Experimental study of critical heat flux in flow boiling under subatmospheric pressure in a vertical square channel

Nathan Colgan, Joseph L. Bottini, Raúl Martínez-Cuenca, Caleb Brooks

Research output: Contribution to journalArticle

Abstract

Critical Heat Flux (CHF) is the maximal limit of heat flux in two-phase nucleate boiling heat transfer; therefore, an understanding of CHF under a wide range of conditions is important for safe system operation. In this work, CHF experiments are conducted over a range of subatmospheric system pressures in a vertical square channel that is heated on one side. The experimental conditions cover a pressure range of 20 kPa to 108 kPa, a mass flux range of 45–190 kg/m2-s, and an inlet subcooling range of 0–14 K. Heat flux is gradually increased until an excursion of the wall temperature occurs, indicating CHF. For the experimental conditions considered, CHF increases with rising system pressure, mass flux, and inlet subcooling, although the effects of mass flux and inlet subcooling are weak. A new correlation for CHF is developed and found to predict the data with an average error of ±15.6%.

LanguageEnglish (US)
Pages514-522
Number of pages9
JournalInternational Journal of Heat and Mass Transfer
Volume130
DOIs
StatePublished - Mar 1 2019

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boiling
Boiling liquids
Heat flux
heat flux
Mass transfer
nucleate boiling
Nucleate boiling
wall temperature
heat transfer
Heat transfer

Keywords

  • Critical heat flux
  • Departure from nucleate boiling
  • Flow boiling
  • Subatmospheric pressure

ASJC Scopus subject areas

  • Condensed Matter Physics
  • Mechanical Engineering
  • Fluid Flow and Transfer Processes

Cite this

Experimental study of critical heat flux in flow boiling under subatmospheric pressure in a vertical square channel. / Colgan, Nathan; Bottini, Joseph L.; Martínez-Cuenca, Raúl; Brooks, Caleb.

In: International Journal of Heat and Mass Transfer, Vol. 130, 01.03.2019, p. 514-522.

Research output: Contribution to journalArticle

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