Engineering design of the National Spherical Torus Experiment

被引:27
作者
Neumeyer, C
Heitzenroeder, P
Spitzer, J
Chrzanowski, J
Brooks, A
Bialek, J
Fan, HM
Barnes, G
Viola, M
Nelson, B
Goranson, P
Wilson, R
Fredd, E
Dudek, L
Parsells, R
Kalish, M
Blanchard, W
Kaita, R
Kugel, H
McCormack, B
Ramakrishnan, S
Hatcher, R
Oliaro, G
Perry, E
Egebo, T
Von Halle, A
Williams, M
Ono, M
机构
[1] Princeton Univ, Dept Energy, Princeton Plasma Phys Lab, Princeton, NJ 08544 USA
[2] Oak Ridge Natl Lab, Oak Ridge, TN USA
[3] Columbia Univ, New York, NY USA
关键词
engineering design; the National Spherical Torus Experiment; proof-of-principle spherical torus;
D O I
10.1016/S0920-3796(00)00469-5
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
NSTX is a proof-of-principle experiment aimed at exploring the physics of the 'spherical torus' (ST) configuration. which is predicted to exhibit more efficient magnetic confinement than conventional large aspect ratio tokamaks. among other advantages. The low aspect ratio (R/a, typically 1.2-2 in ST designs compared to 4-5 in conventional tokamaks) decreases the available cross sectional area through the center of the torus for toroidal and poloidal field coil conductors, vacuum vessel wall, plasma facing components. etc.. thus increasing the need to deploy all components within the so-called 'center stack' in the most efficient manner possible. Several unique design features have been developed for the NSTX center stack, and careful engineering of this region of the machine, utilizing materials up to their engineering allowables. has been key to meeting the desired objectives. The design and construction of the machine has been accomplished in a rapid and cost effective manner thanks to the availability of extensive facilities, a strong experience base from the TFTR era. and good cooperation between institutions. (C) 2001 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:275 / 319
页数:45
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