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Title:Combined Modeling and Experimental Validation of Boiling Curve and Critical Heat Flux
Author(s):Wu, Wen
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, Mechanical
Abstract:To verify this model, experiments are conducted for a range of conditions. A highspeed, high-fidelity imaging system is employed to quantitatively investigate the bubble motion. Predictions are compared with experimental measurements in this study as well as data available in the literature, with an overall good agreement achieved. An average error of +/-25% is observed for the boiling curve prediction, while for the critical heat flux the prediction error is limited within +/-20%, which equals or supersedes most available semi-empirical models or correlations. This model captures and correctly describes the stochastic nature of the flow and thermal variations, as well as the tightly coupled bubble motion in the flow and thermal fields. This suggests that to extend the modeling of subcooled nucleate boiling to predict critical heat flux, both probabilistic formulation and stochastic analysis need to be utilized.
Issue Date:2007
Description:145 p.
Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 2007.
Other Identifier(s):(MiAaPQ)AAI3270054
Date Available in IDEALS:2015-09-28
Date Deposited:2007

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