Experimental study of two-phase pump performance using a full size nuclear reactor pump

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.