Date of Award

January 2016

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

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.

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