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.
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