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Verification of numerical models for seismic fluid-structure interaction analysis of internal components in liquid-filled advanced reactors

机译:液体填充先进反应器内部部件地震流体结构相互作用分析的数值模型的验证

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Earthquake shaking of a liquid-filled advanced reactor induces fluid-structure interaction (FSI) between the reactor vessel (tank), its internal components, and the contained liquid. Seismic design, qualification, and risk assessment of such reactors must consider fluid-structure responses, their geometries and support conditions, and three-directional seismic inputs, all of which require numerical simulations. Numerical models used for analysis of safety-related nuclear equipment must be verified and validated. This paper verifies numerical models of submerged components using analytical solutions. Seismic FSI analysis of the numerical models is performed using the Arbitrary Lagrangian-Eulerian (ALE) and Incompressible Computational Fluid Dynamics (ICFD) solvers in LS-DYNA. Prior analytical solutions are reworked in this paper, and calculation errors are identified and corrected. The solutions address frequencies of two concentric cylindrical pipes filled with liquid: the inner pipe is a submerged component, and the outer pipe contains the liquid. A unitless frequency coefficient is defined and presented for pipes of different materials, filled with different liquids, and with a range of dimensions for application to advanced reactors. The numerical models are verified here by comparing the lateral frequencies of submerged components with those calculated using the corrected analytical solutions. Recommendations for verification of numerical models of internal components in advanced reactors for seismic FSI analysis are provided. Although the unitless frequency coefficients and verification procedures are developed for application to advanced nuclear reactors, they are broadly applicable to FSI analysis of submerged components in liquid-filled vessels such as storage tanks, boilers, and steam generators.
机译:液体填充的先进反应器的地震振动诱导反应器容器(罐),其内部组分和含有液体之间的流体结构相互作用(FSI)。这种反应堆的地震设计,资格和风险评估必须考虑流体结构响应,其几何和支持条件,以及三个方向地震投入,所有这些都需要数值模拟。必须核实和验证用于分析安全相关核设备的数值模型。本文使用分析解决方案验证淹没组件的数值模型。使用LS-DYNA中的任意拉格朗日 - 欧拉(ALE)和不可压缩的计算流体动力学(ICFD)溶剂进行数值模型的地震FSI分析。在本文中重新改造了现有的分析解决方案,并识别并校正计算误差。解决方案地址填充有液体的两个同心圆柱管的频率:内管是浸没的部件,外管含有液体。无单位频率系数被定义和呈现出不同材料的管道,填充有不同的液体,并且具有一系列尺寸用于应用于先进的反应器。通过使用校正的分析解决方案计算的那些,通过比较淹没组件的横向频率来验证数值模型。提供了用于验证地震FSI分析的先进反应器中内部部件数值模型的建议。尽管未经无能的频率系数和验证程​​序用于应用于先进的核反应堆,但它们广泛适用于液体填充容器中浸没组件的FSI分析,如储罐,锅炉和蒸汽发生器。

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