Abstract
The fluid simulation of Small Size Divertor Tokamak (SSDT) plasma edge by the B2-SOLPS5.0 2D [1] transport code gives the following results: First, in the vicinity of separatrix the radial electric field result is not close to the neoclassical electric field. Second, the shear of radial electric field is independent on plasma parameters. Third, switching on poloidal drifts (E×B and diamagnetic drifts) leads to asymmetric parallel and poloidal fluxes from outer to inner plates and upper part of SOL for normal direction of toroidal magnetic field. Fourth, for the normal direction of toroidal magnetic, the radial electric field of SSDT is affected by the variation in temperature heating of plasma. Fifth, the parallel flux is directed from inner to outer plate in case of discharge without neutral beam injection (NBI).
Highlights
A regime of improved confinement is extremely important for the operation of a thermonuclear reactor
In computation region the coordinate which vary in the direction along flux surfaces (x-coordinate or poloidal coordinate) and the coordinate which vary in the direction across flux surfaces (y-coordinate or radial coordinate)
Switching on the poloidal drifts leads to decrease of the parallel velocity, because the poloidal projection of the parallel velocity not compensates poloidal E B drifts, so that the poloidal rotation changes
Summary
A regime of improved confinement is extremely important for the operation of a thermonuclear reactor. Switching on poloidal drifts (E×B and diamagnetic drifts) leads to asymmetric parallel and poloidal fluxes from outer to inner plates and upper part of SOL for normal direction of toroidal magnetic field. For the normal direction of toroidal magnetic, the radial electric field of SSDT is affected by the variation in temperature heating of plasma.
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