Conceptual design of a blanket module integrated with divertor for CFETR

Abstract

Achieving tritium self-sufficiency (tritium breeding ratio (TBR)≥1.1) is one of the most important missions of the Chinese Fusion Engineering Test Reactor (CFETR). The neutronics analysis shows that the global TBR of the CFETR water-cooled ceramic breeder (WCCB) blanket is 1.147 when the plasma is surrounded by blankets (without any windows), which can meet the tritium self-sufficiency requirement. In the engineering design phase, however, a number of blanket modules are replaced by auxiliary systems. It would lead to decline of TBR and failure of tritium self-sufficiency. Therefore, a new blanket module concept extended to the divertor region and integrated with the divertor is proposed to increase TBR. The blanket module is located at the back of the divertor target plates. This paper presents the design of the proposed blanket module. The feasibility of the blanket design is evaluated considering neutronics, thermal and mechanical performances.