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Title:An Experimental Investigation of Critical Heat Flux Performance of Hypervapotron in Subcooled Boiling
Author(s):Chen, Peipei
Doctoral Committee Chair(s):Jones, Barclay G.; Newell, Ty A.
Department / Program:Nuclear Engineering
Discipline:Nuclear Engineering
Degree Granting Institution:University of Illinois at Urbana-Champaign
Subject(s):Engineering, Nuclear
Abstract:A non-dimensional CHF correlation for smooth rectangular channels and the hypervapotron channel was developed and compared with experimental data in this work. In addition, a hot-spot model was developed to give predictions of critical heat flux on both plain and hypervapotron surfaces. It was developed on observations of bubble formation, departure and coalescence, and on the confirmation of nucleation structure on the heating surface. Finally, a numerical code was successfully developed to give CHF predictions for hypervapotron configurations. The simulation indicates that the better performance of CHF in hypervapotron configurations is a result of high conductivity material with augmented heating surfaces in subcooled boiling environment. Different fin dimensions were also tested numerically to compare the experimental results, and suggestions are provided with respect to the combination of performance and economy.
Issue Date:2007
Description:154 p.
Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 2007.
Other Identifier(s):(MiAaPQ)AAI3269857
Date Available in IDEALS:2015-09-28
Date Deposited:2007

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