EASTװ�ô�ֱ���ȶ����о�

对EAST装置偏滤器位形的放电中发生的垂直位移不稳定性的全过程进行了模拟,计算了磁轴垂直位移及垂直位移不稳定性的增长率。模拟的结果与实验结果符合得较好。     

HL-2M�������崹ֱ���ȶ����о�

用DⅢ-D的TokSys研究了HL-2M等离子体垂直不稳定性控制问题.使用真空室和主动线圈控制等离子体垂直不稳定性,分析了真空室的本征模和电流分布,极大简化真空室建模难度,建立了垂直不稳定性数学模型,验证了主动线圈和电源模型参数,计算了不同拉长比位形的等离子体增长率和最大可控垂直位移.利用TokSys建立了雪花、单零、双零偏滤器位形垂直不稳定仿真模型,然后通过simulink对采用PD算法的垂直不稳定系统进行仿真.结果表明,构建的模型能够较好控制不同位形的垂直不稳定性.     

HL-2M等离子体垂直不稳定性研究

用DⅢ-D的TokSys研究了HL-2M等离子体垂直不稳定性控制问题。使用真空室和主动线圈控制等离子体垂直不稳定性,分析了真空室的本征模和电流分布,极大简化真空室建模难度,建立了垂直不稳定性数学模型,验证了主动线圈和电源模型参数,计算了不同拉长比位形的等离子体增长率和最大可控垂直位移。利用TokSys建立了雪花、单零、双零偏滤器位形垂直不稳定仿真模型,然后通过simulink对采用PD算法的垂直不稳定系统进行仿真。结果表明,构建的模型能够较好控制不同位形的垂直不稳定性。     

HL-2M等离子体垂直不稳定性的反馈控制研究

使用无源稳定导体和主动控制线圈来控制HL-2M等离子体的垂直不稳定性。计算了等离子体垂直不稳定性增长时间,构建了等离子体垂直不稳定性控制的线性模型,然后用MATLAB对采用PID算法的垂直不稳定性控制系统进行了模拟仿真。结果表明,无源稳定导体和主动控制线圈能够快速稳定等离子体的垂直不稳定性运动,这也表明设计是可行的。     

Rossby waves in the magnetic fluid dynamics of a rotating plasma in the shallow-water approximation

We have studied rotating magnetohydrodynamic flows of a thin layer of astrophysical plasma with a free boundary in the β-plane. Nonlinear interactions of the Rossby waves have been analyzed in the shallow-water approximation based on the averaging of the initial equations of the magnetic fluid dynamics of the plasma over the depth. The shallow-water magnetohydrodynamic equations have been generalized to the case of a plasma layer in an external vertical magnetic field. We have considered two types of the flow, viz., the flow in an external vertical magnetic field and the flow in the presence of a horizontal magnetic field. Qualitative analysis of the dispersion curves shows the presence of three-wave nonlinear interactions of the magnetic Rossby waves in both cases. In the particular case of zero external magnetic field, the wave dynamics in the layer of a plasma is analogous to the wave dynamics in a neutral fluid. The asymptotic method of multiscale expansions has been used for deriving the nonlinear equations of interaction in an external vertical magnetic field for slowly varying amplitudes, which describe three-wave interactions in a vertical external magnetic field as well as three-wave interactions of waves in a horizontal magnetic field. It is shown that decay instabilities and parametric wave amplification mechanisms exist in each case under investigation. The instability increments and the parametric gain coefficients have been determined for the relevant processes.     

Hot Vertical-Displacement-Event Process due to Internal Energy Perturbations for HL-2M Tokamak Plasma

During the tokamak operation,variation of the stored energy can cause internal perturbations of the plasma.These perturbations may develop into large-scale vertical movement of the whole column for the vertically elongated tokamak,eventually generating the hot vertical displacement event(VDE).It will cause considerable damage to the machine.In this work,the hot VDE process due to stored energy perturbations is investigated by a mature non-linear time-evolution code DINA.The influence on the vertical instability,the displacement direction and the electromagnetic loads on in-vessel components during the hot VDE are analyzed.It is shown that a larger perturbation leads to faster development of the vertical instability.Meanwhile the variation of the Shafranov shift,due to the energy change,is related to the VDE direction.The vertical electromagnetic force on the vacuum vessel and the halo current flowing in the divertor baffle become larger in the case of VDE moving towards the X point.     

