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。     

CFETR包层等效电阻率对等离子体垂直位移增长率的影响

基于CFETR工程设计,使用TOKSYS建立了CFETR极向场线圈、真空室壁和包层结构的等效二维模型.在三种平衡的等离子体位形下,分析了包层结构整体等效电阻率和极向不同位置的等效电阻率对等离子体垂直位移增长率的影响.结果表明,垂直位移增长率随着包层整体等效电阻率的增加近似线性增大;降低极向±60°附近的等效电阻率,能减...     

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为进一步提高HL-2A装置的放电参数和优化等离子体位形，给出了三种可能的主机改造途径：保留真空室，去掉并调整真空室内部分多极场线圈的局部改造方案；保留真空室，重新布局极向场线圈的中等规模改造方案；重新设计真空室和极向场线圈系统的大规模改造方案。对三种改造方案对放电参数和位形的影响和改造工程的可行性进行了分析比较，重新设计真空室和极向场线圈系统的大规模改造方案是最佳选择。     

正弦（余弦）线圈探测等离子体位移方法的改进

用正弦(余弦)线圈与相应鞍形线圈感应信号的相加积分,来得到等离子体电流重心位移,是中小型托卡马克装置常用的方法,对了解与控制等离子体的平衡稳定,具有重要意义。但是在实际上由于中小装置放电时间较短,对等离子体电流及电流重心位移一般不加完善的控制,它们以及外加平衡控制场在放电期间都可以发生明显改变,从而在真空室壁中引     

HL-2M 初始放电位形及波形设计

利用 EFIT 设计了可用于 HL-2M 初始放电的圆截面限制器位形以及偏滤器位形;设计了满足放电击 穿条件要求(零场区域平均杂散磁场应不超过 20G)的零场位形。综合分析放电过程伏秒数消耗及真空室涡流的影 响,使用 PF8 线圈电流补偿真空室涡流产生的杂散磁场,设计了等离子体电流 200kA 的限制器位形及偏滤器位形 的自洽的放电波形。将该放电波形作为放电调试的参考波形,成功实现了限制器位形的初始放电实验。      

第一届核聚变与等离子体物理理论工作学术交流会报告目录

笼一目、作者(西南物理研究所).-、1.磁约束聚变研究的一些进展李正武2.撕架模的动力理论J卜丁厚昌L 3.非理想电导管等离子体的螺旋不稳定性马腾才宫野刘之景朴 4.有限回旋半径效应对环流器气球模的影响石秉仁隋国芳 5.非圆环流器等离子体的高。气球模不稳定性李芳著石秉仁 6.小环径比锐边界等离子体的扭曲模不稳定性一顾永年 了.线圈对非圆托卡马克等离子体中的轴对称模的稳定化作用王中天 8.场反向位形的等离子体李国炳 9.环形的反场箍缩平衡和稳定张鹏10.电流非单调分布时的电阻流体不稳定性马腾才宫野11.场反向箍缩的有限电阻不稳定性…     

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。     

托卡马克垂直不稳定性控制

本文用拉普拉斯变换研究了具有被动和主动控制系统的托卡马克克ＤＮ等离子体的垂直不稳定性控制，求得了系统的稳定性参数和临界拉长度，找到了托卡马克反馈增益参数的第二阻尼稳定运行区。     

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根据基尔霍夫电律和牛顿力学,推导出了HL-2A等离子体平衡响应线性模型。基于matlab/simulink仿真平台并利用HL-2A装置历史实验数据,对等离子体响应模型进行了仿真分析。结果表明,此响应模型能够较好地反映极向场线圈电压与等离子体参数、磁通、磁场等物理量之间的关系,可以作 HL-2M装置位形控制器的研究设计基础。     

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.     

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.     

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。     

Tokamak position control

A set of sensing coils to measure plasma position is described. The possibility of placing these coils outside a vacuum vessel (as a resistive shell) is considered by analyzing a feedback system for controlling otherwise unstable axisymmetric motion. A simple model was used to study the axisymmetric stability of a noncircular plasma surrounded by a conducting vacuum vessel and a feedback control system. Suitable choice of the various constants allowed a study of either horizontally or vertically unstable motion, either with or without an iron core and with various configurations for the vacuum vessel. Analytic expressions for the stability limits are derived, together with the specific response to a requested step displacement, giving the overshoot, steady-state error, decay times, and maximum power supply voltage. By suitably choosing an effective decay index both vertical and horizontal motion were studied. The results are applied to TEXT Upgrade (horizontal elongated, with iron core, horizontal unstable) using an effective decay index of -1     

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.     

HT—6M闭环反馈平衡控制系统

本文描述HT-6M托卡马克装置闭环反馈平衡控制系统的结构组成,通过对各个环节的简化,得到了有效实用的数学模型,进而分析了系统稳态和动态性能。实验结果表明,该系统运行可靠;并且,将等离子体环水平位移控制在2mm以内。     

EAST ICRF天线法拉第屏蔽的电磁分析

法拉第屏蔽是EAST 装置 ICRF天线的一个重要部件。鉴于法拉第屏蔽的结构安全性,通过运用有限元方法和公式对法拉第屏蔽在等离子体破裂和等离子体垂直位移事件两种工况下进行电磁和结构分析,获得了法拉第屏蔽在这两种工况下所受的电磁力、应力分布和变形情况。分析结果满足设计要求,并为法拉第屏蔽的结构安全性评估提供理论依据。     

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利用TSC程序非刚性、可变形等离子体模型的特点，对EAST装置等离子体由于发生垂直位移事件而产生破裂的过程进行了模拟，计算了halo电流和真空室应力在破裂过程中的变化情况，对不同初始条件的破裂情况进行了比较，并模拟了利用杀手弹丸注入快速熄灭等离子体的过程。