Integrated Magnetic and Kinetic Control of Advanced Tokamak Scenarios Based on Data-Driven Models
D. Moreau, M.L. Walker, J.R. Ferron, F. Liu, E. Schuster, J.E. Barton, M.D. Boyer, K.H. Burrell, S.M. Flanagan,P. Gohil, R.J. Groebner, C.T. Holcomb, D.A. Humphreys, A.W. Hyatt, R.D. Johnson, R.J. La Haye, J. Lohr, T.C. Luce, J.M. Park, B.G. Penaflor, W. Shi, F. Turco, W. Wehner and the ITPA-IOS group members and experts
Nuclear Fusion 53 (2013) 063020 (14pp)
Abstract
|
|
The first real-time profile control experiments integrating magnetic and kinetic variables were performed on DIII-D
in view of regulating and extrapolating advanced tokamak scenarios to steady-state devices and burning plasma
experiments. Device-specific, control-oriented models were obtained from experimental data using a generic
twotime-scale method that was validated on JET, JT-60U and DIII-D under the framework of the International Tokamak
Physics Activity for Integrated Operation Scenarios (Moreau et al 2011 Nucl. Fusion 51 063009). On DIII-D, these
data-driven models were used to synthesize integrated magnetic and kinetic profile controllers. The neutral beam
injection (NBI), electron cyclotron current drive (ECCD) systems and ohmic coil provided the heating and current
drive (H&CD) sources. The first control actuator was the plasma surface loop voltage (i.e. the ohmic coil), and the
available beamlines and gyrotrons were grouped to form five additional H&CD actuators: co-current on-axis NBI,
co-current off-axis NBI, counter-current NBI, balanced NBI and total ECCD power from all gyrotrons (with off-axis
current deposition). Successful closed-loop experiments showing the control of (a) the poloidal flux profile,
(b) the poloidal flux profile together with the normalized pressure parameter, and (c) the inverse of the safety
factor profile are described.