Abstract
In relation to void fraction and flow regime transition predictions of cross-flow in horizontal tube bundle of steam generator, a phenomenological drift-flux correlation and new flow regime transition criteria have been developed to meet the demand on the study of two-phase flow gas and liquid velocities, two-phase pressure drop, heat transfer, flow patterns and flow induced vibrations in the shell side of the U-bend section of the steam generator.
Degree Type
Thesis
Degree Name
Master of Science in Nuclear Engineering
Department
Nuclear Engineering
Date of Award
January 2016
Recommended Citation
Mao, Keyou, "DEVELOPMENT OF DRIFT-FLUX CORRELATION AND FLOW PATTERN TRANSITION CRITERIA FOR TWO-PHASE CROSS-FLOW IN HORIZONTAL TUBE BUNDLES" (2016). Open Access Theses. 1125.
https://docs.lib.purdue.edu/open_access_theses/1125
First Advisor
Takashi Hibiki
Committee Member 1
Jun Chen
Committee Member 2
Tatyana Sizyuk