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Title: National Spherical Torus Experiment (NSTX) Engineering Overview and Research Results 1999 - 2000

Abstract

The 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 to 1MA and flat top less than or equal to 0.3 seconds 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.

Authors:
Publication Date:
Research Org.:
Princeton Plasma Physics Lab., NJ (US)
Sponsoring Org.:
USDOE Office of Energy Research (ER) (US)
OSTI Identifier:
765036
Report Number(s):
PPPL-3491
TRN: US0005045
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 6 Oct 2000
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ASPECT RATIO; BEAM INJECTION; DESIGN; MAGNETIC CONFINEMENT; MAGNETIC FIELDS; OPERATION; PLASMA CONFINEMENT; PLASMA PRESSURE; RESEARCH PROGRAMS

Citation Formats

C. Neumeyer. National Spherical Torus Experiment (NSTX) Engineering Overview and Research Results 1999 - 2000. United States: N. p., 2000. Web. doi:10.2172/765036.
C. Neumeyer. National Spherical Torus Experiment (NSTX) Engineering Overview and Research Results 1999 - 2000. United States. doi:10.2172/765036.
C. Neumeyer. Fri . "National Spherical Torus Experiment (NSTX) Engineering Overview and Research Results 1999 - 2000". United States. doi:10.2172/765036. https://www.osti.gov/servlets/purl/765036.
@article{osti_765036,
title = {National Spherical Torus Experiment (NSTX) Engineering Overview and Research Results 1999 - 2000},
author = {C. Neumeyer},
abstractNote = {The 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 to 1MA and flat top less than or equal to 0.3 seconds 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.},
doi = {10.2172/765036},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Oct 06 00:00:00 EDT 2000},
month = {Fri Oct 06 00:00:00 EDT 2000}
}

Technical Report:

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