Evaluation of target-plate heat flux for a possible snowflake divertor in CFETR using SOLPS

China Fusion Engineering Test Reactor (CFETR) is proposed as a good complement to ITER for demonstration of fusion energy. CFETR is based on both physics and some technologies of ITER. The main goals of CFETR are fusion power P-f = 50-200 MW, duty cycle time >= 0.3-0.5, and a tritium breeding ratio similar to 1.2. To explore a more effective way to manage heat exhaust in a future fusion reactor, which will have higher heating power (auxiliary heating power plus 20% of the fusion power) than ITER, a snowflake divertor (SFD) is an optional choice considered for CFETR. In this paper, the preliminary design of a SFD for CFETR is presented, including the divertor magnetic configuration and geometry. A numerical simulation is then performed to evaluate the heat flux onto the divertor targets by using SOLPS. (C) 2014 Elsevier B.V. All rights reserved.