2024-03-29T06:16:21Zhttps://repositori.uji.es/oai/requestoai:repositori.uji.es:10234/1823342023-12-21T08:31:55Zcom_10234_7035com_10234_9col_10234_8617
00925njm 22002777a 4500
dc
Colgan, Nathan
author
Bottini, Joseph L.
author
Martinez Cuenca, Raul
author
Brooks, Caleb S.
author
2019-03
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%.
COLGAN, Nathan, et al. Experimental study of critical heat flux in flow boiling under subatmospheric pressure in a vertical square channel. International Journal of Heat and Mass Transfer, 2019, 130: 514-522.
http://hdl.handle.net/10234/182334
https://doi.org/10.1016/j.ijheatmasstransfer.2018.10.082
critical heat flux
flow boiling
subatmospheric pressure
departure from nucleate boiling
Experimental study of critical heat flux in flow boiling under subatmospheric pressure in a vertical square channel