Abstract
A superconducting steady state tokamak is being designed to address some of the physics and technological issues of steady state operation. Circular plasma operation with poloidal limiter and elongated plasma operation with poloidal divertor are planned for a maximum steady state input power of 0.2 MW and 1 MW, respectively. The conceptual design of various plasma facing components is discussed. The poloidal limiter and divertor are actively cooled so as to keep the surface temperature of the plasma facing components less than 1000°C. In the present design the steady state heat removal capability is limited to a maximum of 1 MW/m 2 due to mechanical attachment scheme adopted for armor tile mounting to the actively cooled substrate. The plasma facing component surfaces have been profiled/shaped so that maximum steady state heat flux on the surface is ≤ 1 MW/m 2.
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