Performance test and analysis of the first large-scale cable-in-conduit conductor with high $J$$_{c}$ Nb$_{3}$Sn strand for fusion reactor

The Comprehensive Research Facility for Fusion Technology (CRAFT) project has been launched in 2019, for developing the essential engineering technologies for Chinese Fusion Engineering Testing Reactor (CFETR). Within this project, a full-size toroidal field (TF) coil will be built as the prototype coil for CFETR. Based on design of CFETR magnet system, the TF coil will operate at 95.6 kA in a peak field of 14.5 T. The high-$J$$_{c}$ Nb$_{3}$Sn strand is taken into consideration due to the critical current density of ITER-grade Nb$_{3}$Sn is too low at 14.5 T. Considering that it will be the first time to apply the high-$J$$_{c}$ Nb$_{3}$Sn strand in the large-scale cable-in-conduit conductor (CICC) for fusion magnet, a conductor sample made of high-$J$$_{c}$ Nb$_{3}$Sn strand with short twist pitch (STP) cable pattern was manufactured in ASIPP and tested in SULTAN facility, to investigate the feasibility. The test campaign focuses on the impact of cyclic electromagnetic (EM) loading and warm-up cool-down (WUCD) to the performance of the conductor, the strain distribution of the conductor before and after EM cycles was measured by inductive method to make a deeper insight of the conductor performance evolution. AC losses tests have also been carried out, providing relevant information for further coil design.