HT-6A托卡马克平衡系统的实验

本文叙述了HT-6A托卡马克平衡系统及第一期平衡实验结果.讨论了HT-6A上铜壳对平衡的贡献;观察到改变垂直场形态因子n而产生的水平位移及垂直位移不稳定现象;介绍了正常放电时的平衡实验,观察到等离子体位移与MHD扰动是紧密相连的;用沙弗拉诺夫薄壳理论计算了对多大的等离子体电流应施加多大的垂直场,结果与实验完全符合。     

Theoretical analysis of a non-contact spring with inclined permanent magnets for load-independent resonance frequency

In this paper a non-contact magnetic spring design is presented that uses inclined magnets to produce an adjustable relationship between load force and dynamic stiffness. With appropriate choice of parameters, the spring may either operate with a range of constant natural frequency against variable load forces, or a positive stiffness in one horizontal direction may be achieved in addition to having a positive vertical stiffness. Dynamic simulations are presented to assess the non-linear stability of a planar three degree of freedom version of the system; cross-coupling between horizontal and rotation motion is shown to compromise passive stability, in which case passive constraints or active control must be used to avoid instability. The design is scalable in that using larger magnets increases the load bearing capacity and decreases the natural frequency of the system.     

EAST上由垂直不稳定性引发破裂的分析与预测

从EAST 装置2016 年的放电实验中，选取了119 次等离子体破裂放电数据，分析诱发等离子体破裂的原因，发现约60%的破裂是由垂直不稳定性直接引起的，其破裂后将会产生更大的晕电流，从而产生更大的电磁应力损坏装置。对由垂直不稳定性引起的破裂(简称为VID)(72 次放电)进行了研究，建立了分别基于单变量(垂直位移)和两维变量(垂直位移、垂直位移增长率)的预测模型用于对VID 破裂的预测。离线测试表明，基于两维变量的预测模型可以在破裂发生前20ms 给出破裂预警信号，预测成功率达93%。     

Hall Currents and the Rayleigh-Taylor Instability of a Finitely Conducting Plasma in the Presence of Coriolis Forces

We have studied the effect of rotation on the development of Rayleigh-Taylor instability of an incompressible, viscous, Hall, finitely conducting plasma of variable density. The solution is developed, through variational methods, for a semi-infinite plasma in which the density varies exponentially along the vertical. It is found that the system is unstable for all wave numbers when the effects of magnetic resistivity are included. The effects of coriolis forces and viscosity on the growth rate of the unstable system are found to be stabilizing while that of Hall currents is destabilizing. Finite conductivity affects the growth rate of the unstable mode differently for the smaller and larger values of the wave numbers, destabilizing for the waves of large wave length and stabilizing for waves of small wave length.     

Observation of poloidal current flowed to the vessel after failure of vertical position feedback control in EAST Tokamak

Plasmas with vertically elongated cross-sections tend to be unstable to an axis-symmetric instability. This paper studies the magnetohydrodynamic equilibria in elongated plasmas after failure of vertical feedback control by using magnetic data for EAST device. Vertical forces on the vessel due to the induced polodial and toroidal currents are evaluated. The maximum force of the Fz_pol in vertical displacement events for EAST designed parameters is given.     

��ֱλ���¹���ITER���ΰ���ĵ�ų�����

采用有限元方法计算了垂直位移事故中ITER包层系统及周围主要部件的电磁场力和力矩。通过ANSYS APDL动态模拟垂直位移事件过程中等离子体电流的形状和大小,并加载外界磁场,计算得到了包括包层在内的所有导体内部的感应电流分布。通过计算,得到了各个位置的包层模块的力和力矩,可用于评估该事故下包层系统的安全性。     

垂直位移事故中ITER屏蔽包层的电磁场分析

采用有限元方法计算了垂直位移事故中ITER包层系统及周围主要部件的电磁场力和力矩。通过ANSYS APDL动态模拟垂直位移事件过程中等离子体电流的形状和大小,并加载外界磁场,计算得到了包括包层在内的所有导体内部的感应电流分布。通过计算,得到了各个位置的包层模块的力和力矩,可用于评估该事故下包层系统的安全性。     

Effect of sample shape on nonlinear magnetization dynamics under an external magnetic field

