Fast Reactor Cores: Seismic Excitation in the Vertical Direction — Numerical Methods

D. Broc, G. Artini, Jérome Cardolaccia, Laurent Martin
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引用次数: 1

Abstract

In the frame of the GEN IV Forum and of the ASTRID Project, a program is in progress in the CEA (France) 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 (or FA) and Neutronic Shields (or NS) immersed in the primary coolant (sodium), which circulates inside the Fuel Assemblies. The FA and the NS are slender structures, inserted in a grid plate, which may be considered as beams form a mechanical point of view. The dynamic behavior of this system has to be understood, for design and safety studies. This dynamic behavior of the core is strongly influenced by the sodium and by contacts between the beams at the pads level and at the top. The fluid leads to complex interactions between the structures in the whole core. The contacts between the beams limit the relative displacements. Two main movements have been considered so far: global horizontal movements under a seismic excitation, and opening of the core. Physical and numerical methods and tools have been developed to describe and simulate the dynamic behavior. These methods are integrated in CAST3M, general computer code developed at the CEA Saclay. The assemblies are modeled as beams. The impacts at the pads between the assemblies are taken into account by using a nonlinear model. The Fluid Structure Interaction is taken into account by using homogenization methods. This paper is devoted to the improvement of these methods to take into account the vertical component of a seismic excitation. The key points are: - the fluid structure coupling in the vertical direction, - the modification of the description of the impacts to take into account the vertical displacements of the assemblies, - the modification of the boundary condition at the foot of the assembly, in order to take into account the uplift with a nonlinear model.
快堆堆芯:垂直方向的地震激励。数值方法
在第四届论坛和ASTRID项目的框架内,CEA(法国)正在进行一个项目,用于开发和验证用于模拟快堆堆芯动态力学行为的数值工具,包括实验和数值部分。堆芯由燃料组件(FA)和浸入主冷却剂(钠)中的中子屏蔽(NS)组成,主冷却剂在燃料组件内部循环。FA和NS是细长的结构,插入在网格板中,从力学的角度来看,它们可以被认为是梁。为了设计和安全研究,必须了解该系统的动态行为。堆芯的这种动态行为强烈地受到钠的影响,也受到垫层和顶部梁之间接触的影响。流体导致整个岩心结构之间复杂的相互作用。梁之间的接触限制了相对位移。到目前为止,主要考虑了两种运动:地震激励下的全球水平运动和岩心的打开。已经开发了物理和数值方法和工具来描述和模拟其动态行为。这些方法集成在CAST3M中,这是CEA Saclay开发的通用计算机代码。组件被建模为梁。采用非线性模型考虑了组件间垫块的冲击。采用均质化方法考虑了流固相互作用。本文致力于改进这些方法,以考虑地震激励的垂直分量。关键是:-流体结构在垂直方向上的耦合,-修改对冲击的描述,以考虑组件的垂直位移,-修改组件底部的边界条件,以便用非线性模型考虑隆起。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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