HL-2A装置电子回旋传输系统

近年来，电子回旋共振加热和驱动在许多装置上得到应用，例如：Tore Supra。JT-60U和Heliotron J，与其它加热和驱动方法相比，它具有以下优点。电子回旋波能以能量集中的高斯模式注入，产生高度集中的功率沉积，能进行理想的MHD不稳定性控制。     

HL-1M装置中的离轴电子回旋加热实验

在HL-1M装置上进行了离轴电子回旋加热实验。研究了电子温度的变化，等离子体密度对加热效果的影响，离轴加热条件下MHD锯齿的变化，波对m/nk=1/1模的影响及在与低杂波电流驱动共同作用下的各种实验现象。 这些现象被认为与高能电子和它们的分布有关。     

加热功率沉积剖面与氘氚自持燃烧条件的建立

研究了不同的加热功率沉积剖面对托卡马克反应在堆点火启动过程的影响，结果表明，在基本相同的总加热功率下，偏轴加热与近轴加热的效果没有太大的差别，因而较低能量的中性中加热有可能在反应堆中的得到应用。     

EAST 电子回旋共振加热效果的数值模拟和分析

为了给EAST 电子回旋共振加热物理实验提供理论依据和模拟预测,从电子热输运方程出发,运用 CRONOS 输运程序对不同等离子体和波参数下,电子回旋加热效果进行了数值模拟计算。给出不同电子回旋波功率、入射角、电子密度和纵场等参数对电子回旋加热效果的影响,预测在不同参数下,电子温度、等离子体总内能和能量约束时间的变化,分析了其原因,并与实验结果进行了初步的比较。     

电子回旋共振加热情形锯齿振荡的数值分析

采用磁重联模型与湍流模型,通过求解耦合了锯齿触发条件的一维输运方程,模拟了电子回旋共振加热(ECRH)情形下T-10托卡马克中锯齿振荡.其中之一是近轴的ECRH,另一个是远轴的ECRH,数值结果与实验的比较表明用湍流模型得到了较好的预测结果,相反,由于重联模型的一些基本缺陷,不可能由重联模型得到满意的结果. 关键词： 锯齿振荡 磁重联模型 湍流模型 电子回旋共振加热     

HL-2Aװ�õ��ӻ���������Ȳ����͹��ʳ�������ķ�������

在HL-2A单零偏滤器条件下,对由弱场侧沿赤道平面垂直注入的电子回旋寻常波(O-模)的波迹和波的功率沉积剖面进行了分析计算。对近磁轴共振情形,需要确定一个有效的物理尺度以正确获得波功率沉积。单一波束的有效吸收层的厚度可以合理地作为这一物理尺度,从而获得统一的功率沉积公式。对比研究了磁轴偏离赤道面和位于赤道面情况下的波功率沉积剖面。     

磁镜等离子体中电子回旋波加热实验的理论研究

本文利用平行平板模型,给出了在不同位置、以不同角度入射到平衡的磁镜等离子体中电子回旋波的传播轨迹;利用线性理论计算了O,X波能量分别被本底电子、热电子吸收的波能量沉积率。根据计算结果,文中对加热本底等离子体的特征进行了描述,对非封闭热电子环的形成作了初步解释。     

撕裂模实时主动控制系统

在HL-2A装置上发展了一套撕裂模实时主动控制系统。该系统在放电期间用电子回旋发射/软X射线诊断实时确定撕裂模的几何位置,结合实时剖面重建和电子回旋波沉积计算,得到电子回旋波反射镜的控制角度值。通过电机实时驱动电子回旋波反射镜到达指定角度,使得电子回旋波功率沉积在撕裂模的有理磁面附近,改变当地局部的电流剖面,从而控制撕裂模,改善等离子体约束。该系统已经在2015年以后的实验中投入使用,并取得了良好的控制效果。它不仅能够实时发现并控制经典撕裂模,并且具有控制新经典撕裂模的潜力。     

HL-2A装置等离子体电子回旋加热的理论研究

电子回旋加热是HL-2A装置主要二级加热手段之一。在通常运行条件下，HL-2A装置欧姆加热功率估计为300-450kW范围（按总环向电流300kA，环压1-1．5V估算）。而电子回旋加热的总功率已达1MW，有望增加到2MW。     

