Plasma control requirements for the International Thermonuclear Experi
mental Reactor (ITER) are identified, and an overview of proposed ITER
plasma control concepts is presented. ITER will operate with a burnin
g deuterium-tritium plasma to produce 1.5 GW effusion power for durati
ons of 1000 s or more. Key plasma control requirements to achieve thes
e objectives encompass (a) plasma scenario and sequencing: plasma init
iation, current rampup, divertor formation, auxiliary heating, ignitio
n and burn, deignition (fusion power shutdown), and current rampdown a
nd termination; (b) plasma magnetics control: plasma current and shape
(R-0, a, kappa, delta) versus time, plus control of critical plasma-t
o-first-wall clearance gaps, including ion-cyclotron coupling gap and
divertor magnetic configuration, during the diverted heating/ignition/
burn/deignition phase of the plasma scenario; (c) plasma kinetics and
divertor control: core plasma density and/or fusion power, core impuri
ty content and/or radiated power fraction; core profile control (auxil
iary heating and/or current drive), and divertor control (pumping, in-
divertor gas and/or impurity injection and magnetic configuration opti
mization for divertor performance); and (d) fast plasma shutdown: fusi
on power and current shutdown by means of impurity injection. Physics
and hardware concepts are presented as to how these plasma control fun
ctions will be implemented. Diagnostic measurements needed for plasma
control are summarized. The relationship of plasma control to machine
protection and public safety is also addressed.