Effect of sample shape on the nonlinear collective dynamics of magnetic moments in the presence of oscillating and constant external magnetic fields is studied using the Landau–Lifshitz–Gilbert (LLG) approach. The uniformly magnetized sample is considered to be an ellipsoidal axially symmetric particle described by demagnetization factors and uniaxial crystallographic anisotropy formed some angle with an applied field direction. It is investigated as to how the change in particle shape affects its nonlinear magnetization dynamics. To produce a regular study, all results are presented in the form of bifurcation diagrams for all sufficient dynamics regimes of the considered system. In this paper, we show that the sample's (particle's) shape and its orientation with respect to the external field (system configuration) determine the character of magnetization dynamics: deterministic behavior and appearance of chaotic states. A simple change in the system's configuration or in the shapes of its parts can transfer it from chaotic to periodic or even static regime and back. Moreover, the effect of magnetization precession stall and magnetic moments alignment parallel or antiparallel to the external oscillating field is revealed and the way of control of such “polarized” states is found. Our results suggest that varying the particle's shape and fields’ geometry may provide a useful way of magnetization dynamics control in complex magnetic systems.     

Study of Globus-M Tokamak Poloidal System and Plasma Position Control

In order to provide efficient performance of tokamaks with vertically elongated plasma position, control systems for limited and diverted plasma configuration are required. The accuracy, stability, speed of response, and reliability of plasma position control as well as plasma shape and current control depend on the performance of the control system. Therefore, the problem of the development of such systems is an important and actual task in modern tokamaks. In this study, the measured signals from the magnetic loops and Rogowski coils are used to reconstruct the plasma equilibrium, for which linear models in small deviations are constructed. We apply methods of the H∞-optimization theory to the synthesize control system for vertical and horizontal position of plasma capable to working with structural uncertainty of the models of the plant. These systems are applied to the plasma-physical DINA code which is configured for the tokamak Globus-M plasma. The testing of the developed systems applied to the DINA code with Heaviside step functions have revealed the complex dynamics of plasma magnetic configurations. Being close to the bifurcation point in the parameter space of unstable plasma has made it possible to detect an abrupt change in the X-point position from the top to the bottom and vice versa. Development of the methods for reconstruction of plasma magnetic configurations and experience in designing plasma control systems with feedback for tokamaks provided an opportunity to synthesize new digital controllers for plasma vertical and horizontal position stabilization. It also allowed us to test the synthesized digital controllers in the closed loop of the control system with the DINA code as a nonlinear model of plasma.     

托卡马克中等离子体柱的位移稳定性

本文考虑托卡马克中纵场的作用以及等离子体柱和与之有互感的外迴路的相互作用,在圆截面,瘦环假设下,得到了自由运动时相对于沿水平方向、垂直方向的位移,以及小半径变化的一般稳定条件。由于强纵场的影响,一般来说,等离子体柱的小半径总是随着大半径的变化而改变,以维持通过等离子体角向电流迴路的磁通不变。对于这种扰动,当考虑到外迴路电流变化以后,稳定区域超过公式0关键词：     

托卡马克中等离子体的平衡重建

本文描述了用外部磁测量信号,和等离子体总电流,以及角向β_p的测量值,重建托卡马克中等高子体半衡的方法。对圆截面、非圆截面和偏滤器位形;对不同的电流分布分别作了重建计算。数值研究了测量误差、探针布置对重建结果的影响。     

Feedback Stabilization of a Corkscrew Istabilty

An application is made of lumped feedback to achieve stability of a distributed electromechanical system. A conducting elastic wire, placed in an axial magnetic field and carrying a current, exhibits instability at a certain threshold of magnetic pressure. The two dimensional transverse displacement of the wire is sampled and these signals are used to produce proportional feedback forces which allow stable equilibrium to be restored. A stability diagram is determined indicating the minimum feedback force to prevent static instability. For one station feedback, there is a maximum allowable feedback to prevent overstabil1 ity. In addition, the maximum value of destabilizing force which can be stabilized is somewhat less than that required for the second mode to become unstable. The wave dynamics of this corkscrew instability are related to several types of electromechanical interaction. The pinch confinement of a plasma, proposed as a scheme for containing a controlled thermonuclear reaction, suffers from a similar corkscrew instability.     

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.     

Thermoelectric rotating torus for fusion

A plasma toroid is rotated toroidally to supersonic speeds by external means. The input power maintains the rotation and also heats the plasma. The thermoelectric effect from the resulting temperature gradient creates and maintains a poloidal magnetic field against resistive decay, confining the plasma in steady state. The shear in the rotation keeps the plasma stable to MHD kinks and interchanges. Such a system has two novel advantages as a fusion device: there are no strong electromagnets needed to create the confining magnetic field, and there is effectively no limit on the field strength and, hence, no limit on the plasma pressure contained. The system has to be of a large aspect ratio, to minimize centrifugal effects, and a weak, external vertical magnetic field is needed to balance the radial hoop force.