离子回旋共振加热的电子加热

理论分析和实验结果都证明在离子回旋共振加热情况下,电子能直接从波吸收能量,其能量吸收机制是郎道阻尼和飞行时间磁泵阻尼。本文从线性化波的一般理论,导出了电子吸收功率和吸收特征长度的解析表示式,与其他结果进行了比较并做了简短的讨论。     

电子回旋波驱动的托卡马克芯部等离子体极向旋转

提出了一个驱动托卡马克芯部等离子体极向旋转的新途径：用电子回旋波产生芯部等离子体极向旋转.物理机制如下：在高功率的电子回旋波加热的托卡马克等离子体中，共振局域化现象将产生极向电场从而形成极向外高内低的离子密度分布；这个极向离子的积累可以克服来自磁泵的阻尼而使等离子体极向旋转退稳定.从流体力学方程和漂移动力学方程中，得到了等离子体旋转退稳的判别式.结果表明现有的电子回旋波加热功率水平可以驱动芯部等离子体的极向旋转. 关键词：     

Reconstruction of heat flux profile on the HL-2A divertor plate with a three-dimensional analysis model

A three-dimensional analysis model based on the finite element method (FEM) is developed, which can derive the evolution and distribution characteristics of heat flux deposited on the divertor plate from the surface temperature measured by infrared thermography diagnostics. The numerical simulations of surface heating due to localized power bursts and the power deposition calculations demonstrate that this analysis can provide accurate results and useful information about localized hot spots compared with the normal one- and two-dimensional calculations. In this paper, the details of this three-dimensional analysis are presented, and some results in ohmic heating and electron cyclotron resonant heating (ECRH) discharge on HL-2A are given.     

HL-2Aװ��SDD��X����PHA����ʵ����

用软X射线脉冲高度分析(PHA)阵列系统获得了等离子体的电子温度剖面和电子速率分布的时间演化。测量结果表明,电子温度剖面在OH阶段较平缓,接近抛物线1.0×[1-(r/a)2]2分布;而在ECRH(功率0.8MW)阶段,等离子体中心(z＝0)电子温度上升了0.6keV,边缘(z＝30cm)处只上升了0.1keV,反映出ECRH功率沉积在等离子体中心区域;在ECRH期间有大量的高能电子产生,因而电子速率分布在ECRH期间显著改变;等离子体中心的高能电子的数量和能量都比等离子体边缘的增加更大,ECRH(～0.8MW)期间等离子体中心(z＝0)产生的高能电子的能量可达17keV。分析表明：在ECRH(纵场Bt=1.3T)放电期间,ECRH加热效果显著,ECRH的功率主要沉积在等离子体中心附近;电子温度剖面在ECRH阶段较OH阶段峰化;ECRH期间有大量的高能电子产生,电子速率分布被改变成为非麦克斯韦分布。     

HL-2Aװ�õ�Լ�����ƺͱ߽羻���빦�ʷ���

在HL-2A装置孔栏位形放电的等离子体实验中,电子回旋辅助加热期间观察到了等离子体约束改善的现象,并对等离子体从低约束模式(L模)向约束改善模式转换时的等离子体线平均电子密度、等离子体储能、分界面内辐射功率、能量约束时间、Hα辐射等进行了研究。同时,分析了电子密度和等离子体辐射功率的空间分布随时间的演化。对改善约束的相关功率(辅助加热、欧姆加热功率和损失功率)进行了分析,并研究了等离子体约束改善转换时的边界净输入功率(阈值)与电子线平均密度和环向磁场的关系。     

Low-threshold parametric decay instabilities in the experiments on the electron cyclotron resonance heating in tokamaks and stellarators

The experimental conditions have been analyzed for a significant reduction of the threshold of the reflective parametric decay instabilities under electron cyclotron resonance heating (ECRH) of a plasma in magnetic devices in the absence of the upper hybrid resonance for the pump wave. The role of the nonmonotonic profile of the plasma density near the O point of the magnetic island, which allows for the localization of ion Bernstein waves in the direction of the density gradient and the suppression of convective losses from the decay region has been discussed. It has been shown that the threshold of the instability of the induced backscattering near the local maximum of the density profile is decreased by four orders of magnitude and is easily exceeded in present-day ECRH experiments at a power of several hundred kilowatts.     

