• 主题
高级搜索  >
历史搜索 清空历史
首页> 外文会议>ASME(American Society of Mechanical Engineers) Pressure Vessels and Piping Conference 2006 vol.4 pt.A: Fluid-Structure Interaction >DYNAMIC ANALYSIS OF NUCLEAR STEAM GENERATOR, PROGRAM OVERVIEW
【24h】

DYNAMIC ANALYSIS OF NUCLEAR STEAM GENERATOR, PROGRAM OVERVIEW

机译：核蒸汽发生器的动态分析，程序概述

获取原文
获取原文并翻译 | 示例
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

The present paper exposes the main directions of a R&D program that DCN and CEA are currently developing to study the dynamic response of the steam generator of a naval nuclear propulsion reactor submitted to a shock. The structure is composed of tube bundles, immersed in a two phase flow fluid (steam and water). The dynamic solicitation contains high accelerations and high frequencies. It is thus necessary to establish which kind of physical phenomena can take place, and which kind of numerical tool can be used to study the dynamic behavior of the system. If the acceleration and the frequencies are very high, it will be necessary to consider highly non linear physical phenomena, with large deformation within short time duration. If the acceleration and (or) the frequencies are lower, simpler methods can be considered, assuming a linear behavior for the structure. In the latter case, as the frequencies still remain higher than the seismic ones, it might be necessary to take into account different kind of eigenmodes, as those depending on the fluid compressibility.As the fluid is a two phase medium, the use of homogenized fluid model has to be investigated. Since the tube bundle is a periodic structure, a homogenization technique can be used. Basic principles of the method are recalled as well as potential developments of existing methods. Influence of dissipative effects has also to be evaluated. The paper exposes the various problems that have to be addressed in order to produce a physical model of the structure that takes into account the various fluid-structure interaction effects for the shock analysis of the steam generator.
机译：本文揭示了DCN和CEA当前正在开发的R＆D程序的主要方向，以研究遭受冲击的海军核推进反应堆的蒸汽发生器的动态响应。该结构由浸在两相流流体（蒸汽和水）中的管束组成。动态请求包含高加速度和高频率。因此，有必要确定可以发生哪种物理现象，以及可以使用哪种数值工具来研究系统的动态行为。如果加速度和频率很高，则有必要考虑高度非线性的物理现象，并在短时间内产生较大的变形。如果加速度和（或）频率较低，则假定结构具有线性行为，可以考虑采用更简单的方法。在后一种情况下，由于频率仍然高于地震频率，可能有必要考虑不同种类的本征模，这取决于流体的可压缩性。由于流体是两相介质，因此使用均质流体模型必须研究。由于管束是周期性结构，因此可以使用均质化技术。回顾了该方法的基本原理以及现有方法的潜在发展。耗散效应的影响也必须进行评估。本文揭示了为产生结构的物理模型而必须解决的各种问题，该模型考虑了蒸汽发生器冲击分析中各种流体-结构相互作用的影响。

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