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Dynamic Analysis of ITER Tokamak Using Simplified Model for Support Structure

机译:基于简化结构的ITER托卡马克动力学分析

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摘要

The simplified analytical model of a support structure composed of complicated structures such as multiple flexible plates was proposed for dynamic analysis of the ITER major components of the VV and TF coil. The support structure composed of flexible plates and connection bolts was modeled as a spring model composed of only two spring elements simulating the in-plane and out-of-plane stiffness of the support structure with flexible plates including the effect of connection bolts. The stiffness of both these spring models for the VV and TF coil agree well with that of shell models simulating actual structures such as flexible plates and connection bolts. It is therefore found that the spring model with only these two parameters, in-plane and out-of-plane stiffness, simplifies the complicated support structure with flexible plates for the dynamic analysis of the VV and TF coil. Using the proposed spring model, the dynamic analysis of the VV and TF coil for the ITER were performed to estimate the integrity under the design earthquake at Rokkasho, a candidate for an ITER site. As a result, it is found that the maximum relative displacement of 8.6 mm between the VV and TF coil is much less than the current design gap of 100 mm, so that the integrity of the major components (VV and TF coil) of the ITER tokamak device is ensured for the expected earthquake event.
机译:提出了由复杂结构(如多个柔性板)组成的支撑结构的简化分析模型,用于对VV和TF线圈的ITER主要组件进行动态分析。由柔性板和连接螺栓组成的支撑结构被建模为仅由两个弹簧元件组成的弹簧模型,该弹簧模型模拟了具有连接板作用的柔性板的支撑结构的平面内和平面外刚度。 VV和TF线圈的这两个弹簧模型的刚度与模拟实际结构(例如柔性板和连接螺栓)的壳模型的刚度非常吻合。因此发现,仅具有这两个参数的弹簧模型(平面内和平面外刚度)简化了用于VV和TF线圈动态分析的具有柔性板的复杂支撑结构。使用所提出的弹簧模型,对ITER的VV和TF线圈进行了动力分析,以估算Rokkasho(ITER选址的候选地点)在设计地震下的完整性。结果发现,VV和TF线圈之间的最大相对位移8.6 mm远小于当前的100 mm设计间隙,因此ITER的主要组件(VV和TF线圈)的完整性确保将托卡马克装置用于预期的地震事件。

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