Compact DT fusion spherical tori at modest fields

Conference · Tue Jan 01 04:00:00 EST 1985

OSTI ID:5437904

Peng, Y K.M.

A spherical torus is obtained by retaining only the indispensable components on the inboard side of a tokamak plasma, such as a cooled, normal conductor that carries current to produce a toroidal magnetic field. The resulting device features an exceptionally small aspect ratio (typically 2-to-1 elongation), and ramp-up and maintenance of the plasma current primarily by noninductive means. The tokamak plasma takes on the spherical shape with a modest hole through the center, suggesting the name of spherical torus. This paper reviews the initial assessments of near-term DT fusion devices based on the spherical torus concept.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5437904
• Report Number(s): CONF-850610-37; ON: DE85016415
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CLOSED PLASMA DEVICES
COMPACT TORUS
CONFIGURATION
DEUTERIUM
DOCUMENT TYPES
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
HIGH-BETA PLASMA
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MAGNET COILS
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PLASMA
RADIOISOTOPES
REVIEWS
SPHERICAL CONFIGURATION
STABLE ISOTOPES
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TORI
TRITIUM
YEARS LIVING RADIOISOTOPES