Poloidal divertor experiment with applied E vector x B vector/B/sup 2/ drift
It has been proposed that the E vector x B vector/B/sup 2/ drift arising from an externally applied electric field could be used in a tokamak or other toroidal device to remove plasma and impurities from the region near the wall and to reduce the amount of plasma striking the wall, either assisting or replacing a conventional magnetic field divertor. A poloidal magnetic divertor (without pumping chamber) was added to the Wisconsin Levitated Toroidal Octupole, and the octupole was operated with a tokamak-like magnetic field configuration (q = 0.7). A radial electric field was applied in the scrape-off zone, causing an E vector x B vector/B/sup 2/ drift with a large poloidal component. This reduced plasma flux reaching the wall of the toroid by up to a factor of 5 beyond the effect of the magnetic divertor, for divertor configurations with both high and low magnetic mirror ratios, in good agreement with a simple theoretical model. Plasma density and density scale length were also reduced in the scrape-off zone, in qualitative agreement with the model. This was not accompanied by any new instabilities in the scrape-off zone, nor by any appreciable degradation of confinement of the central plasma.
- Research Organization:
- Wisconsin Univ., Madison (USA)
- Sponsoring Organization:
- USDOE Asslstant Secretary for Energy Technology
- DOE Contract Number:
- AS02-76ET53051
- OSTI ID:
- 5176100
- Report Number(s):
- DOE/ET/53051-5
- Country of Publication:
- United States
- Language:
- English
Similar Records
Experimental demonstration of vector E x vector B plasma divertor
Experimental demonstration of E x B plasma divertor
Divertor experiments in a toroidal plasma, with E x B drift due to an applied radial electric field
Technical Report
·
Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:6531992
Experimental demonstration of E x B plasma divertor
Journal Article
·
Thu Nov 30 23:00:00 EST 1978
· Phys. Fluids; (United States)
·
OSTI ID:6651238
Divertor experiments in a toroidal plasma, with E x B drift due to an applied radial electric field
Technical Report
·
Sat Sep 01 00:00:00 EDT 1979
·
OSTI ID:5124365
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
CLOSED CONFIGURATIONS
CLOSED PLASMA DEVICES
DIVERTORS
ELECTRIC FIELDS
IMPURITIES
MAGNETIC FIELD CONFIGURATIONS
MULTIPOLAR CONFIGURATIONS
OCTUPOLAR CONFIGURATIONS
PLASMA DRIFT
POLOIDAL DIVERTORS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
CLOSED CONFIGURATIONS
CLOSED PLASMA DEVICES
DIVERTORS
ELECTRIC FIELDS
IMPURITIES
MAGNETIC FIELD CONFIGURATIONS
MULTIPOLAR CONFIGURATIONS
OCTUPOLAR CONFIGURATIONS
PLASMA DRIFT
POLOIDAL DIVERTORS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES