Combined Modeling and Experimental Validation of Boiling Curve and Critical Heat Flux

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.

Name thesis:degree_name

Ph.D.

Level thesis:degree_level

Dissertation

Discipline thesis:degree_discipline

Nuclear Engineering

Grantor

University of Illinois at Urbana-Champaign

Year dc:date

2015

Author dc:creator

• Wu, Wen

Contributors dc:contributor

• Jones, Barclay G.
• Newell, Ty A.

• Engineering, Mechanical

Language dc:language

eng

Identifier

(MiAaPQ)AAI3270054

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/85912