托卡马克HT-7U低温超导磁体的绝缘系统

主要介绍低温超导托卡马克HT-7U中磁体的绝缘结构,绝缘材料的特性,绝缘结构形成的工艺,绝缘层的电性能和力学性能等。     

Superconducting Busline Design for HT—7U Tokamak

Superconducting (SC) tokamak HT-7U has seven pairs of buslines connecting toroidal/Poloidal coils and the current leads,These SC buslines(SCBLs) share a common cryostat and are made of the calbe in conduit conductors(CICCs) arranged as a decoupling configuration.In order to reduce the heat loads conducted from the seven current leads with a capacity of 15kA during the magnets cooldown.the buslines with a much lower thermal conduction were employed in comparison with the current leads,and a special cooling loop was designed.     

Recent Progress of HT-7U Superconducting Tokamak

HT-7U is a superconducting tokamak. which is being constructed in Institute of Plasma Physics, Chinese Academy of Sciences. The mission of the HT-7U project is to develop a scientific and engineering basis of the steady state operation of advanced tokamak.The engineering design of the device has been optimized. The R&D program is going on. Short samples of the conductor and a CS model coil were tested. All the TF and PF coils will be manufactured and tested in Institute of Plasma Physics. Therefore, a 600-meter long jacketing line for cable-in-conduit conductors along with two winding machines, a set of VPI equipment and a test facility for the TF and PF coils are ready in ASIPP now. In this paper, the recent progress of the HT-7U is described.     

低通PID算法在HT-7密度控制系统中的应用研究

PID控制是反馈控制系统中最常用的控制方法,基于数字滤波技术设计的低通滤波PID算法通过滤掉误差信号中的噪音信号从而提高了算法的控制效果.介绍了HT-7密度控制系统结构,详细说明了该控制算法的原理及实现过程,该算法在HT-7密度控制系统中应用,得到了很好的控制效果.     

Design of Amplifier Circuit for the HT-7 Tokamak Thomson Scattering System

Thomson scattering diagnostic is important for measuring electron temperature and density profiles. To improve the signal-to-noise ratio, a silicon avalanche photodiode （APD） with high quantum efficiency, high sensitivity, and high gain up to 100 was adopted to measure the Thomson scattering spectrum. A preamplifier, which has low noise, high bandwidth, and high sensitivity, was designed with suitable transimpedance. Using AD8367 as the post-amplifier, good performance of the APD readout electronics have been obtained. A discussion is presented on the performance of the amplifier using a laser diode to simulate the Thomson scattering light. The test results indicate that the designed circuit has a high amplifying factor and fast rising edge. So reduction of the integral gate of the CAMAC ADC converter can improve the signal-to-noise ratio.     

Upgraded data service system for HT-7 Tokamak

A data service system plays an indispensable role in HT-7 Tokamak experiment. Since the former system doesn＇t provide the function of timely data procession and analysis, and all client software are based on Windows, it can＇t fulfill virtual fusion laboratory for remote researchers. Therefore, a new system which is simplified by three kinds of data servers and one data analysis and visualization software tool has been developed. The data servers include a data acquisition server based on file system, an MDSplus server used as the central repository for analysis data, and a web server. Users who prefer the convenience of application that can be run in a Web Browser can easily access the experiment data without knowing X-Windows. In order to adjust instruments to control experiment the operators need to plot data duly as soon as they are gathered. To satisfy their requirement, an upgraded data analysis and visualization software GT-7 is developed. It not only makes 2D data visualization more efficient, but also it can be capable of processing, analyzing and displaying interactive 2D and 3D graph of raw. analyzed data by the format of ASCII, LZO and MDSplus.     

Insulating process for HT-7U central solenoid model coils

The HT-7U superconducting Tokamak is a whole superconducting magnetically confined fusion device. The insulating system of its central solenoid coils is critical to its properties. In this paper the forming of the insulating system and the vacuum-pressure-impregnating (VPI) are introduced, and the whole insulating process is verified under the superconducting experiment condition.     

The Compression Algorithm for the Data Acquisition System in HT－7 Tokamak

HT-7 superconducting tokamak in the Institute of Plasma Physics of the Chinese Academy of Sciences is an experimental device for fusion research in China. The main task of the data acquisition system of HT-? is to acquire, store, analyze and index the data. The volume of the data is nearly up to hundreds of million bytes. Besides the hardware and software support, agreat capacity of data storage, process and transfer is a more important problem. To deal with this problem, the key technology is data compression algorithm. In the paper, the data format in HT-7 is introduced first, then the data compression algorithm, LZO, being a kind of portable lossless data compression algorithm with ANSI C, is analyzed. This compression algorithm, which fits well with the data acquisition and distribution in the nuclear fusion experiment, offers a pretty fast compression and extremely fast decompression. At last the performance evaluation of LZO application in HT-7 is given.     

