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.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
