Experimental demonstration of E x B plasma divertor

Journal Article · Fri Dec 01 04:00:00 EST 1978 · Phys. Fluids; (United States)

DOI:https://doi.org/10.1063/1.862186· OSTI ID:6651238

Strait, E J; Kerst, D W; Sprott, J C

The E x B drift due to an applied radial electric field in a tokamak with poloidal divertor can speed the flow of plasma out of the scrape-off region, and provide a means of externally controlling the flow rate and thus the width of the density fall-off. An experiment in the Wisconsin levitated toroidal octupole, using E x B drifts alone, demonstrates divertor-like behavior, including 70% reduction of plasma density near the wall and 40% reduction of plasma flux to the wall, with no adverse effects on confinement of the main plasma.

• Research Organization: Department of Physics, University of Wisconsin-Madison, Madison, Wisconsin 53706
• OSTI ID: 6651238
• Journal Information: Phys. Fluids; (United States), Journal Name: Phys. Fluids; (United States) Vol. 21:12; ISSN PFLDA
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700101* -- Fusion Energy-- Plasma Research-- Confinement
Heating
& Production
ANNULAR SPACE
CLOSED PLASMA DEVICES
CONFIGURATION
CROSSED FIELDS
DIVERTORS
ELECTRIC FIELDS
MAGNETIC FIELDS
PLASMA DENSITY
PLASMA DRIFT
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TOROIDAL CONFIGURATION