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 two-time-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. Fusion51 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, Ψ(x), (b) the poloidal flux profile together with the normalized pressure parameter, βN, and (c) the inverse of the safety factor profile, , are described.
首次在DIII-D上进行了集成磁性和动力学变量的实时剖面控制实验，旨在调节并将先进托卡马克方案外推至稳态装置和燃烧等离子体装置。利用在JET、JT-60U和DIII-D上经过验证的通用双时间尺度方法，从实验数据中获得了面向控制的装置特定模型，该验证是在国际托卡马克物理活动集成运行方案框架下进行的（Moreau等，2011，Nucl. Fusion 51, 045009）。在DIII-D上，这些数据驱动模型被用于综合设计磁性和动力学剖面的集成控制器。中性束注入（NBI）、电子回旋电流驱动（ECCD）系统和欧姆线圈提供了加热与电流驱动（H&CD）源。第一个控制执行器是等离子体表面环电压（即欧姆线圈），而可用的束线和回旋管被分组为五个额外的H&CD执行器：同向轴NBI、同向离轴NBI、反向NBI、平衡NBI以及所有回旋管的总ECCD功率（具有离轴电流沉积）。本文描述了成功实现闭环控制的实验，分别控制了（a）极向磁通剖面Ψ(x)，（b）极向磁通剖面与归一化压力参数βN，以及（c）安全因子剖面倒数 的闭环控制。