Progress in the Initial Design Activities for the Cfetr Divertor Development

The Chinese Fusion Engineering Testing Reactor (CFETR) divertor development is ongoing by further optimizing the water-cooled divertor design scheme finished in the CFETR engineering design stage and research and development (R&D) of small, medium-sized test mock-ups and prototype fabrication based on realizable fusion reactor materials and material connection technology. To increase the tritium breeding ratio (TBR) of at least 0.04, The CFETR divertor development would adopt a hybrid divertor-blanket integration concept that breeding blanket will be placed underneath target components (TCs) instead of cassette. This paper summarizes the initial design activities influenced by the new concept. The new concept aims to explore high heat load handling configuration together with remote handling (RH) from plasma side and hybrid divertor-blanket design. The dome position is lowered in the aspect of divertor geometry. The TCs are more convenient for neutrons passing through instead of shielding. The preliminary interface design between the divertor and lower blanket system is presented. By developing independent RH technology for the inner TCs, dome TCs and outer TCs, assembly/dis-assembly of the TCs on the lower blanket can be realized. The new advanced tungsten flat-type mock-up is successfully endured the 1000 cycles with 20 MW/m 2 steady state (SS) heat load. All this work will be beneficial for final divertor scheme of fusion reactor.