On heat removal from the first-wall elements and warm toroidal field coils in the JUST-T tokamak

Abstract

Heat removal from the structural elements of a compact tokamak with warm coils intended for the transmutation of minor actinides is an especially critical problem. This paper is concerned with the thermal processes on the first-wall elements and the toroidal field windings, ignoring the most stressed component of JUST-T, i.e. the blanket. The analysis has shown that the peak load on the first-wall elements in JUST-T does not exceed a similar load in the International Thermonuclear Experimental Reactor tokamak. The two-dimensional numerical code for calculation of the current distribution density, Ohmic heating and heat transfer due to heat conductivity and extraction of heat by the water flux has been developed.

Keywords:

• Tokamak
• Volumetric neutron source
• Divertor
• Warm coil

Acknowledgements

This work was performed under the auspices of the Russian Fund of Fundamental Research (grant 05-02-08137-OFI_e).