Methodology of Plasma Shape Reachability Area Estimation in D-Shaped Tokamaks

This paper suggests and develops a new methodology of estimation for multivariable reachability region plasma separatrix shape on the divertor phase discharge in D-shaped tokamaks. The is applied to spherical Globus-M/M2 tokamak, including controllability vertical unstable position basis experimental data. An assessment important design tokamak poloidal field coils synthesis magnetic control system. When designing it necessary avoid small vertically plasma, because such cases occur practice at restricted voltage horizon coil. To make estimations mentioned above robust, PID-controllers horizontal were designed using Quantitative Feedback Theory approach, which stabilizes system provides satisfactory indexes (stability margins, setting time, overshoot) during discharges. controllers tested series models nonlinear current inverters auto-oscillation mode as actuators control. made these models, taking into account limitations actions, i.e., voltages coils. research first step feedback operation Globus-M2 tokamak. developed may be used coil systems projects order weak achievability regions It was found that there strong cross-influence from PF-coils currents CC shape; hence, should simultaneously.