用磁探针反演磁岛二维结构的方法及其在HL-2A装置上的应用

介绍了HL-2A装置中利用磁探针数据反演磁岛极向二维结构的新方法,以及在反演基础上建立的撕裂模动态分析方法。在实验中通过磁探针测量确定作为扰动磁场来源的扰动电流。将扰动磁通与由EFIT重建的平衡磁通叠加反演出磁岛的结构,并给出磁岛的宽度。然后,按时间顺序建构二维结构图并依次记录,之后依次展现图像就可以对磁岛进行动态分析。应用此方法进行撕裂模分析,得出了磁岛旋转与电子抗磁漂移方向相同,验证了磁岛宽度与扰动场的关系及ECRH对磁岛的抑制作用。这显示了磁探针反演磁岛结构方法的直观性,对观察并控制MHD不稳定性非常有利。     

Studies of internal magnetic fluctuation in the HL-1M tokamak

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托卡马克等离子体中内部磁扰动的测量研究

热等离子体中内部磁扰动水平可以由逃逸电子输运来确定，逃逸电子输运采用扰动实验和稳态实验等四种不同方法较容易获得某些局域的逃逸扩散系数，首先利用等离子体快速移动实验，测量孔栏上硬X射线通量的变化，获得边缘扩散系数；第二，由微波辐射强度和硬X射线通量(HXR)信号的锯齿振荡的峰值延迟时间得到径向位置某处到孔栏之间平均扩散系数；第三，软X射线(SXR)强度和HXR通量的信号的锯齿振荡的峰值延迟时间给出等离子体芯区外的径向平均扩散系数；第四，由来自孔栏上HXR韧致辐射谱求得逃逸电子平均能量，继而得到逃逸约束时间， 关键词： 逃逸电子输运 扩散系数 内部磁涨落 软X射线(SXR) 硬X射线 (HXR)     

Runaway electrons as a diagnostic of plasma internal magnetic fluctuations

The transport of runaway electrons in a high-temperature plasma is relatively easy to measure in a steady state experiment and a perturbation experiment, which provides runaway electron diffusion coefficient D_r. This diffusion coefficient is determined by internal magnetic fluctuations, so it can be interpreted in terms of a magnetic fluctuation level. The internal magnetic fluctuation level ($\tilde {b}_r/B_T is estimated to be about (2--4)×^-4 in the HL-1M plasma. The results presented here demonstrate the effectiveness of using runaway electron transport techniques to determine internal magnetic fluctuations. A profile of magnetic fluctuation level in the HL-1M plasma can be estimated from D_r.     

Identification and Analysis of Magnetic Structures on HL-2A

1 Introduction Tearing modes in tokamak plasmas have been studied for many years In HL-2A tokamak, MHD instabilities are investigated by means of the Mirnov probes. The mode number can be determined by the methods of phase comparison analysis or correlation analysis from the experimental data of Mirnov probes, but the analysis of complicated mode structures is difficult. An identification and analysis method of magnetic islands is presented basing on simulation of the perturbation current and magnetic field in plasmas.     

Energy fluxes in helical magnetohydrodynamics and dynamo action

Renormalized viscosity, renormalized resistivity, and various energy fluxes are calculated for helical magnetohydrodynamics using perturbative field theory. The calculation is of firstorder in perturbation. Kinetic and magnetic helicities do not affect the renormalized parameters, but they induce an inverse cascade of magnetic energy. The sources for the large-scale magnetic field have been shown to be (1) energy flux from large-scale velocity field to large-scale magnetic field arising due to non-helical interactions and (2) inverse energy flux of magnetic energy caused by helical interactions. Based on our flux results, a primitive model for galactic dynamo has been constructed. Our calculations yield dynamo time-scale for a typical galaxy to be of the order of 10⁸ years. Our field-theoretic calculations also reveal that the flux of magnetic helicity is backward, consistent with the earlier observations based on absolute equilibrium theory.     

