A unified study for determining poloidal field coil locations for a tokamak

Conference · Thu Sep 01 04:00:00 EDT 1983 · Nucl. Technol./Fusion; (United States)

OSTI ID:6234030

Srivastava, V C; Kalsi, S S

The poloidal field (PF) configuration has a major impact on the size and cost of tokamak machines. This report describes a procedure for developing a minimum cost PF system consistent with constraints imposed by plasma, magnet, and configurational design requirements. This methodology is considered adequate for developing the PF coil configurations. PF configuration studies are described for the International Tokamak Reactor (INTOR) as an illustration. The total cost of the PF system increases appreciably when an idealized PF configuration (with discrete coils) is replaced by a more practical coil configuration. The PF system with a poloidal divertor costs about 50% more than a system utilizing limiter-type impurity control.

• Research Organization: Fusion Engineering Design Center/General Electric Company, Oak Ridge National Lab., Oak Ridge, TN 37830
• OSTI ID: 6234030
• Report Number(s): CONF-830406-
• Conference Information: Journal Name: Nucl. Technol./Fusion; (United States) Journal Volume: 4:2
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
CONFIGURATION
CONTROL
COST
DIVERTORS
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
IMPURITIES
INTOR TOKAMAK
LIMITERS
MAGNET COILS
MAGNETIC FIELD CONFIGURATIONS
POLOIDAL DIVERTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS