Engineering design of the National Spherical Tokamak Experiment

被引：30
|
作者：
Spitzer, J
Ono, M
Peng, M
Bashore, D
Bigelow, T
Brooks, A
Chrzanowski, J
Fan, HM
Heitzenroeder, P
Jarboe, T
Kaita, R
Kaye, S
Kugel, H
Majeski, R
Neumeyer, C
Parsells, R
Perry, E
Pomphrey, N
Robinson, J
Strickler, D
Wilson, R
机构：
[1] OAK RIDGE NATL LAB,OAK RIDGE,TN 37831
[2] UNIV WASHINGTON,SEATTLE,WA 98155
来源：
FUSION TECHNOLOGY | 1996年 / 30卷 / 03期
关键词：
D O I：
10.13182/FST96-A11963134
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：
The National Spherical Tokamak Experiment (NSTX) is an ultra low aspect ratio device with a plasma current of 1 MA. The tokamak features auxiliary heating and current drive with a close-fitting conducting shell to maximize the plasma pressure. NSTX is designed for an experimental pulse length that will demonstrate quasisteady state non-inductively driven advanced tokamak operation. The design also takes maximum advantage of existing facilities and components from previous Princeton devices to reduce the overall program costs.
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收藏
页码：1337 / 1341
页数：5
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