Title of article
Experimental study of two-phase pump performance using a full size nuclear reactor pump
Author/Authors
Kawaji، M. نويسنده , , Chan، A.M.C. نويسنده , , Nakamura، H. نويسنده , , Kukita، Y. نويسنده ,
Issue Information
دوهفته نامه با شماره پیاپی سال 1999
Pages
-158
From page
159
To page
0
Abstract
The performance of a full-size nuclear reactor primary heat transport pump was investigated experimentally under high pressure, steam-water two-phase flow conditions. A new set of two-phase pump performance test data was obtained with local void fraction and mass flux measurements at the pump suction. The effects of suction temperature and initial flow conditions on the two-phase pump performance characteristics were described. © 1999 Elsevier Science S.A. All rights reserved.
Keywords
Transient data collection , Fatigue monitoring , Pressurized water reactors
Journal title
Nuclear Engineering and Design
Serial Year
1999
Journal title
Nuclear Engineering and Design
Record number
14274
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