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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。     

HL-2A装置主机改造的初步方案

HL-2A装置自2003年首次实现等离子体单零偏滤器位形以来，运行参数逐步提高。目前获得了纵场2．7T，等离子体电流厶为410kA的结果，基本达到装置常规运行的指标。由于装置是封闭式偏滤器结构，不能形成拉长的等离子体截面，等离子体参数的进一步提高受到了限制。为了开展更深入的实验研究，装置的升级改造是非常必要的。     

HL-2A装置主机真空性能的改善

HL-2A装置真空室内部件数目繁多，容器本体上的密封部位多达几百个，特别是真空室内多极场线圈真空套从真空室的预装阶段开始，经常会出现一些漏气问题，此问题在原ASDEX运行时就是一个棘手的问题，已进行了多次修补。大部分漏点均发生在厚度仅为约0．2mm的波纹管上，无法采用氩弧焊接，所有这些漏点的修补均采用无铅焊料通过钎焊工艺完成。     

HL-2A装置真空壁条件实验研究与装置改造的概念设计

本文对HL-2A装置开展的真空壁处理技术和壁条件研究结果进行了介绍。HL-2A主机改造的概念设计取得了新的进展，本文同时介绍了主机改造方案，并给出概念设计的初步结果。     

HL-2A装置偏滤器位形研究

1研究方法 等离子体边界是托卡马克平衡运行时等离子体截面的极向磁通函数的等高线，它决定等离子体位形。位形是托卡马克装置实验和工程设计的重要参数，它是由等离子体电流及其分布以及外极向场线圈电流配置共同决定的。     

HL-2A装置杂质线辐射测量的初步结果

杂质作为等离子体和第一壁相互作用的产物，由于能强烈地影响等离子体品质而一直是人们关注的焦点之一。杂质作为托卡马克中热辐射和冷电子的来源，影响等离子体能量和粒子的平衡，进而影响等离子体密度、温度和电流的分布，制约着托卡马克等离子体的输运和稳态运行。     

HL-2A偏滤器位形的边缘等离子体特性

本实验利用主真空率和偏滤器靶板上的静电探针阵列直接测量边缘和偏滤器室的等离子体参数，即边缘温度Tea，密度nea，悬浮电位Фf，径向电场Er及其梯度dEr／dr，极向电场Ep，径向流速vr，极向流速vp.     

Impurity Behaviours of HL-2A Divertor Tokamak during the Initial Operation Period

In order to avoid destroying the vessel wall and poisoning the plasma, at the same time to efficiently extract the waste product of the fusion process from the system, divertors were adopted in some machines just at the beginning of dealing with this problems. Up to now, the remarkable progress has been made in this respect field . In order to understand the physics behind divertors, HL-2A tokamak with two closed divertors was successfully built in 2002. Its parameters are as follows：     

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.     

实验物理与工业控制系统平台在HL-2A主机测控系统中的应用

描述了利用实验物理与工业控制系统(EPICS)平台对HL-2A主机运行参数进行的集中测控系统开发。系统采用s7nodave设备驱动模块,实现了SoftIOC与各PLC的通讯,将各子系统的PLC集成到了EPICS控制系统中。通过对关系型数据库和应用层软件CSS中数据归档及报警等组件的扩展与配置,实现OPI层与各个子系统的实时通信。测控系统成功地将HL-2A主机参数集中在EPICS平台下运行,为下一代装置的主机集中测控系统设计打下了基础。     

Recent Experimental Results of HL-1M Tokamak and Progress of HL-2A Project

Recent experimental results of HL-1M tokamak and progress of HL-2A project are presented. Strong fishbone instability was observed during off-axis ECRH. This is first observation of the fishbone instability purely driven by energetic electrons produced by ECRH. The MBI was first proposed and demonstrated on HL-1M. Recently new results of MBI experiment were obtained by increasing the pressure of gas. A stair-shape density increment was obtained with high-pressure multi-pulse MBI just like the density evolution behavior during the multipellet injection. It is shown     

Fast Bolometer Arrays on the HL-2A Tokamak

Bolometers are considered to be a standard diagnostic for fusion experiments, mainly for measuring the total radiated power and spatial profiles of the local radiation power density. New design and the first result are presented from three AXUV arrays with high temporal resolution installed on the HL-2A tokamak. This high temporal resolution allows the study of transient radiative phenomena.     

The Power Supply System for HL-2A Tokamak

The HL-2A is the first divertor tokamak in China. Its construction is based on the main components of ASDEX from IPP and an entirely new power supply system is required to power its magnetic field coils and the plasma heating system. The most important electric parameters of HL-2A are toroidal field of 2. 8kA with a flat topT, plasma current of 450 of 5 s.     

HL-2A装置等离子体可见光成像系统

为了配合HL-2A装置的工程联调和首次等离子体放电，需要一种可靠和直观的诊断手段，以确认产生了所谓的“First plasma”(初始等离子体)放电。为此我们研制了一套新的诊断系统，即等离子体可见光成像。等离子体成像是近年来发展起来的一项先进诊断手段。目前在托卡马克装置上广泛采用。     

Construction of the HL-2A Tokamak

HL-2A is the first tokamak with divertor in China. The objectives of HL-2A are to produce more adaptable divertor configurations to study energy exhaust and impurity control, and to study enhanced core plasma confinement by profile control and moderate plasma shaping. HL-2A has well optimized operational flexibility and excellent accessi-bility for the diagnostic systems to facilitate various plasma experiments.     

HL-2A装置LHCD实验的控制

为了研究非感应方式等离子体电流的产生，在HL-2A装置上开展了低杂波电流驱动实验，并对LHCD实验进行了微机控制。在2004年的实验中准确无误地将微波投入了装置，实现了对整个LHCD系统运行状态的监控和系统保护。在等离子体破裂时，控制系统会立即切断微波对装置的投入。     

FBI程序对HL-2A装置等离子体边界计算的初步结果

JT-60U装置上的FBI程序是运行于UNIX操作系统下综合的等离子体参数计算系统，该程序已在HL-2A装置上采用了，其主要计算模块的功能是使用等离子体边界外的电磁测量信号，利用丝电流方法识别等离子体边界。程序引进时最大程度地考虑了两个装置电磁测量系统、装置尺寸结构和线圈系统的不同而进行了修改。     

HL-2A装置偏滤器中的微波干涉仪测量

微波干涉仪测量等离子体电子密度是一种常规监测工具，利用这种工具可以给出电子密度随时间变化的波形图。等离子体电子密度和微波干涉仪测出的相位差之间的关系为：