首页> 外文会议>ASME Pressure Vessels and Piping conference >CONFINEMENT EFFECTS ON ADDED MASS OF CYLINDRICAL STRUCTURES IN A POTENTIAL FLOW
【24h】

CONFINEMENT EFFECTS ON ADDED MASS OF CYLINDRICAL STRUCTURES IN A POTENTIAL FLOW

机译:势流对圆柱结构附加质量的约束效应

获取原文

摘要

Efficient modelling and accurate knowledge of the mechanical behaviour of the reactor core are needed to estimate the effects of seismic excitation on a nuclear power plant. The fuel assemblies (in the reactor core) are subjected to an axial water flow which modifies their dynamical behaviour. Several fluid-structure models simulating the response of the core to a seismic load has been developed in recent years; most of them require high computational costs. The work which is presented here is a first step in order to simplify the fluid forces modelling, and thus to be able to catch the main features of the mechanical behaviour of reactor core with low computational costs. The main assumption made in this work is to consider the fluid flow as an inviscid potential flow. Thus, the flow can be described only using one scalar function (velocity potential) instead of a vector field and strongly simplifies the fluid mechanics equations, avoiding the necessity to solve Navier-Stokes equations. The pressure distribution around a cylinder is first solved in Fourier space for different values of the parameters (wavenumber, confinement size). The method is applied to a simple geometry (cylinder in an axial flow with a variable confinement) in order to test its effectiveness. The empirical model is then compared to simulations and reference works in literature. The configuration with large confinement has been solved, and results were in agreement with Slender Body Theory. The dependency on the confinement size strongly depends on the wavenumber, but in any case added mass increases as the confinement size decreases. Finally, future perspectives to extend the model to a group of cylinders and to improve the model are discussed (i.e. add viscosity to the model).
机译:需要有效的建模和对反应堆堆芯机械行为的准确了解,才能估算地震激发对核电站的影响。燃料组件(在反应堆堆芯中)承受轴向水流,从而改变了它们的动态性能。近年来,已经开发了几种模拟岩心对地震荷载响应的流体结构模型;他们中的大多数需要高昂的计算成本。这里介绍的工作是第一步,以简化流体力建模,从而能够以较低的计算成本掌握反应堆堆芯机械性能的主要特征。在这项工作中所做的主要假设是将流体流动视为无粘性的潜在流动。因此,仅可以使用一个标量函数(速度势)而不是矢量场来描述流,并且极大地简化了流体力学方程,从而避免了求解Navier-Stokes方程的必要。首先在傅立叶空间中求解圆柱体周围的压力分布,以获取不同的参数值(波数,约束尺寸)。该方法应用于简单的几何形状(轴向流量可变的圆柱体)以测试其有效性。然后将经验模型与模拟和参考文献进行比较。解决了大局限的配置,其结果与细长体理论相吻合。对限制尺寸的依赖性在很大程度上取决于波数,但是在任何情况下,随着限制尺寸的减小,附加质量也会增加。最后,讨论了将模型扩展到一组圆柱体并改进模型的未来观点(即为模型添加粘度)。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号