Date of Award
Master of Science in Nuclear Engineering
Committee Member 1
Committee Member 2
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.
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.