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。     

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。     

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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.     

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%。     

圆柱界面不稳定性的多组分气体动理学数值计算

在假定单元内各组分同温同速的条件下,采用气体动理学格式(Gas-Kinetic Scheme,GKS)对空气/He和空气/R22圆柱界面不稳定性进行了数值计算,得到不同时刻的密度分布以及界面上特征位置的位移历史和平均速度。当激波穿过界面后,界面上特征位置的位移随时间逐渐增大,特征位置的平均速度与前人的实验结果和数值模拟结果吻合很好。对比结果表明,从微观气体运动角度出发的GKS方法对于界面不稳定性问题具有良好的模拟能力。     

风速与风向对小尺度热晕不稳定性的影响

给出了两种特殊风向对小尺度热晕不稳定性扰动能量增长影响的实验及数值计算结果：当风向与扰动梯度方向平行时，风速对不稳定性有明显的抑制作用，而垂直优动梯度方向的风则对热晕不稳定性没有影响。     

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。     

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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。     

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。     

垂直不稳定性和逃逸电子的协合效应对HL-2A装置器壁的损伤

1垂直不稳定性的产生 非圆截面（通常是D形或豆形）等离子体的性能和能量约束时间优于圆截面，并且可获得更大的等离子体电流，但等离子体的垂直稳定性会因其被拉长而变坏，拉长比值k值愈大，则垂直不稳定性的可能性就增加。描述垂直不稳定性的重要参数有衰减指数n，稳定参数，和增长率参数y。     

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.     

Synergetic Effects of Runaway Electron and Vertical Instability on the Wall Damage on HL-2A Tokamak

1 Generation of vertical instability Tokamak experiments show that the energy confinement time and performance are better, and the larger plasma current can be achieved for non-circular cross-sectional shape of plasma than circular cross-section. However, the external magnetic fields which are used to produce the non-circular cross sectional shape also cause the confined plasma to become unstable to small vertical displacement. In general, the ratio of elongation k is larger, the possibility of instability is more. In practice, this vertical displacement mode stabilized by feedback control system or other provided external radial magnetic field to balance out the plasma motion. Under some of situations the control system may be fail due to rapid growth rate of instability exceeding the ability of controlling. The plasma will then move vertically upwards or downwards depending upon the characteristics of instability and control failure.     

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.     

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.     

Modulation instability of an intense laser beam in an unmagnetized electron–positron–ion plasma

The modulation instability of an intense circularly polarized laser beam propagating in an unmagnetized, cold electron–positron–ion plasma is investigated. Adopting a generalized Karpman method, a three-dimensional nonlinear equation is shown to govern the laser field. Then the conditions for modulation instability and the temporal growth rate are obtained analytically. In order to compare with the usual electron–ion plasmas, the effect of positron concentration is considered. It is found that the increase in positron-to-electron density ratio shifts the instability region towards higher vertical wave numbers but does not cause displacement along the parallel wave number direction, and the growth rate increases as the positron-to-electron density ratio increases.