NONINDUCTIVE CURRENT DRIVE EXPERIMENTS ON DIII-D, AND FUTURE-PLANS

Citation
R. Prater et al., NONINDUCTIVE CURRENT DRIVE EXPERIMENTS ON DIII-D, AND FUTURE-PLANS, Fusion engineering and design, 26(1-4), 1995, pp. 49-58
Citations number
9
Categorie Soggetti
Nuclear Sciences & Tecnology
ISSN journal
09203796
Volume
26
Issue
1-4
Year of publication
1995
Pages
49 - 58
Database
ISI
SICI code
0920-3796(1995)26:1-4<49:NCDEOD>2.0.ZU;2-H
Abstract
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.