核聚变实验装置HT-7U一维及二维辐射防护设计研究

主要介绍一维、二维中子输运程序ANISN,DOT3.5在核聚变实验装置HT-7U辐射屏蔽物理设计中的应用。计算和分析了该装置实验大厅内外中子注量/能谱、γ注量/能谱、中子剂量率、γ剂量率的空间分布,对屏蔽材料的选取及屏蔽层厚度进行了优化设计,为HT-7U装置的辐射屏蔽物理设计提供了建议性意见及理论依据。     

核聚变实验装置HT-7U及大厅活化分析

使用一维ＳＮ离散坐标法输运程序ＡＮＩＳＮ、活化计算程序ＡＦＤＫＲ并使用一维球几何模型对ＨＴ－７Ｕ装置米要部件及混凝土屏蔽墙的活化进行了计算和分析,给出了中子能谱、γ能谱、大厅内外剂量率空间分布及放射性水平的时间分布,对ＨＴ－７Ｕ装置的主要中子学参数及周围居民接收剂量水平给出了定量的分析。     

HT-7U超导托卡马克冷质部件支撑结构分析

介绍一种叠板式柔性支撑结构以及该结构用于HT 7U超导托卡马克装置中的特点 ,并介绍了有限元分析法在支撑系统分析中的应用 ,计算在各种载荷作用下支撑结构在的极限应力及应力分布状况 ,为结构设计的各项参数提供必要的理论依据     

HT-7托卡马克实验装置上基于PLC控制的中性束诊断电源系统

文章介绍HT-7托卡马克实验装置上的中性束诊断电源系统的组成、结构，以及基于S7-300PLC的逻辑控制系统。实验表明，该系统操作简单，性能稳定可靠。     

A Web-Based System for Remote Data Browsing in HT-7 Tokamak

HT-7 is the first superconducting tokamak device for fusion research in China.Many experiments have been performed on the HT-7 tokamak since 1994 with numerous satisfactory results achieved in the fusion research field. As more and better communication is required with other fusion research laboratories, remote access to experimental data is becoming increasingly important in order to raise the degree of openness of experiments and to expand research results. The web-based remote data browsing system enables authorized users in geographically different locations to view and search for experimental data without having to install any utility software at their terminals. The three-tier software architecture and thin client technology are used to operate the system effectively. This paper describes the structure of the system and the realization of its functions, focusing on three main points： the communication between the participating tiers, the data structure of the system and the visualization of the raw data on web pages.     

HT-7 诊断中性束电源控制系统设计

本文介绍了HT-7托卡马克实验装置上研制的基于脉宽调制（PWM）的诊断中性束电源系统的组成、结构和控制需求,以及控制系统的组成和控制功能等。经实际调试与多轮HT-7实验运行,验证了该套电源控制系统的稳定性与可靠性。     

Remote Control for the HT-7 Distributed Data Acquisition System

HT-7 is the first superconducting tokamak device for fusion research in China. Many experiments have been done in the machine since 1994, and lots of satisfactory results have been achieved in the fusion research field on HT-7 tokamak^[1]. With the development of fusion research, remote control of experiment becomes more and more important to improve experimental efficiency and expand research results. This paper will describe a RCS (Remote Control System),the combined model of Browser/Server and Client/Server, based on Internet of HT-7 distributed data acquisition system (HT7DAS). By means of RCS, authorized users all over the world can control and configure HT7DAS remotely. The RCS is designed to improve the flexibility, opening, reliability and efficiency of HT7DAS. In the paper, the whole process of design along with implementation of the system and some key items are discussed in detail. The System has been successfully operated during HT-7 experiment in 2002 campaign period.     

Plasma Shape and Current Control Simulation of HT-7U Tokamak

This paper describoes the discharge simulation of HT-7U tokamak plasma equilibrium and plasma current by solving MHD equations and surface average transport equations using an equilibrium evolution code. The simulated result shows the evolution of plasma parameter versus time .The simulated result can play an important role in the design of the plasma equilibrium and control system of a tokamak.     

HT-7超导托卡马克上γ辐射的初步研究

尝试了在HT-7托卡马克准稳态等离子体实验平台上，对伽马辐射能谱与通量进行测量与分析。实验中，测量得到了不同放电条件下的伽马辐射能谱和通量的时间演化过程，观测到了丰富的伽马辐射行为。针对欧姆加热、低杂波、离子回旋波、离子伯恩斯坦波、长脉冲等不同放电条件下的伽马辐射行为做了研究，结合其它相关诊断数据，给出了初步的分析结果。     

Using Poloidal Flux as Feedback Control Signal for Injected Power of LHCD in Long Pulse Discharge on HT-7 Tokamak

Long pulse discharge is one of the important goals of HT-7 superconducting tokamak experiments. For ITER （International Thermonuclear Experimental Reactor） or a tokamak reactor, carrying out a steady operation is one of the main techniques. For long pulse discharges on HT-7 the poloidal flux is used as the feedback signal to control the injected power of LHCD （Low Hybrid Current Drive） system. Experimental results are presented.     

Magnetic Sensorless Sensing of Plasma Position in the Superconducting Tokamak HT-7

Magnetic sensorless sensing experiments of the plasma horizontal position have been carried out in the superconducting tokamak HT-7. The horizontal position is calculated from the vertical field coil current and voltage without using signals of magnetic probes placed nearby a plasma. The calculations are focused on the ripple frequency component of the power supply.There is no drift problem with the time integration of magnetic probe signals. The error of the derived plasma position is lower than 2% of the plasma minor radius.     

Preliminary Engineering Design of Toroidal Field Magnet System for Superconducting Tokamak HT-7U

1.IntroductionHT-7Usuperconductingtokamakisanationalsci-entificresearchprojectofChina.ThislargefusionexperimentaldevicewillbebuiltinthelnstituteofPlasmaPhyslcsofChineseAcademyofSciences.ThemissionofHT-7Uistodevelopthescientificba-sisforacontinuouslyoperatingtokamakfusionreac-tor,achievingasteadystateandanextremelylongpuIseoperatlonwlthhigh-betadouble-null,aswellassingle-nullplasmasatfllllcllrrent.HT-7Uisafullsuperconductingtokamakdevlce.ltstoroidalfieldsystemisoneoftheimportantpartsofthe…