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Title: Vibration of a tube bundle in two-phase Freon cross-flow

Journal Article · · Journal of Pressure Vessel Technology
DOI:https://doi.org/10.1115/1.2842130· OSTI ID:131622
;  [1]; ;  [2]
  1. AECL Research, Chalk River, Ontario (Canada). Chalk River Labs.
  2. Univ. of Toronto, Ontario (Canada). Dept. of Mechanical Engineering

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.

Sponsoring Organization:
USDOE
OSTI ID:
131622
Journal Information:
Journal of Pressure Vessel Technology, Vol. 117, Issue 4; Other Information: DN: Paper presented at the Pressure Vessels and Piping Conference, Minneapolis, MN (US), June 19--23, 1994; PBD: Nov 1995
Country of Publication:
United States
Language:
English