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Divertor experiments in a toroidal plasma, with E x B drift due to an applied radial electric field

Technical Report ·
DOI:https://doi.org/10.2172/5124365· OSTI ID:5124365
It is proposed that the E x B drift arising from an externally applied electric field could be used in a tokamak or other toroidal magnetic plasma confinement device to remove plasma and impurities from the region near the wall and reduce the amount of plasma striking the wall. This could either augment or replace a conventional magnetic field divertor. Among the possible advantages of this scheme are easy external control over the rate of removal of plasma, more rapid removal than the naturally occurring rate in a magnetic divertor, and simplification of construction if the magnetic divertor is eliminated. Results of several related experiments performed in the Wisconsin Levitated Octupole are presented.
Research Organization:
Wisconsin Univ., Madison (USA)
DOE Contract Number:
AS02-76ET53051
OSTI ID:
5124365
Report Number(s):
COO-2387-117
Country of Publication:
United States
Language:
English