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.
Keywords
Cross-Flow, Drift-Flux Model, Flow Pattern, Steam Generator, Two-Phase Flow
Degree Type
Thesis
Degree Name
Master of Science in Nuclear Engineering
Department
Nuclear Engineering
First Advisor
Takashi Hibiki
Committee Member 1
Jun Chen
Committee Member 2
Tatyana Sizyuk
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