To settle fusion technology, technical- and engineering challenges should be solved to control unstable fusion plasma. In-vessel control coil (IVCC) in Korea Superconducting Tokamak Advanced Research (KSTAR) has been implemented for plasma control. We...
To settle fusion technology, technical- and engineering challenges should be solved to control unstable fusion plasma. In-vessel control coil (IVCC) in Korea Superconducting Tokamak Advanced Research (KSTAR) has been implemented for plasma control. We characterize the mechanical behaviors of IVCC under high heat-generation environments due to electrically induced eddy currents. Numerical evaluations reveal electromagnetic-, thermal- and mechanical responses under operating conditions. Thermal stability is assessed in terms of transient temperature variations and consequent thermal stress distributions. Experimental approaches using IVCC mock-up models are employed to validate the numerical results. We suggest candidates reduce eddy current and guarantee heat-dissipating performance via tailored methods with an upgrade of the IVCC case. The preliminary results will be the fundamental data for feasible upgrade of IVCC in KSTAR.