Abstract
Tokamak Simulation Code (TSC) is a numerical model of an axisymmetric free boundary tokamak plasma and the associated control systems. The time dependence of ohmic discharges of China Fusion Engineering Test Reactor (CFETR) has been simulated using TSC in this work. The TSC numerical model, CFETR device and plasma parameters are presented. According to the CFETR design requirements, the poloidal field coils current waveforms are designed. The ramp up, flat top, ramp down in double-null configuration ohmic discharge plasma current are simulated by the poloidal field coils current waveforms and NBI heating. Displacement feedback system and current feedback system are used to control the plasma from the limiter shape to the divertor shape. Major radius, minor radius, triangle deformation, elongation, plasma configuration are obtained. The calculation results can be beneficial to provide the references for CFETR physics design and components design.
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