DⅢ—D托卡马克H模式等离子体中的快波电流驱动

在DⅢ-D托卡马克的H模式和VH模式等离子体中首次测量了由快阿尔芬波驱动的电流。对极向通量演变的分析表明,快波电流驱动分布是中心峰化的,但有时比理论预计的宽。尽管对于很少发生ELMs的等离子体,测得的电流驱动效率与理论一致,但是对于有快ELMs的等离子体,电流驱动效率为一个数量级,则太低了。功率调制实验表明,电流驱动随ELM频率的增大而降低是由于中心吸收的快速功率的份额降低引起的。当等离子体分界面外侧的电子密度上升到大于ELMs引起的快波截止密度时,吸收和电流驱动是最弱的,从而可能允许边缘损失机制耗散快波功率,因为对于脱离等离子体的快波,截止密度是一个障碍。     

在低混杂波频率范围大功率微波辅助下实现HT-7托卡马克低环电压启动

在HT－7托卡马克放电实验中，使用N∥谱实时可调，频率在等离子体低混杂波频率范围，功率达150－200kW的大功率微波，辅助托卡马克装置的加热场进行了等离子体放电。在低环电压下实现了托卡马克的成功启动。使用这种方法使HT－7装置的启动环电压由通常的20V左右下降到5V以下。这相当于实现了放电启动的最大加热场副边场强由2.5-3V/m降低到0.6V/m左右。实验还观察到，在这种微波辅助低环电压启动条件下，气体电离过程和等离子体电流建立过程中的伏秒数的消耗，初始等离子体的辐射等一系列不同于单纯欧姆放电过程的物理现象。     

Design criteria and current status of LHCD system on SST1 machine

The lower hybrid current drive (LHCD) system for superconducting steady state tokamak-1 (SST-1) machine is in advanced stage of integration and commissioning. The system is designed to launch 1 MW of RF power at a frequency of 3.7 GHz to sustain 220 kA of plasma current non-inductively for 1000 s. The system employs a conventional grill antenna (having 2 × 32 waveguides), vacuum and air transmission lines and high power source system. A new design for vacuum transmission line, which enables better vacuum and RF compatibility has been successfully executed and tested. The transition from the narrow waveguide to WR284 waveguide system is achieved through a simple design, having stacks of copper plates with the waveguides milled in them, referred as transforming module and is successfully tested for mechanical, vacuum and RF performance. Many of the critical components have been successfully fabricated and tested as per the designs. The components and sub-systems are made ready and the integration is in progress. All the components are actively cooled and are compatible with 1000 s operation.The performance tests and current status of various sub assemblies and partially integrated LHCD system is discussed in detail in this paper.     

低杂波电流驱动下HT-7超导托卡马克等离子体硬X射线辐射研究

用７个ＮａＩ（Ｔｌ）闪烁探测器组成的阵列观测能量范围在２０－５００ｋｅＶ,来自ＨＴ－７托卡马克等离子体的硬Ｘ射线轫致辐射。实验结果显示,硬Ｘ射线的径向辐射强度分布与低杂波的功率谱和等离子体的密度及磁志强度等放电参数密切相关。通过测量不同放电参数下硬Ｘ射线的径向强度分布,研究低杂波在等离子体中传播和吸收机制。     

Robust control design for the plasma horizontal position control on J-TEXT Tokamak

It is extremely important for tokamak to control the plasma position during routine discharge. However, the model of plasma in tokamak usually contains much of the uncertainty, such as structured uncertainties and unmodeled dynamics. Compared with the traditional PID control approach, robust control theory is more suitable to handle this problem. In the paper, we propose a H_∞ robust control scheme to control the horizontal position of plasma during the flat-top phase of discharge on Joint Texas Experimental Tokamak (J-TEXT) tokamak. First, the model of our plant for plasma horizontal position control is obtained from the position equilibrium equations. Then the H_∞ robust control framework is used to synthesize the controller. Based on this, an H_∞ controller is designed to minimize the regulation/tracking error. Finally, a comparison study is conducted between the optimized H_∞ robust controller and the traditional PID controller in simulations. The simulation results of the H_∞ robust controller show a significant improvement of the performance with respect to those obtained with traditional PID controller, which is currently used on our machine.     

A poloidal field control system based on VxWorks in HT-7 Tokamak

The PF (Poloidal Field) control system is one of the most important control systems in HT-7 Tokamak.Most of parameters such as plasma current, plasma horizontal position and plasma vertical position will be monitored.For the purpose of long-pulse discharge and the more precise control to plasma, the real-time operation system VxWorks is applied, instead of the behindhand and unbefitting DOS operation system. This paper describes the development process of HT-7 PF control system based on VxWorks on Intel X86 platforms. The method of using hardware cards in VxWorks, and the network communication with other operation systems are discussed especially. Results of the comparison between VxWorks and DOS operation systems are given too.     

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.     

Neutron-imaging technique for monitoring high-temperature plasma dynamics

A preliminary design for the adaptation of a pinhole experiment (PINEX) technique to the monitoring of the dynamics of high-temperature plasmas is described. Specifically, this imaging technique uses a thick aperture, an efficient radiation converter, and highly intensified television cameras to provide real-time viewing of radiation sources, such as the neutron emissions from d-d and d-t fusion reactions in controlled thermonuclear research devices. The neutron emission strengths,R 510¹⁵ n/sec, recently achieved at the Tokamak Fusion Test Reactor (TFTR) and the Joint European Torus (JET) should be sufficient for 3 to 6-cm spatial resolution and 10 to 100-msec time resolution using such a system. Such information should be useful for on-line optimization of the plasma and for quantitative evaluation of its performance.     

碘化汞探测器及其对HL-1M装置中X射线辐射测量

本文叙述新研制的以高纯度碘化汞晶体为基片的低噪声、高探测效率、高计数率、较高能量分辨率，常温状态下运行的ＨｇＩ２半导体探测器的特点，以及特制的电荷灵敏前放和主放大器组成的探测系统对ＨＬ－１Ｍ托卡马克在欧姆加热、低杂波电流驱动、外加径向电场以及激光吹气掺杂等实验条件下，来自等离子体心部的硬Ｘ射线辐射进行测量，得到辐射强度和能谱随时间的变化等实验结果，并对实验结果作了初步的解释。     

HL-2A托卡马克装置的工程和实验概况

中国环流器二号A装置(HL-2A)是核工业西南物理研究院2002年投入实验运行的托卡马克,它是我国第1个具有偏滤器、等离子体截面具有一定垂直拉长的托卡马克.HL-2A的磁体使用铜导体,具有良好的灵活性和等离子体的可近性,其极向场线圈全部位于环向场线圈之内,位于真空室内的偏滤器的成形线圈可建立双零和单零的偏滤器位形.HL-2A已发展了30多套先进的等离子体诊断系统和总功率4 MW的辅助加热系统,加料技术得到持续发展.随着上述系统的建设和放电综合控制技术的提高,HL-2A装置已获得了高约束模式,这为开展先进托卡马克(AT)物理实验,ITER和聚变堆的科学、技术和工程问题等的研究奠定了基础.HL-2A也成为国际上最活跃的中型托卡马克,为国际托卡马克物理活动(ITPA)作出了积极贡献.     

Tokamak research at University of São Paulo

The main results obtained in the small tokamak TBR-1 of University of São Paulo (USP) are reviewed. The main effort has been concentrated on the characterization and external control of MHD activity, plasma edge phenomena and diagnostic development. The design of a small-aspectratio tokamak, TBR-E, and the research program to be carried out in TCA, to be transferred from Lausanne to São Paulo, are also briefly described.