Research on Fluid-Structure Interaction Dynamic Characteristics of Steam Generator Heat Exchanger Tubes

Article Preview

Abstract:

For heat exchanger tube of steam generator, the relation between heat exchanger tube and fluid is typical fluid-structure interaction problem. Flow induced vibration has been found so far to be responsible for fatigue damage and failure of steam generator tubes, which will result in large economic loss and radioactive pollution. So the steam generator tubes are the weakest link in the primary coolant loop. Based on the synthesis of all sorts of factors influencing the dynamic characteristics of steam generator heat transfer tubes, establishing the heat transfer tube model, research on the weakening effect of fluid hole on fluid, the natural frequencies of the heat transfer tubes are analyzed under different fluid holes and fluid hole distance by numerical simulation.

You might also be interested in these eBooks

Info:

Periodical:

Advanced Materials Research (Volumes 482-484)

Pages:

183-187

Citation:

Online since:

February 2012

Export:

Price:

Permissions CCC:

Permissions PLS:

Сopyright:

© 2012 Trans Tech Publications Ltd. All Rights Reserved

Share:

Citation:

[1] Report from Kansai Electric Power Company on Denting of Steam Generator Tubes Found During the Periodical Inspection of Takahama Power Station Unit-3, Kansai Electric Power Company, Nuclear and Industrial Safety Agency(NISA), Ministry of Economy, Trade and Industry(METI), January23,2004 NISA/METI.

DOI: 10.4324/9780203302156_chapter_seventeen

Google Scholar

[2] Jong Chull Jo,Myung Jo Jhung,Woong Sik Kim.Dynamic characteristics of steam generator U-tubes with defect[J].Nuclear Engineering and design.2005 (235): 821– 831.

DOI: 10.1016/j.nucengdes.2004.09.009

Google Scholar

[3] Shahab Khushnood, Zaffar M. Khan. A review of heat exchanger tube bundle vibration in two-phase cross-flow[J]. Nuclear Engineering and Design.2004 (230):233-251.

DOI: 10.1016/j.nucengdes.2003.11.024

Google Scholar

[4] Eisinger, F.L., Rao, M.S.M., Steininger, D.A, et al. Numerical simulation of cross flow induced fluidelastic vibration of tube arrays and comparison with experimental results. J. Press. Vessels Technol. 1995.117, 31–39.

DOI: 10.1115/1.2842087

Google Scholar

[5] Sigrist, J.F., Broc, D., 2007a. Homogenisation method for the modal analysis of a nuclear reactor with internal structures modelling and fluid–structure interaction coupling. Nuclear Engineering and Design 237, 431–440.

DOI: 10.1016/j.nucengdes.2006.08.006

Google Scholar

[6] Sigrist, J.F., Broc, D., 2008a. Homogenisation method for the modal analysis of tube bundle with fluid–structure interaction modelling. Finite Elements in Analysis and Design 44, 323–333.

DOI: 10.1016/j.finel.2007.11.017

Google Scholar

[7] Oakley, O.H., Constantinides, Y., Navarro, C., et al. Modeling vortex induced motions of spars in uniform and stratified flows. OMAE 2005-67238. In: Proceedings of OMAE 2005: 24th International Conference on Offshore Mechanics and Arctic Engineering, Halkidiki, Greece, June 12–16.

DOI: 10.1115/omae2005-67238

Google Scholar