0
RESEARCH PAPERS

Vibration in Nuclear Heat Exchangers Due to Liquid and Two-Phase Flow

[+] Author and Article Information
W. J. Heilker

Analytical Engineering, NCE, Combustion Engineering, Inc., Chattanooga, Tenn. 37402

R. Q. Vincent

Component Engineering Test Laboratory, Combustion Engineering, Inc., Chattanooga, Tenn. 37402

J. Eng. Power 103(2), 358-366 (Apr 01, 1981) (9 pages) doi:10.1115/1.3230729 History: Received March 06, 1980; Online November 09, 2009

Abstract

In order to optimize a steam generator tube bundle support system, it is necessary to understand the differences in vibration behavior of tube arrays subjected to a two-phase flow regime as compared to a single phase flow regime. The relationships discussed in this paper are based on findings derived from a comprehensive vibration testing program which included both water and simulated two-phase (air-water) flow regimes. Tube bundles of various configurations and spacings were tested in crossflow using 3/4 in. (1.9 cm) and 7/8 in. (2.2 cm) o.d. tubes with 36 in. (91 cm) span lengths and as many as 40 tubes per array. Sufficient test loop capacity was provided to drive most test array configurations up to and beyond fluid-elastic instability. Parameters obtained included displacement, effective force coefficients, damping coefficients, Strouhal numbers, and instability constants for various tube array configurations in both liquid and simulated two-phase flow mediums.

Copyright © 1981 by ASME
Your Session has timed out. Please sign back in to continue.

References

Figures

Tables

Errata

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In