低混杂波电流驱动中原副边回路相互作用

本文用速度空间二维高速电子Ｆｏｋｋｅｒ－Ｐｌａｎｃｋ方程和原、副边回路方程组成的方程组描述托卡马克装置低浊经杂民流驱动宏观参数，研究了低混杂波电流驱动中的电场效应和原、副边回路相互作用应用该程序，初步模拟了ＨＬ－１装置的ＬＨＣＤ实验。     

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。     

HL—1装置表面分析站的研制

等离子体与表面相互作用的重要性是人们公认的。我们试图在HL-1装置上原位测量表面状态,本文叙述了为HL-1研制的表面分析站及测得的一些结果。为装置提供了实验数据。     

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.     

托卡马克工程试验混合堆等离子体性能的等值线图分析

本文简要叙述托卡马克工程试验混合堆等离子体概念设计的物理基础,对等离子体性能进行了等值线图(Plasma Operation Contour)分析。根据工程试验混合堆的要求,得出一组等离子体参数。     

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。     

Diffusive Losses and Scaling Law for Large Tokamaks

Under plasma conditions aimed for in the next generation of tokamak devices, it is necessary to consider a multi-parameter model for diffusive energy losses which would limit the temperatures and confinement times attainable. In this paper, we study a model for plasma diffusion in a reactor size tokamak considering various plasma parameters (like density, temperature, spatial gradients, collisional effects, etc.) and also topological elements of the magnetic configuration (like magnetic shear, magnetic curvature, etc.).     

A CONCEPT FOR NEXT STEP ADVANCED TOKAMAK FUSION DEVICE

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HL-2A装置大拉长比和三角形变等离子体位形设计

介绍了基于MATLAB 程序自主开发的等离子体位形编辑和设计代码SE,包括其设计原理、主要功能、人机界面和操作步骤。通过SWEQU 代码对SE代码的准确性进行了有效验证,分别用上述两种代码设计和验证了两种具有中等拉长比和三角形变位形的放电参数。具有较高拉长比和三角形变位形的实现需要投入装置的上偏滤器线圈来突破圆形截面的限制。最后通过SE代码编辑了一个较大拉长比和三角形变的等离子体位形,并获得了相应的放电参数。结果表明,在HL-2A 装置投入上偏滤器线圈后,可以得到具有较大拉长比和三角形变的新等离子体位形,这些位形为提高HL-2A 等离子体的品质奠定了坚实的基础。     

低杂波驱动中增强的电子回旋辐射

本文基于三波共振相互作用，研究了低杂波驱动的高频电磁辐射。Ｖｌａｓｏｖ方程的导向中心形式被用来推导包括动力效应的耦合系数。在小ｋｚ近似下，给出了耦合系数中的所有速度积分。对一般非线性色散关系进行了详细理论分析，结果表明：（１）低杂泵浦波可以激发电子Ｂｅｒｎｓｔｅｉｎ波，并伴随高频电磁辐射；（２）以这种方式激发的电磁辐射是一种热电子回旋辐射，辐射强度随着等离子体温度和密度的增加而增加。这样我们可以假定，本非线性不稳定性可以成为低杂波驱动中增强电子回旋辐射及等离子体电子回旋辐射的起因。     

First results of movable limiter experiments and its effects on the tokamak plasma confinement

Limiters play a number of roles in the tokamak operation. It serves primarily to protect the wall from the plasma when there are disruptions, runaway electrons, or other instabilities and also the limiters localize the plasma–surface interaction. In this research, we presented the first results of movable limiter experiments and its effects on the tokamak plasma confinement. For this purpose, we designed, constructed, and installed a movable localized poloidal limiter, and then measured the effects of limiter position on the time intervals of plasma parameters such as plasma density, temperature, and energy confinement time. The results of effects of the movable limiter experiments on plasma confinement.     

D-~3He商用堆工作物理参数的空间分析

由于D-~3He聚变堆不要求厚的包层和大的内侧空间,中子壁负载小得多,第一壁几乎是永久性的,维修更换问题减轻。采用低径比有利于电流驱动和较大的等离子体变形和好的垂直稳定性,以便得到大的等离子体电流,因而得到高的β和好的约束。本文从目前普遍采用的堆芯等离子体物理规律为基础,编制了DHE3TOK程序。研究了以D-~3He为燃料,低径比A=2.5工作在第一稳定区的商用堆特点。对它的工作物理参数空间范围进行广泛调查的基础上,提出了需要研究和发展的关键工程技术问题。     

非自持和非麦氏分布情况下托卡马克堆芯等离子体功率平衡

本文给出一组托卡马克堆芯等离子体功率平衡方程,它描述了在非自持和非麦氏分布情况下等离子体功率平衡的问题,计算结果表明。在现实可行的聚变堆工程和相应的等离子体参数情况下,堆芯中每秒可产生聚变中子PN大于10~19。     

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。      

用于热核聚变加热的FEM

世界各国的实验室正在开展研究的频率为１００－３００ＧＨｚ的高功率自由电子脉塞（ＦＥＭ），主要用于托卡马克变等离子体的电子回旋共振加热，采用三维ＷＡＧＦＥＬ数值模拟程序，结合ＨＬ－２Ａ装置的要求，提出了一个平均输出功率为１ＭＷ，频率为８０ＧＨｚ的ＦＥＭ理论方案，此方案对今后ＨＬ－２Ａ装置ＦＥＭ的设计论证是有参考价值的。     

HL-1装置供电及控制系统调试

本文在介绍供电系统及其主要技术参数和调试概况的基础上,着重分析了电源参数与等离子体参数间的关系,叙述了获得平衡稳定等离子体的调试过程,并对供电回路的退耦方法进行了初步探讨。     

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.     

Spectroscopic Diagnostic of the Peripheral Plasma in the Globus-M2 Tokamak with the Injection of Neutral Helium

JETP Letters - The diagnostic of the peripheral plasma parameters in terms of the relation of lines of neutral helium is included in the diagnostic complex of the tokamak Globus-M2. The first...     

Measurement and analyses of the mean effective ion charge in the centre of tokamak discharges

There are two different definitions for specifying the mean effective ion charge Z_eff in plasmas: a) from the Spizer electrical resistivity of the plasma and b) from bremsstrahlung radiation losses of the plasma. In this paper Z_eff in the centre of tokamak ohmic discharges has been determined from information on sawtooth-relaxations of the steady state plasma, based on the analysis for the power balance of the plasma electrons in the plasma centre during the period of recovery after the sawtooth crashes. This method is found to supply reliable results for tokamak parameters. While its application requires some efforts in data analysis, it can provide a reliable determination of Z_eff, independent of the information from bremsstrahlung radiation losses of the plasma.     

托卡马克等离子体中q=2面附近的磁流体驰豫现象

本文在采用一维圆柱输运模型来摸拟托卡马克等离子体欧姆加热时,考虑了杂质辐射与磁岛演变的耦合作用。我们发现,在一定参数条件下,m/n=2/1的磁岛宽度及相应于q=2面附近的电子温度会产生驰豫振荡。本文主要讨论了出现这种驰豫现象的原因及其对增强托卡马克约束的意义。