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Title: Spherical torus fusion reactor

Abstract

The object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.

Inventors:
Issue Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
5641672
Application Number:
ON: DE86013767
Assignee:
Dept. of Energy
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; TOKAMAK TYPE REACTORS; DESIGN; SPHERICAL CONFIGURATION; ASPECT RATIO; SPECIFICATIONS; CONFIGURATION; THERMONUCLEAR REACTORS; 700200* - Fusion Energy- Fusion Power Plant Technology

Citation Formats

Martin Peng, Y K.M. Spherical torus fusion reactor. United States: N. p., 1985. Web.
Martin Peng, Y K.M. Spherical torus fusion reactor. United States.
Martin Peng, Y K.M. Thu . "Spherical torus fusion reactor". United States.
@article{osti_5641672,
title = {Spherical torus fusion reactor},
author = {Martin Peng, Y K.M.},
abstractNote = {The object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1985},
month = {10}
}