HL-2A装置等离子体水平位移控制

介绍了HL-2A装置等离子体水平位移反馈控制系统的硬件组成、控制流程和控制算法,反馈控制的调试过程。在相同参数放电条件下比较了等离子体位移的受控情况。等离子体位移的控制结果较为满意。     

Control of LHCD on the HL-2A Tokamak

in order to study non-indutive plasma current production, the lower hybrid current drive（LHCD） experiment on the HL-2A tokamak is carried out. Simultaneously a microcomputer has been used to control the whole LHCD system. During the experiment this year, we can monitor and protect the LHCD system by use of the microcomputer control system, which will imediately switch off the microwave power to be launched into the tokamak if the plasma is disrupted. All this ensure that the microwave is injected into the equipment correctly.     

Vacuum System for HL-2A Tokamak

The vacuum system of today＇s tokamak devices is designed to meet the operational requirements of the experiments. The operation can be divided into five modes, （1） pumping down and leak detecting of the vacuum vessel, （2） baking, （3） plasma-facing component （PFC） conditioning, （4）evacuating and controlling of the particles at plasma edge, （5） plasma discharge experiments.     

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设计了HL-2A装置主机真空室烘烤温度反馈控制系统,用实验法获得系统近似数学模型,建立了HL-2A装置烘烤系统阶跃响应模型。运用控制理论对系统性能指标进行了设计分析,利用Simulink软件对控制系统进行了稳定性分析,通过西门子PLC300系统对此控制系统进行了软硬件实现。     

Observations of Edge Plasma on HL-2A Tokamak

The edge plasma characteristics are studied by a movable array of Mach/Reynolds stress/Langmuir 10-probes and fast reciprocating 4-probes in the boundary region. These probes can measure edge plasma temperature, density, poloidal electric field, radial electric field, Reynolds stress, poloidal rotation velocities and their profiles obtained by changing the radial positions of the probe array in different discharges. Measurement resuits are used to analyze plasma confinement, turbulent fluctuations and their correlation. The fixed flush 3-probe arrays are mounted on the 4-divertor neutralization plates at the same toroidal cross-section in divertor chamber. These probes are used to measure the profiles of the electron temperature, density and float potential in divertor chamber.     

HL-2A Tokamak Experiment Data System

HL-2A tokamak experiment data system （ HL-2A EDS ） consists of an experiment network, various of dada acquiring sub-systems, a great deal of realtime data processing applications, a display system, a lot of interacting data analyzing workstations, a data storage system, a management platform, and a high performance computer. The system was built start in 2002, and has been modified greatly since then.     

The ECRH Transmission System for HL-2A Tokamak

Electron cyclotron resonance heating and electron cyclotron current drive （ ECRH/ECCD ） have been developed significantly in recent years in many devices such as Tore Supra, JT-60U, Heliotron J. It has many advantages over other means of heating and current drive. The EC power can be injected as narrow gaussian beams, giving rise to so highly localized power deposition as to make ECRH an ideal candidate for local MHD control.     

Study of Plasma MHD Equilibrium in HL-2A Tokamak

1 Introduction In an axisymmetric toroidal system, the MHD equilibrium G-S equation can be written as：     

Study of Plasma MHD Equilibrium in HL-2A Tokamak

In an axisymmetric toroidal system, the MHD equilibrium Grad-Shafranov equation can be written as     

Overview of the Power Supply System on the HL-2A Tokamak

This paper shows the R＆D results of the power supply system in 2006, including the application of speed control assemblies of two 80 MVA MG sets, the modification of the exciting field system, the development of the new HV modulators in ECRH system, the update of several poloidal power supplies. It also presents the status of the power suppIy system in HL-2A experimental operation and foresees the power and energy requirements for new power supply system at HL-2M device.     

Theoretical Study of ECRH Heating Of HL-2A Tokamak Plasma

Electron cyclotron resonance heating （ECRH） is one of the main auxiliary heating schemes for the HL-2A tokamak. Routinely, the ohmic heating can provide a heating power about 300-450 kW in this device （ estimated from that the total toroidal current is about 300 kA while the totoidal voltage is 1-1.5 V）. The total power for the ECRH now is 1 MW and in future 2 MW.     

