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Development and Mechanical Investigation of Central Solenoid Structure for COMPASS-U Tokamak

机译:Compass-U Tokamak中央螺线管结构的开发与机械调查

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COMPASS-U will be the successor of the existing COMPASS tokamak which is the main experimental facility of the Tokamak Department at the Institute of Plasma Physics of the Czech Academy of Sciences. COMPASS-U tokamak will be a flexible high magnetic field device with an advantage for scaling towards ITER (International Thermonuclear Experimental Reactor) and DEMO (DEMOnstration Power Station). The ITER and DEMO are foreseen to produce more energy than needed to power them. Based on the results obtained from the COMPASS-U it will be possible to learn more about the tokamak device, which will give more knowledge to construct larger of this type devices in the future. COMPASS-U requires new design of the whole structure of the device. One of the most challenging issues is the design of the Central Solenoid (CS) coils and its support structure. This task requires evaluation of many different case studies which include inter alia geometrical, technological and material properties verifications. In this contribution we present development and mechanical investigation of the CS structure. Based on a previous work, which showed the need of further optimization of the CS structure, additional development was done. In this work preload structure was added to the whole system. This allows to include preload as an additional load step. Preload was added to include compression of the CS coils in axial direction. The influence of the impregnation conditions on the CS behavior was checked. Several ways of impregnation application were studied and their influence on the CS structure was examined. Mechanical analysis using Finite Element Method (FEM) includes 2D axisymmetric model of the CS structure. Results for CS structure are presented for one particular loading scenario which is the premagnetization of the coils without plasma.
机译:Compass-U将成为现有指南针Tokamak的继任者,是捷克科学院等离子物理研究所的Tokamak部门的主要实验设施。 Compass-U Tokamak将是一个灵活的高磁场装置,具有用于缩放ITER(国际热核实验反应堆)和演示(演示发电站)的优势。预见的艾特和演示,产生比为它们供电的更多能量。基于从罗盘获得的结果 - 你可以了解有关Tokamak设备的更多信息,这将提供更多知识,以便将来构建更大的这种类型的设备。 Compass-U需要设备整个结构的新设计。最具挑战性的问题之一是设计中心螺线管(CS)线圈及其支撑结构的设计。该任务需要评估许多不同的案例研究,该研究包括尤其包括几何,技术和材料特性验证。在这一贡献中,我们提出了对CS结构的开发和机械调查。基于以前的工作,表明需要进一步优化CS结构,完成了额外的开发。在这项工作中,预加载结构被添加到整个系统中。这允许将预载荷作为额外的负载步骤。加入预加载以包括在轴向方向上的CS线圈压缩。检查浸渍条件对CS行为的影响。研究了几种浸渍申请的方法,研究了它们对Cs结构的影响。使用有限元方法(FEM)的机械分析包括CS结构的2D轴对称模型。对于一个特定的加载方案,提供了CS结构的结果,这是没有等离子体的线圈的预留。

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