首页> 外文会议>Proceedings of International Conference on Structural Mechanics in Reactor Technology >MODAL ANALYSIS OF A NUCLEAR REACTOR WITH FLUID- STRUCTURE INTERACTION: ADDED MASS AND ADDED STIFFNESS EFFECTS
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MODAL ANALYSIS OF A NUCLEAR REACTOR WITH FLUID- STRUCTURE INTERACTION: ADDED MASS AND ADDED STIFFNESS EFFECTS

机译:具有流体-结构相互作用的核反应堆的模态分析:附加质量和附加刚度效应

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The present paper is related to the modal analysis of a naval propulsion ground prototype nuclear reactor with fluid-structure interaction modeling. Many numerical methods have been proposed over the past years to take fluid-structure phenomenon into account in various engineering domains, among which nuclear engineering in seismic analysis.The purpose of the present study is to apply general methods on a global approach of the nuclear reactor. A simplified design of the pressure vessel and the internal structure is presented; fluid-structure interaction is characterized by the following effects:? added mass effects are highlighted with the calculation of an added mass operator, obtained from a finite element discretisation of the coupled problem. The numerical model is developed within the Castem code using an axi-symmetric model of the industrial structure;? coupling effects between the external and internal structure via the confined inner fluid are also illustrated and numerically described with the added mass operator;? added stiffness effects are taken into account with an added stiffness matrix describing pre-stress effects due to a static pressure loading simulating the actual operating conditions of the reactor.The expected fluid-structure interaction effects on the nuclear pressure vessel and their numerical modeling leads to the definition of a global coupled model which can be used to perform a seismic analysis.
机译:本文涉及一种具有流固耦合模型的海军推进地面原型核反应堆的模态分析。过去几年中已经提出了许多数值方法来考虑流体工程现象在各个工程领域中的应用,其中包括在地震分析中的核工程。 本研究的目的是将一般方法应用于核反应堆的整体方法。提出了压力容器及其内部结构的简化设计。流体与结构的相互作用具有以下作用: ?通过从耦合问题的有限元离散化获得的附加质量算符,可以突出显示附加质量效应。数值模型是在Castem代码中使用工业结构的轴对称模型开发的。 ?还通过附加的质量算子对内部和内部结构之间通过有限内部流体的耦合作用进行了图示和数值描述; ?考虑了增加的刚度效应,并使用增加的刚度矩阵描述了由于模拟反应堆实际运行条件的静压载荷而产生的预应力效应。 预期的流体-结构相互作用对核压力容器的影响及其数值模型导致可以用来进行地震分析的整体耦合模型的定义。

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