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首页> 外文期刊>WSEAS Transactions on Applied and Theoretical Mechanics >FEM-DBEM procedure for crack analysis in baffle module of Wendelstein 7-X
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FEM-DBEM procedure for crack analysis in baffle module of Wendelstein 7-X

机译:Wendelstein 7-X挡板模块中裂纹分析的FEM-DBEM程序

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"Wendelstein 7-X" is the world's largest nuclear fusion experiment of "stellarator type" in which a hydrogen plasma is confined in a magnet field, generated with external superconducting coils, allowing the plasma to be heated up to fusion temperature. The water-cooled Plasma Facing Components (PFC) protect the Plasma Vessel (PV) against radiative and convective heat from the plasma. After the manufacturing process of the heat shields and baffles, several cracks have been found in the braze and in the cooling pipes. Due to heat loads occurring during each Operational Phase (OP), thermal-stresses are generated in the heat sinks, brazes and cooling pipes, that encourage cyclic crack-growth and, eventually, the water leak through the pipes. The aim of this study is to predict the operational limits of the baffles and heat shields under cyclic heat loads, by using a numerical model based on a FEM-DBEM approach, in order to provide an assessment on the risks of premature failure for segments assembled in the PV.
机译:“ Wendelstein 7-X”是世界上最大的“恒星型”核聚变实验,其中氢等离子体被限制在由外部超导线圈产生的磁场中,从而使等离子体被加热到聚变温度。水冷等离子表面组件(PFC)保护等离子容器(PV)免受来自等离子体的辐射热和对流热。在隔热罩和挡板的制造过程之后,在钎焊和冷却管中发现了一些裂缝。由于在每个操作阶段(OP)期间都会产生热负荷,因此在散热器,铜焊和冷却管中会产生热应力,从而导致周期性裂纹扩展,并最终导致水从管中泄漏。这项研究的目的是通过使用基于FEM-DBEM方法的数值模型来预测挡板和隔热罩在循环热负荷下的运行极限,以便对组装的节段过早失效的风险进行评估在PV中。

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