Optimization of a WCCB blanket module with detached first wall for CFETR

Abstract

State-of-the-art blanket designs in fusion reactor engineering tend to use a first wall to protect the plasma facing components from high surface heat flux. This first wall is prone to get damaged, and thus should better be easily replaceable for convenient maintenance. The wall should also have a tungsten cladding of reasonable thickness to balance the blanket's tritium breeding and plasma shielding capabilities. In this regard, optimization of a CFETR water-cooled ceramic breeder (WCCB) blanket module is proposed. Compared to the present design, the optimized module features a detached first wall bolted to the back part of the blanket, with thickened tungsten armor covered on the surface. The new design not only allows convenient replacement and maintenance by remote handling, but is expected to provide improved protection against plasma surface loads. This paper presents the detailed design of the proposed blanket module, as well as feasibility analysis results from thermo-mechanical and thermal-hydraulics aspects.