Critical heat flux of water in vertical round tubes at low pressure and low flow conditions

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An experimental study on critical heat flux (CHF) has been performed for water flow in vertical round tubes under low pressure and low flow (LPLF) conditions to provide a systematic data base and to investigate parametric trends. Totally 513 experimental data have been obtained with Inconel-625 tube test sections in the following conditions: diameter of 6, 8, 10 and 12 mm; heated length of 0.3 similar to 1.77 m; pressure of 106 similar to 951 kPa; mass flux of 20 similar to 277 kg m(-2) s(-1): and inlet subcooling of 50 similar to 654 kJ kg(-1), thermodynamic equilibrium critical quality of 0.323 similar to 1.251 and CHF of 108 similar to 1598 kW m(-2). Flow regime analysis based on Mishima Bi Ishii's flow regime map indicates that most of the CHF occurred due to liquid film dryout in annular-mist and annular flow regimes. Parametric trends are examined from two different points of view: fixed inlet conditions and fixed exit conditions. The parametric trends are generally consistent with previous understandings except for the complex effects of system pressure and tube diameter. Finally, several prediction models are assessed with the measured data; the typical mechanistic liquid him dryout model and empirical correlations of (Shah, M.M., 1987. Heat Fluid Flow 8 (4), 326-335; Baek, W.P., Kim, H.G., Chang, S.H., 1997. KAIST critical heat flux correlation for water flow in vertical round tubes, NUTHOS-5, Paper No. AA5 show good predictions. The measured CHF data are listed in Appendix B for future reference. (C) 2000 Published by Elsevier Science S.A. All rights reserved.
Publisher
ELSEVIER SCIENCE SA
Issue Date
2000-06
Language
English
Article Type
Article
Keywords

BURNOUT

Citation

NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.49 - 73

ISSN
0029-5493
URI
http://hdl.handle.net/10203/77235
Appears in Collection
NE-Journal Papers(저널논문)
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