无导体壳托卡马克装置的对称磁探针

建议采用一种对称磁探针阵列，用于诊断无导体壳圆截面托卡马克等离子体的平衡位移。     

Computational Study of MHD Equilibrium of Noncircular Tokamak Reactor Plasmas

The MHD equilibrium and stability of noncircular tokamak plasmas limited by a separatrix is studied for reactor size systems. A typical example with a plasma current of 15.8 MA and major radius of 8.1 is presented. The required vertical field is generated by a set of discrete external coils and no conducting shell is included. The detailed equilibrium shape is calculated numerically for a vertical elongated plasma with two stagnation points symmetrically located above and below the midplane as would be required for a system with a poloidal divertor. The plasma height to width ratio is 2, the plasma shape factor is 1.6 and poloidal ? is 2.2. The plasma is locally stable. The general stability criteria with respect to quasi-rigid motions (special kink modes) are calculated numerically and found to be satisfied. Size scaling and the engineering constraints are discussed.     

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.     

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.     

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.     

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。     

Fast parallel Grad–Shafranov solver for real-time equilibrium reconstruction in EAST tokamak using graphic processing unit

To achieve real-time control of tokamak plasmas, the equilibrium reconstruction has to be completed sufficiently quickly. For the case of an EAST tokamak experiment, real-time equilibrium reconstruction is generally required to provide results within 1ms. A graphic processing unit(GPU) parallel Grad–Shafranov(G-S) solver is developed in P-EFIT code,which is built with the CUDA? architecture to take advantage of massively parallel GPU cores and significantly accelerate the computation. Optimization and implementation of numerical algorithms for a block tri-diagonal linear system are presented. The solver can complete a calculation within 16 μs with 65×65 grid size and 27 μs with 129×129 grid size, and this solver supports that P-EFIT can fulfill the time feasibility for real-time plasma control with both grid sizes.     

HT-7U超导托卡马克等离子体位形平衡和反演编码

介绍了应用于托克马克装置上等离子体位形平衡和反演编码(EFTT)的物理含义。提出了HT-7U装置EFTT代码开发移植的总体计划和主要流程结构,介绍了格林函数、平衡和反演核心子函数的构成。提出了在EFIT编码的移植开发中遇到的三类主要问题的解决方案。对编码产生的格林函数和等离子体特征参数的数据进行了分析比较。     

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。     

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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。     

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.     

HL-2A 装置可见光诊断方法初探

等离子体H_α 径向分布的测量是等离子体实验中的重要内容。在HL- 2A 实验中, 等离子体成像系统中的CCD 图片记录了等离子体辐射信息, 特别是H_α  线辐射信息( 在相机前加H_α 滤光片) 。因为光测量是辐射的线积分, 数据的处理和分析显得十分必要的。利用等离子体可见光成像系统, 采用Abel 变换, 得到H_α  在HL- 2A 装置中的径向分布, 提供了一项可靠的测量手段。     

J-TEXT 装置等离子体平衡重建与集成运算

利用Matlab 语言将EFIT 程序反演计算过程进行优化整合,简化了程序操作步骤,并增加了对计算结果的分析与存储功能。利用整合后的EFIT 程序,计算分析了J-TXET 装置放电过程中等离子体磁场位形和其它参数的演变,绘制了等离子体压强剖面图、等离子体电流密度和安全因子分布等磁面信息的重建结果。此外,还将反演结果与软X 射线测算数据进行比对。结果表明,改善后的EFIT 程序能够初步满足对实验放电的反演计算分析要求,为J-TXET 装置的放电控制和运行提供重要的参考数据。     

Analytic description of tokamak equilibrium sustained by high fraction bootstrap current

By using an expansion technique based on the tokamak ordering, the Grad－Shafranov equation is analytically solved for tokamak equilibrium sustained by a full bootstrap current. This approximate approach is suitable for equilibria with non-circular cross-sections of modest ellipse and triangular deformations. As an input parameter set, the plasma pressure profile and the electron and the ion temperature profiles can be selected as arbitrary functions of the averaged minor radius. Equilibrium properties of this plasma are discussed.     

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利用Matlab语言将EFIT程序反演计算过程进行优化整合,简化了程序操作步骤,并增加了对计算结果的分析与存储功能。利用整合后的 EFIT 程序,计算分析了 J-TXET 装置放电过程中等离子体磁场位形和其它参数的演变,绘制了等离子体压强剖面图、等离子体电流密度和安全因子分布等磁面信息的重建结果。此外,还将反演结果与软X射线测算数据进行比对。结果表明,改善后的EFIT程序能够初步满足对实验放电的反演计算分析要求,为J-TXET装置的放电控制和运行提供重要的参考数据。     

带铁芯托卡马克装置的等离子体平衡数值解法

本文提出一种计算铁芯变压器托卡马克装置中等离子体平衡的数值方法。将铁芯对等离子体平衡的影响等效地看作外部线圈电流的作用,这样问题就转化为求解空芯变压器装置的等离子体平衡问题。这一方法的另一特点是计算区域减至最小。     

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欧姆驱动条件下,托卡马克等离子体中的电流由欧姆驱动电流和等离子体内部的自恰电流构成。在简单的Spitzer电阻率模型下,欧姆驱动的环向电流密度剖面,主要由每一时刻的电子温度剖面和有效电荷数Zeff的剖面决定。讨论并给出了确定了平衡位形的基本方程,在大环径比近似下,给出了存在锯齿振荡条件下的环向电流剖面和小的非圆变形的平衡解。     

Study of the plasma equilibrium in Damavand tokamak via numerical solution of the Grad-Shafranov equation

In this work we study the Damavand tokamak plasma equilibrium with an elongated ross section and fixed boundary conditions. These equilibria are characterized by three parameters such as elongation, triangularity and magnetic axis shift. An iterative scheme f the moment’s method is used to solve the Grad-Shafranov equation in flux coordinate system. Magnetic flux surface contours and main equilibrium parameters have been btained by applying the geometry and boundary conditions of the Damavand 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.     

Hybrid Method for Tokamak MHD Equilibrium Configuration Reconstruction

A hybrid method for tokamak MHD equilibrium configuration reconstruction is proposed and employed in the modified EFIT code. This method uses the free boundary tokamak equilibrium configuration reconstruction algorithm with one boundary point fixed. The results show that the position of the fixed point has explicit effects on the reconstructed divertor configurations. In particular, the separatrix of the reconstructed divertor configuration precisely passes the required position when the hybrid method is used in the reconstruction. The profiles of plasma parameters such as pressure and safety factor for reconstructed HL-2A tokamak configurations with the hybrid and the free boundary methods are compared. The possibility for applications of the method to swing the separatrix strike point on the divertor target plate is discussed.