Short-term power sources for tokamaks and other physical experiments

The Compass-D tokamak is being planned to move from UKAEA Culham (England) be and reinstalled in IPP Prague (Czech Republic). An overview of Compass-D energetics is described in short. The new power sources have to be designed. Alternative solutions of power sources have been investigated. Ignitrons and mechanical breakers can be replaced by modern high-power semiconductors. With respect to the need of accumulated energy, new technologies of energy storage - supercapacitors and high-speed flywheels, not applied up to now in similar fusion projects, are characterized in comparison with traditional ones - capacitors and big motor-flywheel generators. It is shown that these technologies enhance possibilities in arrangement of power supplies for tokamaks as well as for other high-power demanding experiments with pulse length from fraction to tens of seconds.     

紧凑 Tokamak(球形环)聚变堆第一壁及中心导体柱上中子负荷及核热计算与分析

采用通用蒙特卡罗粒子输运程序ＭＣＮＰ／３８计算低环径比Ｔｏｋａｍａｋ（紧凑环或球形环）聚变堆第一壁及中心导体上的中子壁负荷分布和核热沉积分布，并与常规Ｔｏｋａｍａｋ堆第一壁上中子壁负荷分布和核热沉积分布进行比较、分析。结果表明，在中子壁负荷归一化为１ＭＷ／ｍ２时，与常规Ｔｏｋａｍａｋ相比，在低环径比Ｔｏｋａｍａｋ堆第一壁及中心柱表面上中子壁负荷分布峰值并不比常规Ｔｏｋａｍａｋ堆第一壁上的峰值高，而且低于低环径比Ｔｏｋａｍａｋ堆整个第一壁上的平均值，而中心柱上的核热沉积峰值稍高于常规Ｔｏｋａｍａｋ堆第一壁上的核热沉积峰值，但对较高中子壁负荷情况，中心导体柱上的核热沉积和辐照损伤仍可能是比较严重和值得特别研究的问题。     

基于CAMAC总线的交替式数据采集及实时监控系统研究

进行了一种称为交替式数据采集及实时监控系统的研究。该系统不仅能实现以较高频率进行任意时间的数据采集，还能在放电过程中以图形方式实时显示等离子体的各种参数供实验人员在线分析及控制。     

EAST技术诊断系统监控子系统分析和设计

EAST是为科学研究建造的全超导核聚变实验装置。根据EAST的实验特点和性能要求,技术诊断系统数据监控子系统采用管理层、控制层和现场设备层3 层网络结构完成对装置的监控,通过采集卡和以太网实现信号采集及数据的传送。在EAST工程调试实验和两轮放电实验中,该数据监控系统成功实现了对EAST装置的运行状态和故障诊断的实时监控,表明该系统具有性能稳定、可靠等特点。     

Tokamak等离子体图像诊断系统的研制

针对Tokamak等离子体放电实验中需要对等离子体进行直观诊断的需求,根据实验的特点,研制了等离子体图像诊断系统,该系统以Matrox公司的Meteor Ⅱ/Digital采集卡和UNIQ VISION公司的UC610相机等为硬件核心,采用了Visual C++多线程技术进行实时图像采集,采用了Bayer变换和Gamma校正等数字图像处理技术将采集到的Bayer格式的灰度数字图像转换为彩色数字图像;该图像诊断系统实现了Tokamak放电实验中等离子体图像实时采集、处理和诊断等功能,充分满足了等离子体放电实验诊断的要求。     

基于LabVIEW的EAST纵场电流实时测控系统

EAST纵场超导磁体是用来产生纵向磁场约束等离子体使其稳态运行的重要装置,其中的电流控制及失超检测对于保证托克马卡装置正常运行是非常重要的;通过对传统的纵场电流测控系统进行分析,提出了使用LabVIEW及相应硬件实现托克马卡纵场电流测量与控制,并详细介绍了系统的硬件结构、软件设计和实现;通过仿真和实际使用,验证了该系统稳定可靠,大大减小了系统长时间运行过程中引起的纵场电流漂移,在可维护性、集成度、人机界面和易操作性上都有了较大的提高。     

The use of an electrothermal plasma gun to simulate the extremely high heat flux conditions of a tokamak disruption

Disruption damage conditions for future large tokamaks like ITER are nearly impossible to simulate on current tokamaks. The electrothermal plasma source SIRENS has been designed, constructed, and operated to produce high density (> 10²⁵/m³), low temperature (1–3 eV) plasma formed by the ablation of the insulator with currents of up to 100 kA (100 s pulse length) and energies up to 15 kJ. The source heat fluence (variable from 0.2 to 7 MJ/m²) is adequate for simulation of the thermal quench phase of plasma disruption in future fusion tokamaks. Different materials have been exposed to the high heat flux in SIRENS, where comparative erosion behavior was obtained. Vapor shield phenomena has been characterized for different materials, and the energy transmission factor through the shielding layer is obtained. The device is also equipped with a magnet capable of producing a parallel magnetic field (up to 16 T) over a 8 msec pulse length. The magnetic field is produced to decrease the turbulent energy transport through the vapor shield, which provides further reduction of surface erosion (magnetic vapor shield effect).     

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。     

EGYPTOR Tokamak: Modification of the Original Design Using Permanent Compensation Coils and First Results of the Breakdown Discharge

The EGYPTOR tokamak is a small device of rectangular cross section 25 × 20 cm. Modification of the original design is done by adding compensation coils connected to the Toroidal field (TF) coils and Ohmic heating (OH) coils. These compensation coils are used to compensate most of the stray magnetic field components that prevent a breakdown discharge. First results of the breakdown discharge are reported. A gated ICCD camera is used to obtain side view images of the visible light emitted from the plasma.     

CT-6B托卡马克的交流运行实验研究

在CT—6B托卡马克上首次实现了多周期交流运行，对多个周期中等离子体进行比较发现，尽管在每个周期的两个半周中等离子体与壁的相互作用有所不同，但等离子体中的杂质积累并未受到严重影响。通过内磁探针测量了等离子体电流密度的分布，发现等离子体电流首先从弱场区开始反相，电流反相过零时同时存在正负局部等离子体电流，此时的磁面结构有效地约束了粒子。