Gh. Neilson et al., THE TOKAMAK PHYSICS EXPERIMENT - TOKAMAK IMPROVEMENT THROUGH ADVANCEDSTEADY-STATE CONTROL, Fusion engineering and design, 26(1-4), 1995, pp. 563-574
The achievement of a long-pulse ignited discharge with over 1000 MW of
fusion power in the International Thermonuclear Experimental Reactor
will be an important goal for the next phase of the world magnetic fus
ion program. However, improvements in the physics are needed to design
a more economically attractive tokamak power reactor than the present
data base would support. Advanced, steady state plasma controls are t
he key to realizing these improvements. The Tokamak Physics Experiment
has a flexible heating and current drive system for profile control;
a flexible poloidal field system that supports a strongly shaped doubl
e-null poloidal divertor plasma configuration over a wide range of pro
files; and a divertor designed for dispersive operation, flexibility,
and remote handling. The machine performance in deuterium is sufficien
t to produce a reactor-like bootstrap current profile and to confine f
ast electrons for localized current profile control. A conducting stru
cture, plasma rotation, field error compensation coils, and profile co
ntrol are used to provide stable plasma configurations with beta up to
twice the Troyon limit and bootstrap current fraction approaching uni
ty. The facility will be designed for 1000 s pulses initially to minim
ize the influence of initial transients on system behavior, but the pu
lse length can be extended through upgrades of external systems if nec
essary.