Features incorporated in the design of the International Thermonuclear Expe
rimental Reactor (ITER) tokamak and its ancillary and plasma diagnostic sys
tems that facilitate operation and control of ignited and/or high Q DT plas
mas are presented. Control methods based upon straightforward extrapolation
of techniques employed ill the present generation of tokamaks are found to
be adequate and effective for ITER plasma control with fusion powers of up
to 1.5 GW and burn durations of greater than or equal to 1000 s. Examples
of simulations of key plasma control functions, including plasma magnetic c
onfiguration control and fusion burn (power) control, are given. The prospe
cts for the creation and control of steady state plasmas sustained by non-i
nductive current drive and bootstrap current are also discussed.