INTOR physics

Conference · Thu Jan 01 04:00:00 EST 1981 · Proc. Symp. Eng. Probl. Fusion Res.; (United States)

OSTI ID:6362002

Schmidt, J A

The overall INTOR size and magnetic field parameters have been established as part of the INTOR transport modelling program. These studies, based on the presently accepted transport coefficients, have established the INTOR ignition margin and overall INTOR performance. Divertor modelling studies have focused on the performance of the INTOR poloidal field divertor. These studies have shown that the neutrals are confined to the divertor channel, thereby limiting the charge exchange erosion of the first wall. The strong cooling produced by the neutrals reduces the ion temperature in the divertor. The impurities eroded from the divertor plate have a low probability of entering the main discharge.

• Research Organization: Princeton Univ, NJ, USA
• OSTI ID: 6362002
• Report Number(s): CONF-811040-
• Conference Information: Journal Name: Proc. Symp. Eng. Probl. Fusion Res.; (United States)
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
ANNULAR SPACE
CONFIGURATION
DESIGN
DIVERTORS
ELECTRIC COILS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
FLUID MECHANICS
HEATING
HYDRODYNAMICS
INTOR TOKAMAK
MAGNET COILS
MAGNETOHYDRODYNAMICS
MAGNETS
MECHANICS
PLASMA HEATING
POLOIDAL DIVERTORS
SPACE
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TOROIDAL CONFIGURATION
TRANSPORT THEORY