An Experimental Investigation of Critical Heat Flux Performance of Hypervapotron in Subcooled Boiling

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.

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

• Chen, Peipei

Contributors dc:contributor

• Jones, Barclay G.
• Newell, Ty A.

• Engineering, Nuclear

Language dc:language

eng

Identifier

(MiAaPQ)AAI3269857

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/85909