Plasma confinement in tokamaks with robust torus

We present a non-linear symplectic map that describes the alterations of the magnetic field lines inside the tokamak plasma due to the presence of a robust torus (RT) at the plasma edge. This RT prevents the magnetic field lines from reaching the tokamak wall and reduces, in its vicinity, the islands and invariant curve destruction due to resonant perturbations. The map describes the equilibrium magnetic field lines perturbed by resonances created by ergodic magnetic limiters (EMLs). We present the results obtained for twist and non-twist mappings derived for monotonic and non-monotonic plasma current density radial profiles, respectively. Our results indicate that the RT implementation would decrease the field line transport at the tokamak plasma edge.     

EAST真空室内磁场模型的建立与验证

利用毕奥萨伐尔定律,通过对EAST内部等离子体电流的运动状态的研究,建立了EAST内部的磁场数学模型,并利用Matlab对实验数据的拟合分析,对模型进行了分析验证。通过误差分析,进而改进模型,研究表明改进后的模型与实验数据能较好吻合,误差较小。相关研究和结论对托卡马克真空室内磁场测量具有一定的指导意义,为进一步研究基于MEMS技术的超导托卡马克装置电磁测量诊断系统的微纳磁敏传感器奠定理论基础。     

Disruption Mitigation Using Laser Ablation of High-Z Impurities in HL-1M Tokamak

Major plasma disruptions are considered to be a serious problem for development of tokamak fusion reactors. The preliminary experiment results in HL-1M presented here describe the methods of amelioration of plasma current quench in major disruptions using laser ablation of high-Z impurities, which support the design of next generation large tokomaks like ITER. Using injection of impurity with higher electric charge can produce resistive highly radiating plasma and increase the radiation cooling of plasma to make a safe termination of the disruption. It can be possibly a simple and potential approach to decrease significantly the plasma thermal energy and magnetic energy before a disruption then obtain a safe plasma termination. The magnetic energy can be dissipated by impurity radiation .     

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利用毕奥萨伐尔定律,通过对EAST内部等离子体电流的运动状态的研究,建立了EAST内部的磁场数学模型,并利用Matlab对实验数据的拟合分析,对模型进行了分析验证.通过误差分析,进而改进模型,研究表明改进后的模型与实验数据能较好吻合,误差较小.相关研究和结论对托卡马克真空室内磁场测量具有一定的指导意义,为进一步研究基于MEMS技术的超导托卡马克装置电磁测量诊断系统的微纳磁敏传感器奠定理论基础.     

Determination of Plasma Position Using Poloidal Flux Loops and Comparison With Magnetic Probe Measurement in IR-T1 Tokamak

In this paper, we present two magnetic techniques for the measurement of plasma position in IR-T1 tokamak: a poloidal flux loop and a magnetic probe method. In the first method, two flux loops were designed and installed toroidally on the outer surface of the IR-T1 tokamak, and then, displacement of the plasma column was measured from them. In addition, to compare the plasma position obtained using the flux loops, an array of four magnetic probes was designed, constructed, and installed on the outer surface of the IR-T1 tokamak, and plasma position was measured from them. Results were compared and found to be in good agreement with each other.      

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。      

Tokamak plasma equilibrium analysis based on the relaxation method with a specified magnetic axis

In this contribution, we have presented two techniques for the determination of plasma equilibrium position in IR-T1 tokamak: relaxation and optical methods. An analysis method of tokamak plasma equilibrium by a relaxation method with a specified magnetic axis is presented. The degrees of freedom due to designated positions of the magnetic axis are possible by using poloidal field coil currents. Stable steady-state tokamak plasma equilibria are calculated along with the magnetohydrodynamic potential energy. The plasma generates a plasma current which partially or fully cancels the magnetic field from the poloidal field coils. For low-temperature plasmas, the plasma current distribution is centrally peaked; for high-temperature plasmas, the plasma current has a hole. A centrally peaked current distribution in a low-temperature plasma is evolved into a current distribution with a hole by increasing the plasma pressure by Ohmic heating, radio frequency heating, or by neutral beam injection heating. In the second technique, an image-processing technique was used for the output signal of the charge coupled device camera and plasma emission intensity profile and then the plasma position was obtained. Results are compared and discussed.     

