Configuration development and structural assessment of the FEDC ignitor concept

Conference · Wed Jan 01 04:00:00 EST 1986

OSTI ID:5258175

Brown, T G; Lee, V D; Mayhall, J A

The Fusion Engineering Design Center (FEDC) performed a design study for a compact ignition tokamak. The ignitor concept has two unique features. First, the throat of the copper plate toroidal field (TF) coils is preloaded in the vertical direction to minimize the stress levels in the copper. Second, the net inward radial TF coil forces are balanced by a combination of wedging on the adjacent faces of the TF coils and by bucking against the ohmic heating solenoid coils in the bore of the tokamak. Later ignitor concepts eliminated the wedging reactions. Both of these features inherently reduce the radial build of the tokamak device. The FEDC version of ignitor incorporates both of these unique features packaged in a different configurational arrangement. The FEDC ignitor features a totally external preload system. The preload is applied directly to the inner leg of the TF coils in the vertical direction only. Horizontal rings are utilized only to react inplane TF coil forces and are not part of the preload system. Modular quadrants of TF coil encasements are utilized to vastly simplify device assembly methods. This paper presents the configuration and a structural assessment of the FEDC ignitor concept.

• Research Organization: Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5258175
• Report Number(s): CONF-860652-27; ON: DE87000019
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
CLOSED PLASMA DEVICES
COMPACT TORUS
DESIGN
ELECTRIC COILS
ELECTRIC HEATING
ELECTRICAL EQUIPMENT
EQUIPMENT
HEATING
JOULE HEATING
MAGNET COILS
MECHANICAL STRUCTURES
PLASMA HEATING
RESISTANCE HEATING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TORI