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FLUID STRUCTURE INTERACTION FOR TUBES BUNDLES: PRESENTATION OF A LINEAR EQUIVALENT MODEL

机译:管束的流体结构相互作用:线性等价模型的表示

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ASTRID is a project for an industrial prototype of a 600 MWe sodium cooled Fast Reactor, led by CEA. An important program is in progress for the development and the validation of numerical tools for the simulation of the dynamic mechanical behavior of the Fast Reactor cores, with both experimental and numerical parts. The cores are constituted of Fuel Assemblies (of FA) and Neutronic Shields (or NS) immersed in the primary coolant (sodium), which circulates inside the Fluid Assemblies. The FA and the NS are slender structures, which may be considered as beams, form a mechanical point of view. The analysis of the dynamic behavior of tubes bundles immersed in a dense fluid is a major challenge in the nuclear industry (reactor cores, steam generators). In some cases, the excitation is given by the fluid flow, with a complex behavior which may lead to instabilities. The paper only considers the case of an external excitation (earthquake or shock). The fluid leads to two main effects: "inertial effects" with lower vibration frequencies and "dissipative effects" with a higher damping. In the general case the fluid has to be described by the Navier-Stokes equations. It is possible to use the Euler linear equations in the case of vibrations of the tubes in a globally stagnant fluid. In all cases the modeling of the system could lead to huge numerical problems if each tube is described explicitly. Homogenization technics allow to limit the size of the problem. Homogenization methods taking into account the Euler equations for the fluid have been developed, and widely used for analyses of the dynamic behavior of reactor cores. Only the inertial effects are theoretically described but the dissipative effects may be roughly taken into account by using a Rayleigh damping. The paper presents an improvement of the method, allowing a better description of the dissipative effects, with a more general form of the expression of the forces exchanged between the fluid and the tubes. The theoretical basis of the numerical model are presented, as well as illustrations of the interest of the method: a better physical description is obtained for the dynamic behavior of the tubes bundle, particularly in the case of interactions with free fluid, without tubes.
机译:ASTRID是由CEA领导的600 MWe钠冷却快堆的工业原型项目。正在开发一个重要程序,以开发和验证用于仿真快堆堆芯动态力学行为的数值工具,包括实验部分和数值部分。核心由浸入在流体总成内部循环的主冷却剂(钠)中的燃料总成(FA)和中子屏蔽(或NS)组成。 FA和NS是细长的结构,可以看作是梁,形成了机械的观点。对浸没在稠密流体中的管束的动态行为进行分析是核工业(反应堆堆芯,蒸汽发生器)的一项重大挑战。在某些情况下,激发是由流体流动引起的,其行为复杂,可能会导致不稳定。本文仅考虑外部激励(地震或冲击)的情况。流体导致两个主要作用:振动频率较低的“惯性作用”和阻尼较高的“耗散作用”。在一般情况下,必须通过Navier-Stokes方程描述流体。如果管在整体停滞的流体中发生振动,则可以使用Euler线性方程。在所有情况下,如果每个管都进行了明确描述,则系统建模可能会导致巨大的数值问题。均质化技术可以限制问题的大小。已经开发了考虑流体的欧拉方程的均质化方法,并被广泛用于分析反应堆堆芯的动态行为。从理论上仅描述了惯性效应,但是通过使用瑞利阻尼可以大致考虑耗散效应。本文提出了一种方法的改进,可以更好地描述耗散效果,并以更一般的形式来表达流体与管之间交换的力。提出了数值模型的理论基础,并举例说明了该方法的重要性:对于管束的动态行为,尤其是在与自由流体相互作用而无管的情况下,可获得更好的物理描述。

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