湍流雷诺协强及密度扰动对极向动量输运影响的实验研究

利用静电探针阵列对HL-2A边缘等离子体径向和极向速度进行了测量,获得了最后闭合磁面附近湍流的雷诺协强 以及 和 间相位差的剖面。实验表明,虽然 、 的幅值对雷诺协强的大小会有影响,但雷诺协强的变化趋势主要取决于二者相位差的变化;另一方面,欧姆放电以及不同电子回旋加热功率L模放电条件下的实验结果显示,密度扰动引起的粒子输运所带来的极向动量输运的贡献与雷诺协强项对极向动量输运的贡献是可比的。这表明在分析湍流引起的动量输运时必须考虑粒子输运的贡献。     

HL-2M 装置磁测量系统设计及初始放电实验结果

介绍了 HL-2M 装置上满足等离子体放电的磁测量系统的物理设计,主要包括磁探针、磁通环以及 电流测量系统的设计。通过 HL-2M 装置典型的放电位形参数对磁探针的极向布局、有效面积,磁通环的极向布 局以及测量等离子体电流的罗氏圈互感值进行了初步设计。目前,HL-2M 装置已经完成初始等离子体放电。各个 子系统均能达到其测量目标。      

HL-2A 装置偏滤器改造的初步设计

根据HL- 2A 装置的结构特点, 提出了HL- 2A 装置偏滤器系统改造的基本方向。对HL- 2A 极向场线圈系统进行了优化设计, 计算了单零平衡位形, 进行了开放式偏滤器的结构设计, 并对新的偏滤器系统进行了热分析和结构分析。结果表明, 新的偏滤器系统新的偏滤器系统能够满足具有一定拉长比和三角形变的等离子体放电要求。     

HL-2M等离子体对共振磁扰动线圈电流相位响应的模拟

在HL-2M托卡马克平衡位形(Ip=1.0MA,βN=1.62,q95=4.01)下,使用环形单流体程序MARS-F研究了等离子体对共振磁扰动(RMP)线圈电流相位差的响应.在最优相位差时,扰动磁场显著地改变边界层磁场的拓扑,形成明显的磁岛链,增加了等离子体在边界层的输运,降低了压强梯度,减小了对ELM的驱动.模拟结果...     

HL-1装置等离子体平衡的实验研究

用对称磁探针测量了HL-1装置等离子体环的水平位移和垂直位移,经微机数据处理系统即时给出了位移随时间的变化曲线,并对装置的杂散场情况作了讨论。实验表明,平衡场和杂散垂直场的合成场能保证等离子体平衡在孔栏中心附近的位置。     

HL-2A装置实时等离子体位形重建系统的加速优化

现有的HL-2A实时平衡重建系统采用的是网格尺寸为33×33,将无法满足HL-2M装置对控制精度和速度要求。为此开发了网格尺寸为129×129的重建系统,并通过GPU并行、算法重构等优化方法,使得新的重建系统在保证计算精度的情况下能够使得每一次平均重建计算维持在600μs内,可满足HL-2A和HL-2M中周期为1ms等离子体控制系统对重建系统精度和速度要求。     

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现有的HL-2A实时平衡重建系统采用的是网格尺寸为33×33,将无法满足HL-2M装置对控制精度和速度要求.为此开发了网格尺寸为129×129的重建系统,并通过GPU并行、算法重构等优化方法,使得新的重建系统在保证计算精度的情况下能够使得每一次平均重建计算维持在600μs内,可满足HL-2A和HL-2M中周期为1ms等离子体控制系统对重建系统精度和速度要求.     

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描述了HL-2A等离子体实时平衡重建的GPU并行化算法,主要包括G-S方程的并行化处理、三对角方程求解、网格边界磁通计算以及一系列矩阵相乘的并行加速.并行后,在129×129的网格下完成一次迭代计算需要约575μs.     

