Analysis of flow-induced vibration of steam generator tubes subjected to cross flow
Creators
- 1. Suzhou Nuclear Power Research Institute, 1788 Xihuan St., Suzhou 215004, Jiangsu (China)
- 2. School of Power and Mechanical Engineering, Wuhan University, 8 Donghu St. S., Wuhan 430072, Hubei (China)
- 3. China Nuclear Power Engineering Co., Ltd., 1001 Shangbu Rd., Shenzhen 518031, Guangdong (China)
- 4. CPI Nuclear Power Institute, 18 Xizhimen St., Beijing 100044 (China)
Description
Highlights: • The dynamics of tubes subjected to cross flow is investigated. • A three-dimensional CFD model, coupled with a structural model is obtained. • The relationship between pitch and displacement for two tubes is analyzed. • The mutual influence of two contiguous tubes in cross flow is discussed. - Abstract: 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 Poincaré 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 × 3 tube bundle in cross flow, and the vibration responses of the 9 tubes are investigated
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2014.05.029Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2014.05.029;
- PII
- S0029-5493(14)00317-3;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 275
- Journal Page Range
- p. 375-381
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46100592
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- CONFIGURATION; FLUID MECHANICS; NUCLEAR ENGINEERING; PWR TYPE REACTORS; SPECTRAL DENSITY; STEAM GENERATORS; STRUCTURAL MODELS; THREE-DIMENSIONAL CALCULATIONS; TUBES
- Descriptors DEC
- BOILERS; ENGINEERING; ENRICHED URANIUM REACTORS; FUNCTIONS; MECHANICS; POWER REACTORS; REACTORS; SPECTRAL FUNCTIONS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.