The Introduction to the ECRH System of the HL-2A Tokamak

The 1 MW/68 GHz/1 s ECRH system of HL-2A device is being designed or fabricated. The O mode wave beams are injected into plasma from low field side of the HL-2A tokomak. Because the EC wave can heat plasma locally, it is a very versatile scheme which has been employed to heating, current drive, profile control, confinement improvement. Up to now, the basic physical and engineering parameters of the whole system have been fixed and the subsystems are being designed or fabricated.     

Measurement of the Distribution of Magnetic Field in Gyrotron of ECRH System on HL-2A Tokamak

In ECRH system of HL-2A tokamak, we chose a new type of gyrotron imported from Russia. We finished the installation and testing last year with the help of Russian experts. We got a lot of useful data and satisfying results after our experiments with the operating of gyrotron.     

The Analysis and Calculation on ECRH Anode Circuit on the HL-2A Tokamak

In the last year, ECRH system has been built in the HL-2A and the testing of gyrotron is also finished. In the project testing, one of the problems is current-peak occurring in the anode circuit of gyrotron. The current-peak is much larger than that of the value set in protection circuit. The frequent current-peak frequently occurring in the rising of anode-voltage often caused the protection circuit to mistaken trigger. The mistaken triggering often halted the normal gyrotron-testing. A set of equations of anode circuit are derived for analysis the phenomena of the current-peak. The calculation based on the deduced formula shows that value of the current-peak strongly depends on the inductance L, capacitance C and the ramp-time of anode voltage in the anode circuit. The conductance L and capacitance C are the characteristic inductance and capacitance of the cable that is used for anode HV power supply. The numerical calculation is exactly consistent with waveform of the current peak recorded by oscillograph, that means the derived formula are correct. In order to decrease the value of the current-peak, we should decrease capacitance C, and increase inductance L and ramp-time of anode voltage.     

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HL-2A装置电子回旋共振加热系统的主要指标是2MW/1s/68GHz,系统由4个单元组成,每个单元包括一只回旋管,微波传输系统,控制保护测量和冷却等子系统。通过对ECRH系统和回旋管的调试,每只管子微波输出功率500kW,脉冲宽度1s,四管并联运行时总输出功率达到1.63MW,系统使用效率高于80%。     

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.     

HL-2M 装置电子回旋共振加热及电流驱动系统设计与研制进展

根据 HL-2M 装置物理实验加热的需求,完成了总功率为 8MW 的电子回旋共振加热及电流驱动 (ECRH/ECCD)系统设计,开展了波源、传输及天线等关键部件研制。8MW ECRH/ECCD 系统,由 8 套 105GHz/  1MW/3s 波源系统、8 条内径为 63.5mm 的真空传输线及三套极向实时可控的发射天线构成。目前,已完成 ECRH/ECCD 系统关键部件研制及其相关的桌面与高功率性能测试。测试结果表明,微波源回旋管输出微波功率 达到1MW/3s,在真空度为 10^‒2Pa 的过模波纹圆波导传输线中能低耗稳定传输,发射天线极向全量程角度转动响 应时间在 50ms 以内。      

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.     

The Real-Time Arc Protection Circuit for ECRH on HL-2A Tokamak

In 2005 year, SWIP carded through a general engineering and physics experiment of ECRH on HL-2A tokamak. The ECRH protection system is studied and set up to insure the security of ECRH system, and the work is normal. The main protection object of all ECRH system is the gyrotron, and the arc protection for it is more important in the protection system.     

