Investigation of Centrifugal Pump Performance Under Two-Phase Flow Conditions-Reference-Cited by-同舟云学术

Investigation of Centrifugal Pump Performance Under Two-Phase Flow Conditions

Published:1995-03-01 Issue:1 Volume:117 Page:129-137
ISSN:0098-2202
Container-title:Journal of Fluids Engineering
language:en
Short-container-title:

Author:

Noghrehkar G. R.¹,Kawaji M.¹,Chan A. M. C.²,Nakamura H.³,Kukita Y.³

Affiliation:

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

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

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

Abstract

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.

Publisher

ASME International

Subject

Mechanical Engineering

Link

http://asmedigitalcollection.asme.org/fluidsengineering/article-pdf/117/1/129/5711687/129_1.pdf

Reference19 articles.

1. Chan, A. M. C., 1992, “Void Fraction Measurements in Large Diameter Pipes with Thick Metal Walls or Complex Internal Geometries,” ANS Proc. of National Heat Transfer Conf., Aug. 9–12, San Diego, pp. 236–244.

2. Chan A. M. C. , BarrecaS. L. and HartlenR. T., 1991, “An Experimental Study of Centrifugal Pump Performance Under Steam-Water Two-Phase Flow Conditions at Elevated Pressures,” Cavitation and Multiphase Flow Forum—1991, ASME FED-Vol. 109, pp. 111–117.

3. Chan, A. M. C., Kawaji, M., Noghrehkar, G. R., Nakamura, H. and Kukita, Y., 1994, “Two-Phase Head Degradation in a Full-Scale Nuclear Reactor Pump,” a paper to be submitted to the ASME Journal of Fluids Engineering.

4. Drew D. , ChengL. and LaheyR. T., 1979, “The Analysis of Virtual Mass Effects in Two-Phase Flow,” International Journal of Multiphase Flow, Vol. 5, pp. 233–242.

5. Furuya, O., 1984, “Development of an Analytic Model to Determine Pump Performance Under Two-Phase Flow Conditions,” EPRI NP-3519, Electric Power Research Institute, May.

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