等离子体破裂时HL-2M真空室的结构应力分析

利用ANSYS有限元程序分析计算了等离子体线性大破裂时HL-2M真空室上的感应电流及电磁力,并对真空室进行了结构应力分析。结果表明,真空室上主要产生环向感应电流和径向电磁力,且主要集中在真空室壳体的柱状段;在破裂产生的电磁力及其他机械载荷的作用下,真空室的结构设计能较好地满足强度和刚度要求。     

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结合EAST超导托卡马克的物理运行参数,计算给出了装置在等离子体突然破裂时ICRF加热天线上感应电流和电磁力解析式及其随时间变化的曲线图,根据曲线图讨论了电磁力的极限情况和对ICRF加热天线结构的影响。     

真空中激光束对金属表面的作用

一、引 言 在聚变装置真空室里由于等离子体与第一壁表面相互作用,使得器壁局部过热蒸发产生杂质气体,如H_2O,CO,CH_4,C等。这些气体在托卡马克装置放电期间将会导致等离子体能量损失,另外还涉及氢的再循环问题。研究这些现象可以了解托卡马克装置真空室第一壁上吸附气体层的组分及相对含量,以改善真空室的边界条件,进一步减少等离子体能量损失。     

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用ANSYS有限元软件计算了等离子体破裂时真空室上的涡流、电磁力和应力。有限元模型包含了基本的第一壁部件,以更加准确地研究真空室在瞬态电磁力作用下的结构强度。结果表明,高场侧靶板和内靶板带给真空室较大瞬时应力,但真空室的结构强度仍然满足强度要求。分析可校核和改进第一壁部件的结构设计。     

托卡马克等离子体电流猝灭特征行为分析

对托卡马克装置内壁产生巨大电磁力是等离子体破裂重要和直接的影响, 这会对装置的安全运行造成巨大威胁. 等离子体破裂期间电流猝灭率不仅与真空室内第一壁的负载设计有关, 并且与装置重大部件的设计也相关. 本文选用100%-40%区间统计研究等离子体破裂现象. 分析结果表明: 100%-40%区间统计下HL-2A上最小电流猝灭时间为0.7 ms, 对应的最小面积归一化电流淬灭时间为1.4 ms m-2. 瞬时最大电流猝灭率与平均电流猝灭率的比值大部分都大于1.     

HL-1工程联调中真空室的放电清洗

HL-1托卡马克装置工程联调时,内真空系统经200℃60小时烘烤和7万次脉冲放电清洗,接着作了124次低参数托卡马克放电。在环向磁场为15kG下获得了60kA的等离子体电流,等离子体存在时达85ms,本文总结分析了HL-1工程联调期间真空系统的烘烤、真空室的放电清洗技术及效果。     

EAST超导托卡马克装置真空室壁处理的研究

壁处理技术被广泛应用于托卡马克装置上,以降低装置本底杂质水平,改善器壁的再循环.自2008年起,EAST面向等离子体的第一壁采用全碳材料,由于特殊的石墨晶体多孔结构,具有高放气率以及对H₂O,H₂等杂质气体的高吸附性,从而使等离子体放电前期的装置真空室壁处理尤为关键.本文介绍了EAST装置真空室壁处理的实验系统,并研究了装置烘烤与不同工作气体及工作参数下的直流辉光放电清洗对杂质粒子的清除效果.实验结果表明:EAST装置真空室在经过长时问的前期壁处理后,显著地降低了真空室内壁的出气率与本底杂质浓度,这对随后进行的等离子体放电实验非常有必要.     

HL-2A装置破裂放电期间逃逸电子产生过程的实验观测

大破裂放电不仅会在第一壁和偏滤器靶板上产生巨大的热负载沉淀和强烈的电磁力，而且会产生强烈的逃逸电子。逃逸电子的产生给托卡马克的运行造成很大的危害。它的巨大能量可以使装置的某些部份被击穿。等离子体电流熄灭时，环电压有明显上升。因为，等离子体电流的快速下降能引起感应电压，其值能通过环电压线圈测到。     

HT-7托卡马克低杂波天线的涡流及电磁力分析

用有限元方法详细分析并计算了HT 7超导托卡马克等离子体实验装置上低杂波天线壁上的涡流分布、感应磁场位形和天线所受电磁力.针对难以求解的磁场耦合问题,采用了新的迭代算法.具体的分析方法和计算结果对于研究复杂电磁环境下金属板上的涡流及其所受电磁力的分布具有一定的借鉴价值.     