HL-2A装置3MW 68GHz ECRH系统调试与运行

HL-2A装置3MW ECRH系统采用双高压电源形式的电子回旋管,阴极高压电源为回旋管提供加速束电流,阳极高压电源对通过转换区后的束电流施加减速作用,利于回旋管收集极吸收。根据回旋管运行特点和各回旋管不同的工作特性,合理优化回旋管阴极、阳极高压电源工作电压和其他参数。通过远程监控系统,使同时工作的回旋管处于较好的工作状态,充分提高HL-2A装置ECRH系统多管运行的微波输出功率。实验中,6支回旋管同时运行时,微波最高输出功率2.5MW,达到设计额定值83%,使HL-2A装置中等离子体得到了有效的加热。     

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HL-2A装置3MW ECRH系统采用双高压电源形式的电子回旋管,阴极高压电源为回旋管提供加速束电流,阳极高压电源对通过转换区后的束电流施加减速作用,利于回旋管收集极吸收。根据回旋管运行特点和各回旋管不同的工作特性,合理优化回旋管阴极、阳极高压电源工作电压和其他参数。通过远程监控系统,使同时工作的回旋管处于较好的工作状态,充分提高 HL-2A 装置 ECRH 系统多管运行的微波输出功率。实验中,6支回旋管同时运行时,微波最高输出功率2.5MW,达到设计额定值83%,使HL-2A装置中等离子体得到了有效的加热。     

Primary Results of ECRH Experiment and Electron Heat Transport on the HL-2A Tokamak

As an ordinary mainly auxiliary heating on tokamak plasma, electron cyclotron resonance heating （ ECRH ） is an useful method to the study of electron heat transport and confinement performance. In this work, primary results of ECRH experiments on the HL-2A tokamak are presented. The features of confinement and electron heat transport during ECRH are analyzed.     

HL-2A装置电子回旋打火保护系统设计

电子回旋打火保护系统由打火弧光探测器、A/D转换单元和逻辑处理单元组成。弧光探测器响应时间小于2μs,A/D转换单元和逻辑处理单元响应时间小于1μs。打火保护系统输出保护信号关断各供电电源的响应时间小于20μs。     

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应用准光学原理设计了HL-2A装置电子回旋共振加热(ECRH)系统新的集束天线,该天线能使4束68GHz/500kW/1s电子回旋波通过椭球镜聚焦和平面镜的反射,从一个直径350mm装置窗口同时注入托卡马克,对等离子体实现加热。根据基模高斯束的传播原理得出,在装置环向横截面中心处单条波束的功率密度为158MW•m-2,功率密度降为中心密度的1/e2的半径为31.7mm,微波束经过镜面聚焦和反射产生的欧姆损失和衍射损失分别为0.27%和0.64%。利用有限元分析软件Ansys对镜面进行热分析得到,在1s脉冲载荷下最大镜面温升仅为0.47℃,镜面可以自然冷却。     

HL-2A装置ECRH系统的新天线设计

Using the principle of quasi-optic, the new antenna of the electron cyclotron resonant heating(ECRH) system on the tokamak HL-2A has been designed. After being focused by the elliptical mirror and reflected by the plane mirror, 4 68GHz/500kW/1s electron cyclotron wave beams would be injected into the tokamak from one Æ350mm port to accomplish heating to the plasma. Based on the propagating theory of the fundamental Gaussian beam, it is gotten that at the centre of the cross section of the tokamak, the power density of each beam is 158MW•m^-2, and the power density radius, which means that the power density is reduced by a factor 1/e² compared to the power density at the centre of the beam, is 31.7mm. On the mirror, due to the focusing and reflecting, the ohmic loss and diffraction loss of the microwave beams are 0.27% and 0.64%, respectively. By the finite element analysis software ANSYS, some thermal analysis of the mirror have been done. The result shows that the highest temperature increase would be only 0.47℃ under 1s pulse load, so there is no need of any cooling.     

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.     

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.     

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.     

HL-2A装置ECRH系统传输效率的测量研究

介绍了HL-2A装置ECRH系统传输效率的测量方法。通过对MOU、回旋管输出窗口及真空密封窗口吸收功率的测量,得到HL-2A电子回旋系统的传输效率为90％左右。提出了除由MOU处测量微波功率外,可以由传输线的其他部位确定功率的方法。     

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.