One-group interfacial area transport equation for horizontal two-phase flow with 90-degree bend
"The two-fluid model is used in the current thermal-hydraulic system analysis codes to perform detailed assessment of nuclear reactor safety. One of the major shortcomings of the two-fluid model has been the lack of an accurate and dynamic closure relation for interfacial area concentration. The interfacial area transport equation has been successfully used to resolve this problem by dynamically predicting the evolution of the interfacial area concentration. However, only models applicable to vertical two-phase flow are currently available. The present study develops a one-dimensional interfacial area transport equation applicable to horizontal bubbly flow with a 90-degree bend"--Abstract, page iii.
Mueller, Gary Edward, 1954-
Nuclear Engineering and Radiation Science
M.S. in Nuclear Engineering
U.S. NRC Office of Nuclear Regulatory Research
University of Missouri--Rolla
xvi, 184 pages
© 2007 Kennard Callender, All rights reserved.
Thesis - Citation
Nuclear reactors -- Fluid dynamics
Two-phase flow -- Mathematical models
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Link to Catalog Record
Full-text not available: Request this publication directly from Missouri S&T Library or contact your local library.http://merlin.lib.umsystem.edu/record=b5854671~S5
Callender, Kennard, "One-group interfacial area transport equation for horizontal two-phase flow with 90-degree bend" (2007). Masters Theses. 24.
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