Effect of pressure on critical heat flux in uniformly heated vertical annulus under low flow conditions

Citation
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
Citations number
26
Categorie Soggetti
Nuclear Emgineering
Journal title
NUCLEAR ENGINEERING AND DESIGN
ISSN journal
00295493 → ACNP
Volume
203
Issue
2-3
Year of publication
2001
Pages
159 - 174
Database
ISI
SICI code
0029-5493(200101)203:2-3<159:EOPOCH>2.0.ZU;2-R
Abstract
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.