HL-2A等离子体实时平衡重建的GPU并行化

描述了HL-2A等离子体实时平衡重建的GPU并行化算法,主要包括G-S方程的并行化处理、三对角方程求解、网格边界磁通计算以及一系列矩阵相乘的并行加速。并行后,在129×129的网格下完成一次迭代计算需要约575μs。     

HL-2A等离子体垂直振荡缓解边缘局域模实验观测

在HL-2A 装置实验中，通过对水平场加入方波扰动，实现了等离子体垂直运动。当等离子体向上垂直运动时，观察到了边缘局域模(ELM)缓解现象。研究发现，等离子体向上运动过程中边缘不断形成新的闭合磁面，导致等离子体体积膨胀，进而使台基宽度增加。此外，ELM 缓解期间杂质和工作气体再循环有所增加。等离子体向上运动过程中体积膨胀、工作气体再循环及杂质增加可能是导致ELM 缓解的主要物理因素。该实验可为未来聚变实验装置ELM 的控制提供一些参考。     

Analyses of edge plasma characteristics in HL-2A

The edge plasma characteristics are studied by both a movable array of Mach/Reynolds stress/Langmuir 10-probes in the boundary region and the fixed flush probe arrays on the 4 divertor neutralization plates at the same toroidal cross-section in the HL-2A tokamak. The dependence of the Reynolds stress on poloidal flow in the edge plasma is analysed. The result indicates that the sheared poloidal flow in tokamak plasma can be induced by the radial gradient of Reynolds stress. In the divertor experiments of HL-2A, the profiles of the electron temperature, density and floating potential on divertor plates are measured by the flush probe arrays. The edge electron temperature in divertor configuration is higher than that in limiter configuration. The temperature asymmetry between outer and inner target plates is observed. The result of magnetic surface reconstructed from 18 Mirnov coils signals is presented. Both the particle recycling and the impurity flux in the bulk plasma during divertor discharges are discussed. Neutral gas pressure in divertor chamber, measured by fast ionization gauge during divertor discharge, is given.     

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HL-2A和HL-1M装置采用了激光吹气注入高Z杂质来缓减大破裂中的等离子体电流衰竭,并给出了初步实验结果。在HL-2A装置上建立了利用MHD扰动的参量预报放电破裂先兆的报警系统,研制了MHD实时检测与处理系统,实现了放电破裂先兆的预报、快速触发激光吹气、形成阻性高辐射等离子体、消耗热能和磁能,缓减大破裂。实验证明,这是一种使得大型聚变实验装置在放电破裂之前显著减少等离子体中热能和磁能,而且能安全终止放电的简单、快速和有效的途径。     

Mitigation and prediction of disruption on the HL-2A Tokamak

Injection of high-Z impurities into plasma has been proved to be able to reduce the localized thermal load and mechanical forces on the in-vessel components and the vacuum vessel, caused by disruptions in Tokamaks. An advanced prediction and mitigation system of disruption is implemented in HL-2A to safely shut down plasmas by using the laser ablation of high-Z impurities with a perturbation real-time measuring and processing system. The injection is usually triggered by the amplitude and frequency of the MHD perturbation field which is detected with a Mirnov coil and leads to the onset of a mitigated disruption within a few milliseconds. It could be a simple and potential approach to significantly reducing the plasma thermal energy and magnetic energy before a disruption, thereby achieving safe plasma termination. The plasma response to impurity injection, a mechanism for improving plasma thermal and current quench in major disruptions, the design of the disruption prediction warner, and an evaluation of the mitigation success rate are discussed in the present paper.     

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利用静电探针阵列对HL-2A边缘等离子体径向和极向速度进行了测量,获得了最后闭合磁面附近湍流的雷诺协强〈(v)r(v)θ〉以及(v)r和(v)θ间相位差的剖面.实验表明,虽然(v)r、(v)θ的幅值对雷诺协强的大小会有影响,但雷诺协强的变化趋势主要取决于二者相位差的变化;另一方面,欧姆放电以及不同电子回旋加热功率L模放电条件下的实验结果显示,密度扰动引起的粒子输运所带来的极向动量输运的贡献与雷诺协强项对极向动量输运的贡献是可比的.这表明在分析湍流引起的动量输运时必须考虑粒子输运的贡献.