Investigation of Centrifugal Pump Performance Under Two-Phase Flow Conditions

[+] Author and Article Information
G. R. Noghrehkar, M. Kawaji

Department of Chemical Engineering and Applied Chemistry, University of Toronto, Toronto, Ontario, Canada M5S 1A4

A. M. C. Chan

Ontario Hydro Technologies, Toronto, Ontario, Canada M8Z 5S4

H. Nakamura, Y. Kukita

Department of Safety Research, Japan Atomic Energy, Research Institute, Tokai-mura, Ibaraki 319-11, Japan

J. Fluids Eng 117(1), 129-137 (Mar 01, 1995) (9 pages) doi:10.1115/1.2816802 History: Received March 04, 1993; Revised April 27, 1994; Online December 04, 2007


A one-dimensional two-fluid model has been used to study the centrifugal pump head degradation phenomena and to analyze the gas-liquid interaction within the pump impeller under high pressure, steam-water two-phase flow conditions. The analytical model was used to predict the two-phase pump head data for the small-scale and full-scale nuclear reactor pumps and the predictions of the head degradation compared favorably with the test data for different suction void fractions. The physical mechanisms responsible for head degradation were also investigated.

Copyright © 1995 by The American Society of Mechanical Engineers
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