Analysis of flow-induced vibration of steam generator tubes subjected to cross flow

被引：19
|
作者：
Zhao, Wensheng [1 ,2 ]
Xue, Fei [2 ]
Shu, Guogang [3 ]
Liu, Meiqing [1 ]
Lin, Lei [2 ]
Wang, Zhaoxi [4 ]
Xiao, Zhihuai [1 ]
机构：
[1] Wuhan Univ, Sch Power & Mech Engn, Wuhan 430072, Hubei, Peoples R China
[2] Suzhou Nucl Power Res Inst, Suzhou 215004, Jiangsu, Peoples R China
[3] China Nucl Power Engn Co Ltd, Shenzhen 518031, Guangdong, Peoples R China
[4] CPI Nucl Power Inst, Beijing 100044, Peoples R China
来源：
NUCLEAR ENGINEERING AND DESIGN | 2014年 / 275卷
基金：
中国国家自然科学基金;
关键词：
FLUID-STRUCTURE-INTERACTION; IMMERSED BOUNDARY METHOD; HEAT-EXCHANGER; SIMULATION; BODIES; BODY; PWR;
D O I：
10.1016/j.nucengdes.2014.05.029
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
Flow-induced vibration of PWR steam generator tubes is one of the key problems to be considered in nuclear engineering. In this paper, the dynamics of tubes subjected to cross flow is investigated. A fully coupled model for fluid dynamics and structure is used to analyze this fluid-structure problem. The study begins with an analysis of a single tube subjected to cross flow, and the dynamics and flow patterns of the system are investigated. Time trace, power spectral density (PSD), phase-plane plot and Poincare map are used to characterize the motion of the tube. Then, the dynamical behaviours of two tubes with in-line and parallel configuration are studied, and the mutual influence of the two tubes is analyzed. The relationship between pitch-to-diameter ratio and non-dimensional displacement for two contiguous tubes is investigated. Finally, the interactions within a 3 x 3 tube bundle in cross flow, and the vibration responses of the 9 tubes are investigated. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码：375 / 381
页数：7
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