Observation and analysis of halo current in EAST

Plasma in a typically elongated cross-section tokamak （for example, EAST） is inherently unstable against vertical displacement. When plasma loses the vertical position control, it moves downward or upward, leading to disruption, and a large halo current is generated helically in EAST typically in the scrape-off layer. When flowing into the vacuum vessel through in-vessel components, the halo current will give rise to a large J × B force acting on the vessel and the in-vessel components. In EAST VDE experiment, part of the eddy current is measured in halo sensors, due to the large loop voltage. Primary experimental data demonstrate that the halo current first lands on the outer plate and then flows clockwise, and the analysis of the information indicates that the maximum halo current estimated in EAST is about 0.4 times the plasma current and the maximum value of TPF × Ih/Ip0 is 0.65, furthermore Ih/Ipo and TPF × Ih/Ipo tend to increase with the increase of Ip0. The test of the strong gas injection system shows good success in increasing the radiated power, which may be effective in reducing the halo current.     

基于紧致差分的Grad-Shafranov方程快速解法

在等离子体平衡重建迭代计算过程中,需要快速求解Grad-Shafranov方程(G-S方程)。构造了具有四阶精度紧致差分格式的离散方程,采用离散正弦变换技术对其进行快速求解并采用CUDATM实现GPU并行加速,将其应用到EAST等离子体平衡重建PEFIT代码中,实现基于紧致差分格式的快速G-S方程求解。结果表明,在65?65的网格下,给定方程右端项电流分布的前提下,使用GPU求解G-S方程所需时间为大约34?s。     

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为提高等离子体实时平衡反演过程的精度和效率,开发了基于图形处理器(GPU)的P-EFIT程序.简要概括EAST PCS软硬件架构后,描述了并行实时平衡反演程序P-EFIT在EAST PCS中的集成工作.为了验证集成系统的正确性与可用性,用历史实验数据作了性能测试,满足实时控制的要求.目前P-EFIT已集成在EAST中并用于等离子体控制,EAST实验证明控制性能良好.     

Effect of passive plates on vertical instability in the EAST tokamak

The effect of passive plates on vertical displacement control in the EAST tokamak is investigated by open loop experiments and numerical simulations based on a rigid displacement model.The experiments and simulations indicate that the vertical instability growth rate is reduced by a factor of about 2 in the presence of the passive plates,where the adjacent segments are not connected to each other.The simulations also show that the vertical instability growth rate is reduced by a factor of about 10 if all adjacent segments on each passive plate loop are connected to each other.The operational window is greatly enlarged with the passive plates.     

Effect of passive structure and toroidal rotation on resistive wall mode stability in the EAST tokamak

If βN exceeds no-wallβN, the plasma will be unstable because of external kink and resistive wall mode(RWM). In this article, the effect of the passive structure and the toroidal rotation on the RWM stability in the experimental advanced superconducting tokamak(EAST) are simulated with CHEASE and MARS codes. A model using a one-dimensional(1D)surface to present the effect of the passive plate is proved to be credible. The no wall βN limit is about 3li, and the ideal wall βN limit is about 4.5li on EAST. It is found that the rotation near the q = 2 surface and the plasma edge affects the RWM more.     

A divertor plasma configuration design method for tokamaks

The efficient and safe operation of large fusion devices strongly relies on the plasma configuration inside the vacuum chamber.It is important to construct the proper plasma equilibrium with a desired plasma configuration.In order to construct the target configuration,a shape constraint module has been developed in the tokamak simulation code(TSC),which controls the poloidal flux and the magnetic field at several defined control points.It is used to construct the double null,lower single null,and quasi-snowflake configurations for the required target shape and calculate the required PF coils current.The flexibility and practicability of this method have been verified by the simulated results.     

基于光弹调制的运动斯塔克效应诊断

电流密度分布是等离子体物理研究的关键分布参数,在托卡马克先进运行模式发展,电流驱动,约束与输运等方面发挥着重要的作用。中性束与等离子体相互作用产生的分裂光谱,包括σ分量与π分量,水平观测时,σ分量的偏振方向垂直于等效电场的方向,π分量的偏振方向平行于等效电场的方向,通过测量分裂光谱的偏振方向可以反演出等离子体电流密度分布。基于光弹调制器的偏振检测系统具有检测精度高、时间响应迅速的独特优点,非常适用于等离子体电流快速变化下的电流密度分布测量。光弹调制器的双折射晶体在周期性外部驱动源的作用下发生弹性形变,其折射率会产生周期性的变化,当偏振光通过时,出射光的偏振特性将相应产生周期性变化,再经过偏振片,形成调制的光强变化。运动斯塔克效应(MSE)诊断的偏振检测系统由两个光弹调制器(PEM)和一个偏振片组成,通过检测不同调制频率的调制强度的比值,从而快速、精确地获得分裂光谱的偏振方向的实时变化,进而得到等离子体电流密度分布。详细介绍了东方超环托卡马克(EAST)装置上的MSE诊断,初步完成了离线测试与标定,参与中性束电流本文驱动物理实验,初步获得了等离子体电流密度分布的信息。     

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利用11/2-D平衡演化程序对EAST的首轮纯欧姆放电进行了数值模拟，获得的模拟结果与实验结果吻合得很好。同时，对放电全过程中的伏秒消耗进行了分析。     

Analysis of Dα（Hα） spectrum emitted in front of the limiter in HT-7^＊

In order to understand the recycling and emission processes of hydrogen atoms in HT 7, spectral profiles of the Dα（Hα） line emitted in front of the limiter have been observed with a high-resolution spectrometer and simulated by using the neutral particle transport code DEGAS 2. The results show that four processes are necessary to interpret the Dα（Hα） line shape： 1） atom desorption, 2） molecular dissociation, 3） particle reflection, and 4） charge-exchange. The products of the first two processes are cold atoms which emit photons near the peak of Dα（Hα） line shape, and those from the last two are warm atoms contributing to the blue side of the spectrum. For a typical ohmic discharge （shot 68520 ne（0） ≈ 3× 10^19 m^-3. these components contribute 32%, 15%, 32% and 21%, respectively. Dα（Hα） line shapes under different plasma parameters are also discussed in this paper.     

Comparison benchmark between tokamak simulation code and TokSys for Chinese Fusion Engineering Test Reactor vertical displacement control design

Vertical displacement event(VDE) is a big challenge to the existing tokamak equipment and that being designed. As a Chinese next-step tokamak, the Chinese Fusion Engineering Test Reactor(CFETR) has to pay attention to the VDE study with full-fledged numerical codes during its conceptual design. The tokamak simulation code(TSC) is a free boundary time-dependent axisymmetric tokamak simulation code developed in PPPL, which advances the MHD equations describing the evolution of the plasma in a rectangular domain. The electromagnetic interactions between the surrounding conductor circuits and the plasma are solved self-consistently. The TokSys code is a generic modeling and simulation environment developed in GA. Its RZIP model treats the plasma as a fixed spatial distribution of currents which couple with the surrounding conductors through circuit equations. Both codes have been individually used for the VDE study on many tokamak devices, such as JT-60U, EAST, NSTX, DIII-D, and ITER. Considering the model differences, benchmark work is needed to answer whether they reproduce each other's results correctly. In this paper, the TSC and TokSys codes are used for analyzing the CFETR vertical instability passive and active controls design simultaneously. It is shown that with the same inputs, the results from these two codes conform with each other.