Three Dimensional Identification of Zonal Flows in the HL-2A Tokamak

1 Introduction Zonal flows （ZF） have been studied in some fusion devices. For example, geodesic acoustic mode （GAM） is observed with the frequency of fGAM - 15 kHz, poloidal mode number （m〈3） and radial wave number （ krρi -0.2） using beam emission spectroscopy at plasma edge in the D Ⅲ- D tokamak.     

Geodesic Acoustic Mode in Toroidally Axisymmetric Plasmas with Non-Circular Cross Sections

The geodesic acoustic mode （GAM）, first predicted by Winsor, Johnson and Dawson in an attempt to explain some experimentally observed low frequency oscillations in stellarators, is a special electrostatic fluid mode with low mode number and coupled with the so-called geodesic curvature of a toroidally confined plasma. The recent on this mode are due to the close relevance of the stabi- lization of drift turbulence by both the zonal flow and the GAM. Previously, the GAM was illustrated in very simple geometries,     

Numerical Investigation of Finite k Effect on Damping Rate of Geodesic Acoustic Mode in Collisionless Plasmas

Numerical method is applied to the investigation of the GAM damping rate with the finite k effects included. It is found that generally the damping rate given by the analytical method is smaller than that given by the numerical method, and the analytical damping rate has good approximation in the high q region （q 〉 4）. The difference between the analytical and numerical damping rates increases with the increasing kpi. However, for the short-wavelength case （kpi = 0.2）, the analytical methods are only good enough around q = 4 because of the slow convergence of Bessel function with the large variable.     

Design and Studies of Disruption Prediction System on the HL-2A Tokamak

In the contemporary large tokamak, the disruptive termination of a discharge will reduce the lifetime of the first wall materials because of the intense heat flux at the energy quench and the intense runaway electrons during the current quench, and generate high electromagnetic forces on vacuum vessel components. The system of disruption warner must be established in the HL-2A tokamak. MHD real-time measuring and processing system has been designed and implemented. The system can be predicted the auras of dischage disruption in real-time, the energy quench and the current quench can be avoidanced.     

Pellet Injection Experiments in the HL-2A Tokamak

The advantages of pellet injection as a competitive means of fuelling a tokamak are well known. They include： （ 1 ） deep deposition of fuel, （ 2 ） better fuelling efficiency, （ 3 ） purer plasma, and so on. Meanwhile, improving plasma performance by pellet injection has been proven in many tokamak experiments. The deposition of pellet particles following pellet injection causes a temporal change of the local plasma temperature and density gradients which affects the transport properties of the plasma, so pellet injection can be used as a method of studying the transport process as well.     

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.     

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.     

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.     

Microwave Reflectometry on HL-2A Tokamak

One of the most important electron density diagnostics, microwave reflectometry, has been developed on many large and medium nuclear fusion devices in recent years . Not only the electron density profiles with high temporal and spatial resolutions, but also the profiles of plasma rotation and turbulence can be obtained with this diagnostic system.     

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.     

Pellet Enhanced Performance on the HL-2A Tokamak

Enhanced confinement has been achieved by the centre fuelling of pellet injection on the HL-2A tokamak. The energy confinement time increases from 50ms to 140ms after the pellet injection. Experimental results show that the improvement of the confinement is related to the decrease of the electron heat transport. Several phenomena which may lead to the improved confinement have been observed in the experiments. After the pellet injection the hollow electron temperature profile and the peaked electron density profile can be sustained for about 200ms, but the improved confinement remains at about 500ms. Sawtooth features and MHD modes have been observed by soft x-ray array and the Mirnov probes. The weak （or reversed） magnetic shear is thought to be an important cause of the low electron heat transport.     

Siliconization for Wall Conditioning in the HL-2A Tokamak

The sputtering of impurities is caused by the interactions between plasma and the first wall, and the recycling of the gas affects the particle and energy transport of plasmas with a complicated mechanism in plasma operation. It is important for present tokarnaks to achieve a good confinement and high performance plasmas by means of controls of the vacuum condition, usage of low Z materials, control of the recycling of neutral particles and suppressions of the appearances and yield of impurities. For higher plasma parameters, some of the first wall of HL-2A is covered with graphite materials and carbon fiber tiles. Hence the studies on the in-situ coating application and development, and the interactions between the coating film and plasma are needed to effectively control the impurity, improve plasma confinement and achieve high performance plasma.     

Fast Bolometer Arrays on the HL-2A Tokamak

Bolometers are considered to be a standard diagnostic for fusion experiments, mainly for measuring the total radiated power and spatial profiles of the local radiation power density. New design and the first result are presented from three AXUV arrays with high temporal resolution installed on the HL-2A tokamak. This high temporal resolution allows the study of transient radiative phenomena.     

Laser Blow-Off Injected Impurity in HL-2A Tokamak

Transient perturbation methods are most appropriate to study particle transport in tokamaks. Two most commonly used techniques of impurity injection are laser blow-off and gas puffing. Short bursts of impurities, injected using the laser blow-off injection technique, are among other transient perturbation methods, undoubtedly best suited to study impurity transport The injection time and the amount of injected material can be controlled in order to study a certain phase of the discharge with a minimum perturbation of the plasma parameters. Furthermore, the source is of very short duration and thus provides an experimentally more direct measure of impurity transport.     

New Diagnostic Systems on HL-2A Tokamak

1 Introduction HL-2A is a middle size （ R= 1.65 m, α=0.40 m） tokamak with a closed divertor. The main subjects are investigation of the divertor and edge plasma physics, plasma transport and its mechanism, plasma profile control with auxiliary heating and so on. A great number of diagnostics have been designed and equipped on the device. Among them three new diagnostics have been developed for particle transport, the zonal flow and density profile.     

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.     

Study of Plasma MHD Equilibrium in HL-2A Tokamak

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

Multi-Channel FIR Laser Interferometer on the HL-2A Tokamak

In recent years, the high density plasma in the range of 10^19～ 10^20m^-3 have been operated in large or middle tokamak device in the world. A muhichannel far infrared interferometer for profile measurement of plasma density on HL-2A divertor tokamak is being developed, however the design of the interferometer will appear many new problem in face of experimental environment of the HL-2A divertor device, such as how to make both transmission and arrangement of optics of the interferometer, the effect of electromo- tive force on device and how about the vibration etc. According to the eight windows setting on the largest flange of the device we have to design a Michelson-type FIR laser interferometer with 8 probing channels and eight concave mirrors must be attached it to the inner wall of the vacuum vessel of the device. Therefore, there are many problems should be taken into account to resolve, for example, （ 1 ） the vibration-proof consider for muhichannel interferometer and HCN laser, （2） the stabilization and reliability of the mirror frame uum vessel, the mirrors, hanging on internal wall of vachow to prevent the sputtering to （3） the vacuum seal of the windows and the design of mobile seal for the shutter to avoid the sputter coating of plasma,     

The Pellet Enhanced Performance on the HL-2A Tokamak

Improved confinement during the fuelling is one of the most important subjects for the tokamak research. Experiments have confirmed that anomalous transport is caused by turbulences driven by temperature and density gradient in plasma. Pellet injection is not only an important fuelling method, but also is an efficient tool for controlling the plasma pressure and current profile. The improved energy confinement has been observed in many tokamaks with center pellet injection since 1980＇s.