Thermal-hydraulic analysis of PF coils during plasma discharges on EAST

For the consideration of superconducting magnet stability, it is important to keep enough temperature margin under the different operating conditions for the plasma discharge in Tokamak. In order to estimate the stability of the magnets for Experimental Advanced Superconducting Tokamak (EAST), the code SAITOKPF is used to analyze the operating characteristics of the Poloidal Field (PF) coils with the actual operating scenarios. The simulated results are validated by the experimental data. It is found that the heat load of PF1-6 coils is much larger than that of the other coils. Therefore, the investigation is emphasized on the PF1- 6 coils. The analysis includes the AC losses, temperature distribution in the space, temperature margin, and maximum temperature of strands.