辅助加热下HL-2A边界层等离子体数值模拟

以二维边界等离子体流体模拟代码B2.5为核心,编制适合于具有封闭偏滤器位形特征托卡马克的边界层网格划分代码和计算后处理代码.模拟分析HL-2A托卡马克有约3MW辅助加热功率时的边界等离子体特性.结果表明,偏滤器靶板前形成了致密低温等离子体,偏滤器运行于高再循环状态.     

A Nonlinear Feedback Control System for Plasma Confinement

An analytical study of feedback stabilization of a continuum is done in the context of plasma confinement in a TOKAMAK device. Linear and nonlinear "bang-bang" feedback from discrete stations is investigated to find acceptable sensor and enforcer element geometries, compare their effectiveness, and predict the important parameters in their realization. The primary method used is an extension of the energy method.     

Progress in the Secondary Heating System for the HL-2A Tokamak

In 2006, the following work on secondary heating systems for HL-2A tokamak have been done： the development of an electron cyclotron resonance heating （ECRH） system, the improvement of lower hybrid resonance heating （LHCD） system and the fabrication on neutral beam injection （NBI） system.     

The Plasma Boundary in Low-Parameter Divertor Discharges on the HL-2A Tokamak

Because the last closed flux-surface （LCFS） finally determines the shape of plasma cross-section, and the shaping of plasma is a key issue directly related with lots of the hot subjects of an advanced tokamak（AT） and of a reactor, e. g., the control on the current density, equilibrium, scrapeoff layer（SOL）, aspects of edge particle and energy, high plasma kinetic energy, and of course, the MHD instability suppression, the further studies on the LCFS related subjects, e. g., its determination, flux loss, etc., are still tokamak research. It equilibrium, poloidal needed for present is also important to get precise LCFS-related equilibrium or configuration properties for the controls on an AT and for the understandings on the underlying basic physical issues in a discharge.     

Siliconization for Wall Conditioning and Its Effect on Plasma Performance in HL-2A Tokamak

1 Experiments HL-2A tokamak is characterized by a large closed divertor chamber. Before the experimental campaign 2005 the surface of the shielding plates for the MP1 and MP2 has been covered with 2-D carbon fibre composite （about 30% of the first wall）, which can protect the first wall, and effectively shield the splash of heavy metal impurity. The vacuum vessel can be baked up to 120 ℃for degassing and a glow discharge device is installed in the vessel for cleaning the inner surface. Hydrogen glow discharge cleaning （GDC） is applied to remove impurities from the wall, and helium glow discharge cleaning for removing residual hydrogen.     

HL-2A的中央逻辑控制PLC环网设计

PLC逻辑控制是HL-2A中央控制系统的重要组成部分,改造前的逻辑控制系统基本使用硬连接,维护耗时耗力。结合新一代实时工业以太网PROFINET为HL-2A逻辑控制系统的改造设计了环形冗余网络。采用8台西门子交换机SCALANCE X200通过光纤依次连接成环,交换机的电口连接S7-400和上位机,与等离子体放电相关的重要信号仍走硬连接,其他所有信号都走网络传送。中控系统作为管理站对其他7个子系统进行集中化管理,中控可以轻松快速地获取每个子系统的状态,在等离子体放电错误时能很快的预测事故地点和故障分析。根据放电实验结果表明,光纤环网非常适用于设备分散的慢控制系统,整个控制系统逻辑关系清楚,后期扩展和改造也非常方便。改造后的逻辑控制系统能满足HL-2A和HL-2M两套装置的慢控制,维护简便,事故定位快准,提高了放电效率。     

HL-2A Tokamak Gas Puff Imaging

Gas puff imaging （GPI） is one of the important diagnostics for the （ITPAC international tokamak physics activity ） and entering the ITPA IDD （ international diagnostics database ） . GPI is related to many investigations, for example, edge radiations, etc.