NIFS-077

FULL TEXT (PDF, 664 KB)


Author(s):

N. Ohyabu

Title:

High Temperature Divertor Plasma Operation

Date of publication:

Feb. 1991

Key words:

Tokamak, Stellarator, Divertor, Bundle Divertor, High Temperature Divertor Plasma, Improvement of Energy confinement

Abstract:

High temperature divertor plasma operation has been proposed, which is expected to enhance the core energy confinement and eliminates the heat removal problem. In this approach, the heat flux is guided through divertor channel to a remote area with a large target surface, resulting in low heat load on the target plate. This allows pumping of the particles escaping from the core and hence maintaining of the high divertor temperature, which is comparable to the core temperature. The energy confinement is then determined by the diffusion coefficient of the core plasma, which has been observed to be much lower than the thermal diffusivity.

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