Masters Theses

Title

One-group interfacial area transport equation for horizontal two-phase flow with 90-degree bend

Alternative Title

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, leaf iii.

Advisor(s)

Kim, Seunghin

Committee Member(s)

Usman, Shoaib
Mueller, Gary Edward, 1954-

Department(s)

Mining and Nuclear Engineering

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 leaves

Rights

© 2007 Kennard Callender, All rights reserved.

Document Type

Thesis - Citation

File Type

text

Language

English

Library of Congress 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://laurel.lso.missouri.edu/record=b5854671~S5

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