Conceptual design study of a doublet fusion ignition test reactor

Conference · Sun Jan 01 04:00:00 EST 1978

OSTI ID:6235917

Sager, P.

The results of a conceptual design study of an ignition test reactor with niobium--titanium superconducting toroidal field coils are presented. This reactor, which is designed to reach ignition conditions and provide a plasma burn of 30 seconds, has a major radius of 3.8 m, a plasma minor radius of 1.1 m, and a doublet plasma height-to-width ratio of 2.7 m. These specifications were derived from parametric sstudies in which the overall cost was minimized for a reactor providing a modest ignition margin with Alcator scaling. The remote maintenance system is briefly described. While the reactor is designed so that contact maintenance can be performed on components outside the shield envelope, special equipment is designed to gain access to components inside the shield envelope and to permit direct observation and limited adjustments during setup procedures.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• DOE Contract Number: EY-76-C-03-0167-038
• OSTI ID: 6235917
• Report Number(s): GA-A-14795; CONF-781217-1
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
DESIGN
DOUBLET REACTORS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
MAGNETS
MAINTENANCE
REMOTE HANDLING
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR IGNITION
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS