Sy. Chun et al., Effect of pressure on critical heat flux in uniformly heated vertical annulus under low flow conditions, NUCL ENG DE, 203(2-3), 2001, pp. 159-174
Critical heat flux (CHF) experiments have been carried out in a wide range
of pressure for an internally heated vertical annulus. The experimental con
ditions covered a range of pressure from 0.57 to 15.01 MPa, mass fluxes of
0 kg m(-2) s(-1) and from 200 to 650 kg m(-2) s(-1), and inlet subcoolings
from 85 to 413 kJ kg(-1). Most of the CHFs were identified to the dryout of
the liquid him in the annular-mist flow. For the mass fluxes of 550 and 65
0 kg m(-2) s(-1), the CHFs had a maximum value at a pressure of 2-3 MPa, an
d the pressure at the maximum CHF values had a trend moving toward the pres
sure at the peak value of pool boiling CHF as the mass flux decreased. The
CHF data under a zero mass flux condition indicate that both the effects of
pressure and inlet subcooling on the CHF were smaller, compared with those
for the CHF with a net water upflow. The Doerffer correlation using the 19
95 CHF look-up table and the Bowring correlation show a good prediction cap
ability for the present CHF data. (C) 2001 Elsevier Science B.V. All rights
reserved.