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FAST REACTOR CORES SEISMIC EXCITATION IN THE VERTICAL DIRECTION - NUMERICAL METHODS

机译:快速反应器在垂直方向上抑制了地震的激发-数值方法。

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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: 1. the fluid structure coupling in the vertical direction, 2. the modification of the description of the impacts to take into account the vertical displacements of the assemblies, 3. the modification of the boundary condition at the foot of the assembly, in order to take into account the uplift with a nonlinear model.
机译:在第四纪论坛和ASTRID项目的框架内,正在CEA(法国)进行一项计划,以开发和验证用于模拟快堆堆芯动态力学行为的数值工具,同时实验和数值部分。铁心由浸入在冷却剂内部循环的主冷却剂(钠)中的燃料组件(或FA)和中子屏蔽(或NS)组成。 FA和NS是细长的结构,插入网格板中,可以将其视为形成机械角度的梁。为了设计和安全性研究,必须了解该系统的动态行为。芯的这种动态行为在很大程度上受钠的影响,也受焊盘水平和顶部的梁之间的接触的强烈影响。流体导致整个核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,已经考虑了两个主要运动:地震激励下的整体水平运动和岩心的张开。已经开发出物理和数值方法和工具来描述和模拟动态行为。这些方法集成在CEA Saclay开发的通用计算机代码CAST3M中。组件被建模为梁。通过使用非线性模型,考虑了组件之间的焊盘上的冲击。通过使用均质化方法考虑了流体结构的相互作用。本文致力于改进这些方法,以考虑到地震激励的垂直分量。关键点是:1.在垂直方向上耦合的流体结构; 2.考虑到组件的垂直位移,修改了影响描述; 3.修改了脚底部的边界条件。装配,以考虑到带有非线性模型的隆起。

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