Experiments on DIII-D (and other tokamaks) have shown that improved pe
rformance can follow from optimization of the current density profile.
Increased confinement of energy and a higher limit on beta have both
been found in discharges in which the current density profile is modif
ied through transient means, such as ramping of current or elongation.
Peaking of the current distribution to obtain discharges with high in
ternal inductance l(i) has been found to be beneficial. Alternatively,
discharges with broader profiles, as in the VH mode or with high beta
poloidal, have shown improved performance. Non-inductive current driv
e is a means to access these modes of improved confinement on a steady
state basis. Accordingly, experiments on non-inductive current drive
are underway on the DIII-D tokamak using fast waves and electron cyclo
tron waves. Recent experiments on fast wave current drive have demonst
rated the ability to drive up to 180 kA of non-inductive current using
1.5 MW of power at 60 MHz, including the contribution from 1 MW of EC
CD and the bootstrap current. Higher power r.f. current drive systems
are needed to affect strongly the current profile on DIII-D. An upgrad
e to the fast wave current drive system is underway to increase the to
tal power to 6 MW, using two additional antennas and two new 30-120 MH
z transmitters. Additionally, a 1 MW prototype ECH system at 110 GHz i
s being developed (with eventual upgrade to 10 MW). With these systems
, non-inductive current drive at the 1 MA level will be available for
experiments on profile control in DIII-D.