Plasma Response to Resonant Perturbations at Tokamak Edge

In certain circumstances, plasma response suppresses magnetic islands expected at perturbed resonant magnetic surfaces. We investigate the plasma response to the resonant magnetic perturbations in a large aspect ratio tokamak perturbed by external resonant helical windings, considering polar toroidal coordinates for which analytical toroidal equilibrium solutions and perturbing fields are available. We apply an empirical approach to mimic the plasma screening effects by introducing presumed plasma current sheets on the resonance surfaces to cancel the RMP effects. Numerical examples show the effect of plasma response reducing magnetic islands at the plasma edge and also regularizing field lines around the resonant surface. The distribution of connection lengths along the plasma cross section indicates that the plasma response increases the connection lengths since more toroidal turns are performed until a field line reaches the tokamak wall.     

非圆截面托卡马克等离子体边缘磁场的解析解及重构方法

本文用傅里叶及边缘泰勒展开的方法，导出了非圆截面托卡马克等离子体边缘磁面的解析解及其重构的方法。最后作为例子，给出了在ＴＥＸＴ－Ｕ装置中按实际参数重构的等离子体边缘磁面结构及重构的误差。     

Effect of parallel flows and toroidicity on cross-field transport of pellet ablation matter in tokamak plasmas

The first complete set of time-dependent equations describing the cross-field drift of ionized pellet ablation matter in tokamak plasma caused by polarization in the nonuniform magnetic field has been developed and solved numerically. Important new features impacting the drift dynamics have been identified, including the effect of pressure profile variations in the tokamak plasma, curvature drive by near-sonic field-aligned (parallel) flows, and the rotational transform of the magnetic field lines, and are considered from the viewpoint of the parallel vorticity equation. These new features are necessary to obtain favorable quantitative agreement between theory and experimental fuel deposition profiles for both inner and outer wall launched pellet injection cases on the DIII-D tokamak.     

Disruption mitigation using laser ablation of high-Z impurities in HL-1M tokamak

A preliminary experiment triggering a plasma current quench by laser ablation of high-Z impurities has been performed in the HL-1M tokamak. The injection of impurities with higher electric charges into tokamak plasmas can increase the radiation cooling of the plasma. Resistive, highly radiating plasma formed prior to the thermal quench can dissipate both the thermal and magnetic energies, which is possibly a simple and potential approach to reducing significantly the plasma thermal energy and magnetic energy before a disruption thereby a safe plasma termination is obtained.     

Methods for reconstructing equilibrium plasma configurations in the Globus-M spherical tokamak

A magnetic diagnostics allowing one to reliably reconstruct equilibrium plasma configurations in a tokamak over a wide range of operating parameters is developed. The accuracy of determining the geometrical parameters and thermal energy of the tokamak plasma is analyzed in detail. The experimental data obtained in the Globus-M tokamak are processed the with help of the EFIT code. The influence of the plasma configuration on the intensity of the main impurity lines is investigated.     

Stochasticity from external magnetic field measurements

To determine whether or not magnetic field lines inside a tokamak plasma are stochastic we need the Fourier coefficients of any perturbing radial field inside the plasma. Usually what is measured with magnetic pick-up coils is the root mean square poloidal field outside the plasma. Although no unique transformation is available, we present a model which allows an interpretation of the measured (external) root mean square field in terms of the internal Fourier harmonics. The results are applied to particular TEXT discharges, and suggest a link between magnetic stochasticity and an increasing (more positive) radial electric field, as measured with a heavy ion beam probe     

HL—1装置偏压电极类H模能量约束时间研究

能量约束时间是衡量环流器等离子体约束性能的重要参数。分析表明，在加偏压电Ｌ模过渡到类Ｈ模的过程中，如果等离子体的辐射损失功率与总损失功率之比显著变化，则扣除辐射损失的能量约束时间的增量是一种更好的衡量约束得到改善的尺度。在这种考虑之下，我们讨论ＨＬ－１等离子体偏压电极Ｌ模－类Ｈ模过的能量约束及电子热传导特性。     

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用托卡马克模拟程序对实验前期的放电进行了模拟,获得了期望的等离子体演化过程及主要参数波形,如极向场线圈电流、等离子体电流、等离子体位置等。通过等离子体控制系统将模拟获取的参数波形用于实验,开展了等离子体R位置控制、完全程序场控制及RZIp控制下的放电模拟对实验的预测研究。模拟结果与实验吻合较好,表明放电模拟具有一定的可预测性,为今后EAST装置开展更深入的物理实验提供了一定的参考。     

