National Spherical Torus Experiment: engineering overview and research results 1999-2000

被引：3

作者：

Neumeyer, C ^{[1
]}

机构：

[1] Princeton Univ, Plasma Phys Lab, Princeton, NJ 08543 USA

来源：

FUSION ENGINEERING AND DESIGN | 2001年 / 56-57卷

关键词：

National Spherical Torus Experiment; engineering design; spherical torus;

D O I：

10.1016/S0920-3796(01)00411-2

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 Torus Experiment (NSTX) is a new US 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 magnetic confinement concept which is characterized by high beta (ratio plasma pressure to magnetic field pressure) and low toroidal field compared to conventional tokamaks, and could provide a pathway to the realization of a practical fusion power source. NSTX achieved first plasma in February 1999, and since that time has completed and commissioned all components and systems within the machine proper. Routine operation with inductively driven plasma current less than or equal to1 MA and flat top less than or equal to0.3 s has been established, and the ohmic characterization phase of the research program is underway. Radio frequency (RF) and neutral beam injection (NBI) systems have been installed and are presently being commissioned. This paper describes the NSTX mission, gives an overview of the engineering design, and summarizes the research results obtained thus far. (C) 2001 Elsevier Science B.V. All rights reserved.

引用

页码：807 / 812

页数：6

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