PLASMA CURRENT AND SHAPE CONTROL IN TOKAMAKS

This paper is focused on the plasma shape and current control in a large, next generation tokamak characterized by long-duration plasma discharges. The new features of these fusion devices are described and their impact on the feedback control requirements are investigated. Many of the controller design issues are addressed in the HJp synthesis framework, including the model reduction, the power constraints, the voltage limits and plant uncertainties. The application to the case of the International Thermonuclear Experimental Reactor (ITER) shows the effectiveness of this approach for the design of plasma controllers.