EAST装置放电预测的初步研究

用托卡马克模拟程序对实验前期的放电进行了模拟,获得了期望的等离子体演化过程及主要参数波形,如极向场线圈电流、等离子体电流、等离子体位置等。通过等离子体控制系统将模拟获取的参数波形用于实验,开展了等离子体R位置控制、完全程序场控制及RZIp控制下的放电模拟对实验的预测研究。模拟结果与实验吻合较好,表明放电模拟具有一定的可预测性,为今后EAST装置开展更深入的物理实验提供了一定的参考。     

Magnetohydrodynamic equilibrium interpretation of low-aspect-ratio tokamak plasma

It is very important to calculate the equilibrium magnetic field configuration exactly and to estimate the parameters of the device needed for the equilibrium and stability in the design and operate the low-aspect-ratio tokamak, one of the axis-symmetrical torus devices which is widely used in the research of nuclear fusion using plasma. In the previous researches, there were the theoretical and numerical interpretation methods for the high-aspect-ratio tokamak plasma. But for the low-aspect-ratio tokamak plasma, numerical methods such as the finite element method and iteration method are usually used. In this research, we interpreted and examined the features of magnetohydrodynamic equilibrium of the low-aspect-ratio tokamak plasma in combination with the Green function method and finite element method which has high numerical value accuracy.     

多道干涉仪测量托卡马克等离子体电子密度

一、引 言 在目前托卡马克等离子体诊断中,采用垂直多道干涉仪测量等离子体电子密度时,由于等离子体水平位移的影响,使得测量信号在沿大环半径方向的分布是非对称的。这就要求采用非对称的Abel变换来给出等离子体电子密度的空间分布。一种常用的非对称Abel变换是分离变量法,它的基本思想是把测量信号分成对称元和非对称的权函数,对称部分采用标准的Abel变换,变换的结果乘上非对称的权函数。这种方法实际上是假定了等离子体电子密度弦积分值的不对称性与局部的不对称性是相同的;而且对称部分采用标准的Abel变换,如Barr的方法,Bockasten方法等。这些方法是把等离子体看成一个个同心圆,没有考虑到等离子体水平位移引起的弦长变化。本文采用一种新的变换方法,这种方法的特点是考虑到等离子体位移的实际情况。     

Pioneering experiments on atomic-beam-assisted generation of drag currents in the Globus-M spherical tokamak

Research data for drag currents in the Globus-M spherical tokamak are presented. The currents are generated by injecting atomic beams of hydrogen and deuterium. Experiments were carried out in the hydrogen and deuterium plasma of the tokamak. It has a divertor configuration with a lower X-point, a displacement along the larger radius from–1.0 to–2.5 cm, and a toroidal field of 0.4 T at a plasma current of 0.17–0.23 MA. The beam is injected into the tokamak in the equatorial plane tangentially to the magnetic axis of the plasma filament with an impact diameter of 32 cm. To provide a 28-keV 0.5-MW atomic beam with geometrical sizes of 4 × 20 cm (at a power level of 1/e), an IPM-2 ion source is used. The generation of noninductive currents is detected from a rise in the loop current and a simultaneous dip of the loop voltage. The injection of the hydrogen and deuterium atomic beams into the deuterium plasma results in a noticeable and reproducible dip of the loop voltage (up to 0.5 V). Using the ASTRA transport code, a model is constructed that allows rapid calculation of noninductive currents. Calculations performed for a specific discharge confirm that the model adequately describes the effect of drag current generation.     

KT—5B托卡马克上阿尔芬波加热实验中天线阻抗的测量

一、引 言 托卡马克等离子体中的阿尔芬波加热实验研究自80年代初以来取得了许多有价值的实验结果。在阿尔芬波加热实验中,天线辐射阻抗的测量是十分重要的。天线辐射阻抗的变化不仅直接反映了阿尔芬波与等离子体之间的能量耦合情况,而且也反映了波在等离子体中传播过程的某些物理特性。例如,出现离散阿尔芬波(DAW模)或表面静电波(SEW模)便会使阻抗出现较大的峰值。因此,探索一种简便易行又能反映阻抗随放电时间变化的细微