Vibration of a Tube Bundle in Two-Phase Freon Cross-Flow

[+] Author and Article Information
M. J. Pettigrew, C. E. Taylor

AECL Research, Chalk River Laboratories, Chalk River, Ontario, K0J 1J0 Canada

J. H. Jong, I. G. Currie

Department of Mechanical Engineering, University of Toronto, Toronto, Ontario, M5S 1A4 Canada

J. Pressure Vessel Technol 117(4), 321-329 (Nov 01, 1995) (9 pages) doi:10.1115/1.2842130 History: Received March 31, 1994; Revised February 09, 1995; Online February 11, 2008


Two-phase cross-flow exists in many shell-and-tube heat exchangers. The U-bend region of nuclear steam generators is a prime example. Testing in two-phase flow simulated by air-water provides useful results inexpensively. However, two-phase flow parameters, in particular surface tension and density ratio, are considerably different in air-water than in steam-water. A reasonable compromise is testing in liquid-vapor Freon, which is much closer to steam-water while much simpler experimentally. This paper presents the first results of a series of tests on the vibration behavior of tube bundles subjected to two-phase Freon cross-flow. A rotated triangular tube bundle of tube-to-diameter ratio of 1.5 was tested over a broad range of void fractions and mass fluxes. Fluidelastic instability, random turbulence excitation, and damping were investigated. Well-defined fluidelastic instabilities were observed in continuous two-phase flow regimes. However, intermittent two-phase flow regimes had a dramatic effect on fluidelastic instability. Generally, random turbulence excitation forces are much lower in Freon than in air-water. Damping is very dependent on void fraction, as expected.

Copyright © 1995 by The American Society of Mechanical Engineers
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