The temporal evolution of the operating point of a fusion plasma during the
ignition access, during ignited and subignited operation phases, is analyz
ed for plasmas like that of the International Thermonuclear Experimental Re
actor (ITER) on the basis of a one-half-dimensional set of equations includ
ing feedback equations for axiliary heating and fuel supply. It is shown th
at simple proportional feedback controls do not work taking into account th
e delay times in the control process. Proportional-integral-differential (P
ID) and improved types of control are examined for the purpose of controlli
ng a fusion plasma against sudden parameter changes. On this basis a study
on the simultaneous use of D-T fuel injection and auxiliary heating control
methods for an ITER-like plasma is carried out, resulting in an algorithm
capable of finding the optimal operation point in the ignited regime or a h
igh-e operating point in a subignited case taking into account density and
beta limits and stabilizing the reactor performance against changes in conf
inement.