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Title: Spherical torus experiment (STX)

Abstract

The principal engineering features of the proposed Spherical Torus Experiment (STX) are described. Design is dominated by the small bore available for the ohmic heating (OH) solenoid and structural considerations for a situation in which B/sub p/ is approximately equal to B/sub t/. Unique features of a spherical torus plasma include large elongations without shaping fields; an exceptionally high ratio of plasma current to toroidal field, giving the potential for stability at very high beta; strong paramagnetism; and a variety of configurations, ranging from tokamak (q/sub a/) to revised-field pinch (RFP) (q/sub a/ < 1). Access to this regime requires aspect ratios less than 2. A feasibility study has been done for a beam-heated device with A = 1.67, R0 = 0.45, and K = 2. 3 refs., 9 figs.

Authors:
;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
6072688
Report Number(s):
CONF-851102-42
ON: DE86003812; TRN: 86-005255
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: 11. symposium on engineering problems in fusion research, Austin, TX, USA, 18 Nov 1985
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; SPHEROMAK DEVICES; DESIGN; COMPUTER-AIDED DESIGN; JOULE HEATING; MAGNETS; PRESSURE VESSELS; CLOSED PLASMA DEVICES; CONTAINERS; ELECTRIC HEATING; HEATING; PLASMA HEATING; RESISTANCE HEATING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; 700200* - Fusion Energy- Fusion Power Plant Technology

Citation Formats

McManamy, T J, and Lazarus, E A. Spherical torus experiment (STX). United States: N. p., 1985. Web.
McManamy, T J, & Lazarus, E A. Spherical torus experiment (STX). United States.
McManamy, T J, and Lazarus, E A. 1985. "Spherical torus experiment (STX)". United States. https://www.osti.gov/servlets/purl/6072688.
@article{osti_6072688,
title = {Spherical torus experiment (STX)},
author = {McManamy, T J and Lazarus, E A},
abstractNote = {The principal engineering features of the proposed Spherical Torus Experiment (STX) are described. Design is dominated by the small bore available for the ohmic heating (OH) solenoid and structural considerations for a situation in which B/sub p/ is approximately equal to B/sub t/. Unique features of a spherical torus plasma include large elongations without shaping fields; an exceptionally high ratio of plasma current to toroidal field, giving the potential for stability at very high beta; strong paramagnetism; and a variety of configurations, ranging from tokamak (q/sub a/) to revised-field pinch (RFP) (q/sub a/ < 1). Access to this regime requires aspect ratios less than 2. A feasibility study has been done for a beam-heated device with A = 1.67, R0 = 0.45, and K = 2. 3 refs., 9 figs.},
doi = {},
url = {https://www.osti.gov/biblio/6072688}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jan 01 00:00:00 EST 1985},
month = {Tue Jan 01 00:00:00 EST 1985}
}

Conference:
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