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.     

Beam Ion Transport from Neutron Emissivity Measurement in Deuterium Neutral Beam-Heated Deuterium Plasmas of the HL-2A Tokamak

An experiment at the HL-2A tokamak with a high-energy deuterium neutral beam （NB） injection （30 keV, about 0.6 MW） was performed. The emission of d-d fusion neutrons dominated by beam-plasmas reactions when the deuterium NB was injected into the deuterium target plasma was observed by means of a ^235U fission chamber. To obtain information on NB deposition and the slowing down of beam ions in HL-2A plasmas, a very short-pulse deuterium NB injection, or the so-called ＂blip＂ injection, was performed into MHD-quiescent Ohmic deuterium plasmas. Analysis of neutron decay following the NB ＂blip＂ injection indicates that tangentially injected beam ions are well confined, slowing down classically in the HL-2A. In contrast to the MHD-quiescent plasma, anomalous losses of beam ions were observed when tearing mode instabilities were present.     

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.     

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.     

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 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.     

Characteristic of Disruption on HL-2A Tokamak

The tokamak disruption is a dramatic event in which the plasma confinement is suddenly destroyed. Detailed experimental studies of disruptions have been made in many machines. During disruption, the plasma current and plasma thermal energy content collapse in an uncontrollable way, thereby applying mechanical forces and heat loads onto the vacuum vessel components. For that reason, the disruptions in a tokamak must be investigated and the physical processes leading to and occurring at the disruption need to be understood.     

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.     

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：     

HL-2A托卡马克实验进展和科学创新

中国环流器二号A(HL-2A)托卡马克是中国第一个带偏滤器的大型受控核聚变研究装置.文章综述了在HL-2A托卡马克装置上的重要实验结果.自从HL-2A装置建成以来,有以下3个重要进展:实现了等离子体偏滤器位形放电;等离子体电子温度达到5500万度;实现了具有边缘局域模的高约束(H模)放电.随着HL-2A装置辅助加热能力和先进等离子体诊断等系统的发展,该装置在聚变等离子体物理的若干领域做出了以下创新性的贡献:实验验证了对聚变等离子体输运有重要影响的带状流的三维结构;进一步发展了原创的分子束加料技术,并且成功地应用于等离子体输运研究;用低频调制的电子回旋共振加热(ECRH)对撕裂模进行了有效的抑制,并使约束得到改善;观测到高能电子激发的内部扭曲模和阿尔芬模等新的物理现象.文章还简要介绍了该装置的发展计划及近期要开展的物理实验研究内容.