New York, NY USA
来源：
NUCLEAR FUSION | 2000年 / 40卷 / 3Y期
关键词：
D O I：
10.1088/0029-5515/40/3Y/316
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) is being built at Princeton Plasma Physics Laboratory to test the fusion physics principles for the spherical torus concept at the MA level. The NSTX nominal plasma parameters are R-o = 85 cm; a = 67 cm, R/a greater than or equal to 1.26, B-t = 3 kG, I-p = 1 MA, q(95) = 14, elongation k less than or equal to 2.2, triangularity delta less than or equal to 0.5 and a plasma pulse length of up to 5 s. The plasma heating/current drive tools are high harmonic fast wave (6 MW, 5 s), neutral beam injection (5 MW, 80 keV, 5 s) and coaxial helicity injection. Theoretical calculations predict that NSTX should provide exciting possibilities for exploring a number of important new physics regimes, including very high plasma beta, naturally high plasma elongation, high bootstrap current fraction, absolute magnetic well and high pressure driven sheared flow. In addition, the NSTX programme plans to explore fully non-inductive plasma startup as well as a dispersive scrape-off layer for heat and particle flux handling.
引用
收藏
页码：557 / 561
页数：5
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