Abstract
Determination of accurate plasma horizontal position during plasma discharge and a control system based on feedback is essential to transport it to a safe position near the set point. The design of feedback controller is usually based on primitive modeling of the plasma itself. By using the plasma-circuits linearized model, proportional integral derivative based controllers and a model for the power supply of vertical coil system with some values for its poles, we analyzed step feedback response of the overall system of IR-T1 tokamak and corresponding Bode diagrams for two cases with and without the plasma resistance and the eddy currents distribution. Although experimental validation of the plasma model and also the overall system behavior is an important exercise, the results predicted in simulation can give us good insight about system.
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