Masters Theses
One-group interfacial area transport equation for horizontal two-phase flow with 90-degree bend
Abstract
"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.
Advisor(s)
Kim, Seunghin
Committee Member(s)
Usman, Shoaib
Mueller, Gary Edward, 1954-
Department(s)
Nuclear Engineering and Radiation Science
Degree Name
M.S. in Nuclear Engineering
Sponsor(s)
U.S. NRC Office of Nuclear Regulatory Research
Publisher
University of Missouri--Rolla
Publication Date
Spring 2007
Pagination
xvi, 184 pages
Rights
© 2007 Kennard Callender, All rights reserved.
Document Type
Thesis - Citation
File Type
text
Language
English
Subject Headings
Bubbles
Nuclear reactors -- Fluid dynamics
Transport theory
Two-phase flow -- Mathematical models
Thesis Number
T 9091
Print OCLC #
133465679
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~S5Recommended Citation
Callender, Kennard, "One-group interfacial area transport equation for horizontal two-phase flow with 90-degree bend" (2007). Masters Theses. 24.
https://scholarsmine.mst.edu/masters_theses/24
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