Plasma control system(PCS),mainly developed for real-time feedback control calculation,plays a significant part during normal discharges in a magnetic fusion device,while the tokamak simulation code(TSC) is a nonlinear numerical model that studies the time evolution of an axisymmetric magnetized tokamak plasma.The motivation to combine these two codes for an integrated simulation is specified by the facts that the control system module in TSC is relatively simple compared to PCS,and meanwhile,newly-implemented control algorithms in PCS,before applied to experimental validations,require numerical validations against a tokamak plasma simulator that TSC can act as.In this paper,details of establishment of the integrated simulation framework between the EAST PCS and TSC are generically presented,and the poloidal power supply model and data acquisition model that have been implemented in this framework are described as well.In addition,the correctness of data interactions among the EAST PCS,Simulink and TSC is clearly confirmed during an interface test,and in a simulation test,the RZIP control scheme in the EAST PCS is numerically validated using this simulation platform.
Accurate detection of a magnetic island in real time is one of the important issues for the tearing mode(TM) and neoclassical tearing mode(NTM) control.This paper presents a real-time detection system for the magnetic island of NTM control in the EAST Plasma Control System(PCS).Diagnosis is based on magnetic periodic perturbation and electron temperature fluctuation caused by the magnetic island.Therefore,a Mirnov measurement has been selected to calculate the island's parameters,such as island width,frequency of island rotation,and toroidal number.The electron cyclotron emission(ECE) system can detect the island position,which is calculated by two fast detection algorithms called correlation analysis and Hilbert transform.For future NTM control,real-time equilibrium reconstruction(rt-EFIT) is needed to locate the rational q-surface where the island is detected.This fast detection system is able to detect an island within 3 ms.It can be integrated into PCS to provide effective parameters of the island for NTM control by using EC resonance heating(ECRH) in the next experiment of EAST.
RMP(Resonant Magnetic Perturbation,共振磁场扰动)是托卡马克中用于磁流体力学不稳定性主动控制的基本手段之一,被广泛的应用于国际上各大主流装置。为了在EAST(Experimental Advanced Superconducting Tokamak)装置上开展相关的物理实验,在真空室内部设计制造安装了一套多功能的磁扰动线圈,在EAST PCS(Plasma Control System)上利用PID控制方法开发了RMP线圈电流控制算法,算法实现了对RMP线圈电流的开环与闭环控制。利用EAST PCS集成的simserver工具对算法进行了模拟运行测试,验证了算法的正确性。RMP线圈电流控制算法在2014年的EAST实验中得到了使用,实现了对RMP线圈电流的有效控制,为进一步的等离子物理研究奠定了基础。
KTX(Keda Torus for eXperiment)is a new reversed field pinch device.The KTX plasma control system(PCS)can provide real-time,stable,flexible plasma control which is designed by ASIPP(Institute of Plasma Physics,Chinese Academy of Sciences),based on the Linux cluster system and EPICS(Experimental Physics and Industrial Control System)framework,and developed from DIII-D(Doublet III-D)PCS.The control of the equilibrium field in KTX uses a PID(Proportional-Integral-Derivative)feedback controller.The control of the gas injection is an open loop control.The plasma control simulation system is one part of the plasma control system,which is used to test the plasma control algorithm if it is revised and updated.The KTX PCS has been successfully tested using HT-7(Hefei Torus 7)experiment data in simulation mode.In the next phase,an error field feedback control and KTX simulator will be added to the KTX PCS,and the KTX PCS will be applied in experiments in the future.
