Thermal Hydraulic and Two-Phase Phenomena in Reflooding of Nuclear Reactor Cores

[+] Author and Article Information
S. M. Ghiaasiaan

Science Applications International Corporation, Hermosa Beach, CA 90254

I. Catton

School of Engineering and Applied Science, University of California, Los Angeles, Calif. 90024

R. B. Duffey

Electric Power Research Institute, Palo Alto, Calif. 94303

J. Fluids Eng 106(4), 477-485 (Dec 01, 1984) (9 pages) doi:10.1115/1.3243153 History: Received September 22, 1982; Online October 26, 2009


A quasi-steady, two-dimensional thermal hydraulic analysis of the two-phase region formed ahead of a quench front during reflooding of a slab or cylindrical core is carried out, and the results for slab geometry are compared with the experiment. It is shown that the two-phase level variation in the core is due to the transverse heat flux power profile, and is sensitive to the assumed pressure-drop boundary condition for the bundle, while the effects of crossflow and axial friction are small. Implicit expressions are given for predicting the quasi-steady two-phase level variation across slab and cylindrical cores.

Copyright © 1984 by ASME
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