聚变装置中真空室上涡流的分析

本文研究了聚变装置真空室上的涡流问题,将真空室上的涡流看作面电流密度并定义一矢势的法向分量来描述它。详细地叙述了求解真空室上感应涡流的计算方法,对HTU托卡马克实验装置真空室上涡流的大小、分布形式及衰减情况进行了分析。     

Design and Studies of Disruption Prediction System on the HL-2A Tokamak

In the contemporary large tokamak, the disruptive termination of a discharge will reduce the lifetime of the first wall materials because of the intense heat flux at the energy quench and the intense runaway electrons during the current quench, and generate high electromagnetic forces on vacuum vessel components. The system of disruption warner must be established in the HL-2A tokamak. MHD real-time measuring and processing system has been designed and implemented. The system can be predicted the auras of dischage disruption in real-time, the energy quench and the current quench can be avoidanced.     

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破裂诱发的Halo电流会流进内真空室结构,对偏滤器支撑结构有较大的破坏。通过安装在偏滤器支撑结构上的罗柯夫斯基线圈对EAST中Halo电流进行了研究。通过分析不同位置的Halo电流信号,发现这些Halo电流具有环向不对称性,环向不对称因子为2.5, 的最大值是0.65。这些结果对EAST真空室电磁载荷分析有着重要的意义。     

Characteristic of Disruption on HL-2A Tokamak

The tokamak disruption is a dramatic event in which the plasma confinement is suddenly destroyed. Detailed experimental studies of disruptions have been made in many machines. During disruption, the plasma current and plasma thermal energy content collapse in an uncontrollable way, thereby applying mechanical forces and heat loads onto the vacuum vessel components. For that reason, the disruptions in a tokamak must be investigated and the physical processes leading to and occurring at the disruption need to be understood.     

Observations of High Densitly Disruption on HL-2A Tokamak

When the major disruption occurs, it can not only generate great heat loads on the first wall and divertor plates, but also leads to the large electromagnetic force because of the halo current. This large electromagnetic force is very dangerous to the invessel components of the divertor and vacuum vessel. Therefore, how to avoid the disruption is an important issue on tokamak operation. To control and mitigate the major disruptions, the mechanism and the characters of the disruption have to be well understood.     

EAST超导托卡马克冷屏结构与受力分析

EAST是一个全超导磁体系统的托卡马克实验装置,超导纵场和极向场磁体工作在4K温区下。在磁 体和其它发热部件之间布置有冷屏系统,以减少作用到所有低温冷质部件上的热载,将其保持在最低水平。该系 统包括真空室冷屏(内冷屏)和外真空杜瓦冷屏(外冷屏)两部分。在分析了冷屏低温运行时所受热应力以及等离 子体破裂时所受电磁载荷的基础上,运用大型有限元分析程序NASTRAN,对其不同载荷状况进行了数值计算,为其 结构设计与优化提供了理论依据。     

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In a fusion reactor, the blanket is one of the core components inside the vacuum vessel, it is directly facing the plasma, and the working environment is very harsh. In this paper, the induced eddy current and suffered electromagnetic force in the blanket of China Fusion Engineering Test Reactor (CFETR) has been calculated by the vector electromagnetic method of ANSYS in the major plasma disruption or the vertical displacement event. The modeling, the current source loading, boundary conditions setting, solving and calculated results are presented. This will provides the necessary reference data and method for future detailed design and optimization of the blanket components.     

等离子体破裂工况下的聚变堆包层组件电磁分析

在聚变堆中,包层是真空室内的核心部件之一,它直接面对等离子体,工作环境十分恶劣。利用ANSYS 软件的矢量电磁法,计算了中国聚变工程实验堆(CFETR)包层在离子体破裂和垂直位移事件中感应的涡电流和电磁力。介绍了建模、电流源加载、边界条件的设置、求解和计算结果。这为今后包层组件结构的详细设计和优化提供了必要的参考数据和方法。     

Optimization and performance of a high-speed plasma position digital control system

This paper addresses optimization of a high-speed digital feedback controller for a plasma position in Damavand tokamak. Damavand tokamak discharges have plasma currents up to 40 kA with discharge duration greater than 15 ms and toroidal magnetic fields up to 1.2 T. The plasma position is measured using saddle-loops and Rogowski coil and is controlled by electromagnetic forces generated by passing currents through control coils placed around the plasma. A desired control objective is maintaining the plasma in the center of vacuum vessel and to stabilize the plasma in the presence of disturbances in a time domain of the order of few milliseconds. In order to achieve maximum performance it is essential to optimize the control system. In this paper plasma position measurement and the details of implementing high-speed PID controllers based on a TMS320c25 digital signal processor along with the system optimization are presented.