Design activities on helical DEMO reactor FFHR-d1

Based on high-density and high-temperature plasma experiments in the large helical device (LHD), conceptual design studies of the LHD-type helical DEMO reactor FFHR-d1 have been conducted by integrating wide-ranged R&D activities on core plasmas and reactor technologies through cooperative researches under the fusion engineering research project, which has been launched newly in NIFS. Current activities for the FFHR-d1 in this project are presented on design window analyses with designs on core plasma, neutronics for liquid blankets, continuous helical magnets, pellet fueling, tritium systems and plasma heating devices.

► Conceptual design studies of the helical DEMO reactor FFHR-d1 have been conducted. ► Design window analyses with core plasma and engineering designs have been carried out. ► R&Ds on blanket, magnet, tritium control, fuelling and heating systems are discussed.