Engineering overview of the national spherical torus experiment (NSTX)

被引：0

作者：

Neumeyer, C ^{[1
]}

Heitzenroeder, P ^{[1
]}

Chrzanowski, J ^{[1
]}

Nelson, B ^{[1
]}

Spitzer, J ^{[1
]}

Wilson, R ^{[1
]}

Dudek, L ^{[1
]}

Kaita, R ^{[1
]}

Ramakrishnan, S ^{[1
]}

Bashore, D ^{[1
]}

Perry, E ^{[1
]}

机构：

[1] Princeton Univ, Plasma Phys Lab, Princeton, NJ 08540 USA

来源：

17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2 | 1998年

关键词：

D O I：

暂无

中图分类号：

TM [电工技术]; TN [电子技术、通信技术];

学科分类号：

0808 ; 0809 ;

摘要：

The NSTX Project will provide a national facility for the study of plasma confinement, heating, and current drive in a low aspect ratio, spherical torus (ST) configuration, The ST configuration is an alternate confinement concept which is characterized by high beta, high elongation, high bootstrap fraction, and low BT compared to conventional tokamaks, NSTX is the next step ST experiment following smaller experiments such as the PPPL CDX-U (Current Drive Experiment, Upgrade), the START (Small Tight Aspect Ratio Tokamak) at Culham, and the HIT (Helicity Injected Tokamak) at University of Washington, and is similar in scale to the MAST (Meg-Amp Spherical Tokamak) machine now under construction at Culham. This paper provides a description of mission and gives an overview of the main engineering features of the design of the machine and facility and discusses some of the key design solutions.

引用

页码：221 / 226

页数：6

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