Investigation of impurity transport using laser blow-off technique in the HL-2A Ohmic and ECRH plasmas

Impurity transports in two neighboring discharges with and without electron cyclotron resonance heating(ECRH)are studied in the HL-2A tokamak by laser blow-off(LBO) technique.The progression of aluminium ions as the trace impurity is monitored by soft x-ray(SXR) and bolometer detector arrays with good temporal and spatial resolutions.Obvious difference in the time trace of the signal between the Ohmic and ECRH L-mode discharges is observed.Based on the numerical simulation with one-dimensional(1D) impurity transport code STRAHL,the radial profiles of impurity diffusion coefficient D and convective velocity V are obtained for each shot.The result shows that the diffusion coefficient D significantly increases throughout the plasma minor radius for the ECRH case with respect to the Ohmic case,and that the convection velocity V changes from negative(inward) for the Ohmic case to partially positive(outward) for the ECRH case.The result on HL-2A confirms the pump out effect of ECRH on impurity profile as reported on various other devices.     

HL-2A装置的约束改善和边界净输入功率分析

在HL-2A装置孔栏位形放电的等离子体实验中,电子回旋辅助加热期间观察到了等离子体约束改善的现象,并对等离子体从低约束模式(L模)向约束改善模式转换时的等离子体线平均电子密度、等离子体储能、分界面内辐射功率、能量约束时间、H_α辐射等进行了研究。同时,分析了电子密度和等离子体辐射功率的空间分布随时间的演化。对改善约束的相关功率(辅助加热、欧姆加热功率和损失功率)进行了分析,并研究了等离子体约束改善转换时的边界净输入功率(阈值)与电子线平均密度和环向磁场的关系。     

Reduction of impurity confinement time by combined heating of LHW and ECRH in EAST

The core impurity confinement properties are experimentally investigated in the Experimental Advanced Superconducting Tokamak(EAST) plasma heated by lower hybrid wave(LHW) and electron cyclotron resonance heating(ECRH)(LHW+ECRH).It is shown that the impurity confinement time(τ_(imp)) in the L-mode plasma jointly heated by LHW and ECRH is weakly dependent on electron density but strongly dependent on the heating power,thus it is shorter than that in LHW-only heated L-mode plasma with the similar plasma parameters.The combined heating of LHW and ECRH can reduce the collisionality and indicates a more effective heating method for core τimp reduction and normalized poloidal beta(βP) ~(im)provement.It should be emphasized that in this high β_P operation window the small ELM regime can be accessed,and an L-mode level τ_(imp)(40 ms-80 ms) and high β_N(～1.7) can be obtained simultaneously.It means that this typical small ELMy H-mode regime has an advantage in avoiding the serious tungsten accumulation,and will be competitive in future long-pulse steady-state and high-performance operation with high-Z material plasma-facing components.     

EAST装置电子回旋共振加热系统中央控制器设计

介绍了基于可编程逻辑门阵列(FPGA)芯片的电子回旋共振加热(ECRH)系统中央控制器的设计,阐述了中央控制器对输入的总控触发信号、等离子体电流信号、ECRH系统状态信号、高压输出状态信号、波输出状态信号、各类停止信号以及各输出控制信号等的处理与控制逻辑.对FPGA程序做了时序仿真,仿真结果表明,该控制器能够实时响应总...     

Design and application of a new control system for tokamak ECRH power supply

The biggest challenge of designing and building tokamak electron cyclotron resonance heating (ECRH) pulse step modulation (PSM) power supply is satisfying its required output voltage rising time to be less than 100?µs while suppressing the voltage overshoot to be no more than 1%. To fulfill the two requirements, a new control strategy with startup time in microsecond range is proposed in this paper, and a new control system to realize the control strategy is introduced. The control system was built and tested on 60?kV/50?A ECRH power supply. The experimental results indicate that the control system can restrain the overshoot effectively, increase response speed, and obviously improve the dynamic characteristics of the PSM power supply system. Thus, the proposed control system helps the PSM power supply to meet the design specifications.