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首页> 外文会议>ASME(American Society of Mechanical Engineers) Pressure Vessels and Piping Conference 2006 vol.4 pt.A: Fluid-Structure Interaction >MODAL ANALYSIS OF A NUCLEAR REACTOR WITH FLUID-STRUCTURE INTERACTION: INFLUENCE OF FLUID COMPRESSIBILITY
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MODAL ANALYSIS OF A NUCLEAR REACTOR WITH FLUID-STRUCTURE INTERACTION: INFLUENCE OF FLUID COMPRESSIBILITY

机译：流体-结构相互作用的核反应堆的模态分析：流体可压缩性的影响

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摘要

The present paper deals with the modal analysis of a nuclear with fluid-structure interaction effects. In a previous study, added mass and added stiffness effects due to fluid-structure interaction were modeled and studied. A dynamic analysis was performed for a seismic excitation, i.e. in the low frequency range. The present study deals with high frequency analysis, i.e. taking into account compressibility effects in the fluid problem. Elasto-acoustic coupling phenomena are studied and described in the industrial case. The elasto-acoustic coupled problem is formulated using the displacement/pressure-displacement potential coupled formulation which yields symmetric matrices. A modal analysis is first performed on the fluid problem alone, with a calculation of acoustic eigenfrequencies and the corresponding modal masses. A modal analysis is then performed for the coupled fluid-structure problem in the case of an incompressible fluid and a compressible fluid at standard pressure and temperature conditions and for a compressible fluid at the operating pressure and temperature conditions. Elasto-coupling effects are then highlighted and discussed.
机译：本文涉及具有流体-结构相互作用的核的模态分析。在先前的研究中，对由于流体-结构相互作用而增加的质量和增加的刚度效应进行了建模和研究。对地震激励，即在低频范围内，进行了动态分析。本研究涉及高频分析，即考虑了流体问题中的可压缩性影响。弹声耦合现象在工业案例中得到了研究和描述。弹性-声耦合问题是使用位移/压力-位移电势耦合公式来表达的，它产生对称矩阵。首先单独对流体问题进行模态分析，并计算声学特征频率和相应的模态质量。然后，在标准压力和温度条件下为不可压缩流体和可压缩流体的情况下，对于工作压力和温度条件下为可压缩流体的耦合流体结构问题，进行模态分析。然后强调并讨论了弹性耦合效应。

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