Experimental Demonstration of E x B Plasma Divertor
E. J. Strait, D. W. Kerst, and J. C. Sprott
Department of Physics, University
of Wisconsin-Madison, Madison, Wisconsin 53706
(Received 3 April 1978; final manuscript received 27 July 1978)
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.
Ref: E. J. Strait, D. W. Kerst, and J. C. Sprott,
Phys. Fluids 21, 2342-2345 (1978)
The complete paper is available in PDF format.
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