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The current feeder system consisting of superconducting (SC) bus-lines, SC bus-line interface terminal, and current leads is used as the current transmission system for the KSTAR SC coils. The current lead system consists of 11 pairs of vapor-cooled leads for the PF coils and a pair of leads for the TF coils. The PF coils are operated at full currents only during a portion of the entire time. The heat loads of current leads in idle mode, when it carries no current, depend quite strongly on the using material. We have measured the heat load and temperature profile when the overload current was charged in 200 A optimum brass lead. Also, the current feeder system requires a long bus-line that must supply a large amount of current from a current lead to SC coils. We have designed a SC bus-line with NbTi cable-in-conduit conductor (CICC) to reduce Joule heating loss. The CICC is cooled with forced-flow supercritical helium (SHe). The bus-line requires higher reliability and safety than those of the SC coils of the KSTAR. The KSTAR bus-line has been designed to have an independent vacuum space and consist of SHe return and 60 K thermal shield line for shielding. To connect the bus-line with a cryostat of the KSTAR and current lead box, we have developed a prototype SC bus-line interface terminal.

The insulation system of the Korea Superconducting Tokamak Advanced Research (KSTAR) device plays a role of the structural element by binding the conductor jackets as well as breaking the current. The KSTAR Central Solenoid (CS) coils are stacked with four pairs of coils with up-down symmetry. The insulation of the CS coils experiences various stress states, such as tensile, normal compressive, and shear stresses due to applied preload at room temperature, thermal contraction difference during cool-down, and magnetic forces during operation. In particular, the normal tension and shear of the insulation has been a critical issue for magnet design. In this paper, a more detailed model in addition to electromagnetic and global structural analysis will be constructed and analyzed to evaluate the insulation stress. The results may suggest appropriate allowable stress criteria for insulation systems at cryogenic temperature.

The Korea Superconducting Tokamak Advanced Research (KSTAR) device is a steady-state-capable experimental fusion device with a fully superconducting magnet system, including toroidal field (TF) coils, central solenoid (CS) coils, and poloidal field (PF) coils. The major design consideration of the magnet system is to meet the KSTAR mission with plasma current of 2 MA and toroidal field of 3.5 T at the major radius 1.8 m and z=0. The preliminary analyses show that the magnet structure design has mechanical, electrical, and thermal stability during operation. The TF magnets have a wedged structure, including coil cases, inter-coil structures, and inter-octant joints. The CS and PF structures are designed to support the electromagnetic forces. To support the coil system against gravity and lateral loads, gravity support and lateral load structures are designed.