首页> 外文会议>ASME(American Society of Mechanical Engineers) Pressure Vessels and Piping Conference 2007 >NUMERICAL AND EXPERIMENTAL INVESTIGATION OF NUCLEAR REACTOR CORE MODELED BY A POROUS MEDIA
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NUMERICAL AND EXPERIMENTAL INVESTIGATION OF NUCLEAR REACTOR CORE MODELED BY A POROUS MEDIA

机译:多孔介质模拟核反应堆核的数值和实验研究

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This study is about the safety of nuclear reactor core when it is subjected to seismic loading. In order to reduce the uncertainty margin of present day codes, we propose to develop a numerical code including the nonlinear behavior of the structure and the coupling with fluid flow. The challenge of this work is to find out a tractable model taking the structure complexity into account. In this paper we model the nuclear reactor core mechanical behavior including the dynamics of both fuel assemblies and fluid. Each rod bundle is considered as a deformable porous media, so the velocity field of the fluid and the displacement field of the structure are defined in the whole domain space. Fluid part and structure part are first of all considered separately, and secondly, the two parts are coupled. The motion equations of the structure are obtained by a Lagrangian formulation, and to allow fluid structure coupling, the motion equations of the fluid are obtained by an Arbitrary Lagragian Eulerian formulation. The finite elements method is applied to spatially discretize the equations. 2D numerical simulations are compared with experimental data.
机译:这项研究是关于核反应堆堆芯承受地震载荷时的安全性。为了减少当前代码的不确定性余量,我们建议开发一个数字代码,其中包括结构的非线性行为以及与流体流动的耦合。这项工作的挑战是找到一个易于处理的模型,同时考虑到结构的复杂性。在本文中,我们对核反应堆堆芯的力学行为进行建模,包括燃料组件和流体的动力学。每个杆束都被视为可变形的多孔介质,因此在整个域空间中定义了流体的速度场和结构的位移场。首先将流体部分和结构部分分开考虑,其次,将这两个部分耦合。通过拉格朗日公式获得结构的运动方程,并且为了允许流体结构耦合,通过任意拉格朗日欧拉公式获得流体的运动方程。应用有限元方法对方程进行空间离散。将2D数值模拟与实验数据进行比较。

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