Optimal choice of the geometrical descriptors for tokamak plasma shape control

The need for achieving high performance plasmas (characterized by high plasma temperature, density and energy confinement time) both in todays as well as next generations tokamaks, calls for the solution of some challenging control problems, e.g. the control of the plasma shape during operation. The scope of this paper is to present a methodology to choose the plasma shape parameters to be employed by the control system as geometrical descriptors in the plasma shape feedback loop. An application to the design of the International Thermonuclear Experimental Reactor (ITER) is shown.