Measurement of critical heat flux for narrow annuli submerged in saturated water

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An experimental study has been performed to improve understanding of boiling phenomena and critical heat flux (CHF) in narrow gaps. The experiment has been performed with annular test sections submerged in a pool of saturated water under atmospheric pressure with the following conditions: outer diameter of inner tube of 19 mm; heated length of 200 mm; annular gap sizes of 0.5-3.5 mm, and inclination angles from horizontal to vertical positions. The experimental results reveal that the CHF increases with the gap size and the inclination angle. A one-dimensional two-phase model with a modified friction factor correlation is suggested to predict the CHF condition. The developed model is also compared with other CHF data. (C) 2000 Elsevier Science S.A. All rights reserved.
Publisher
ELSEVIER SCIENCE SA
Issue Date
2000-06
Language
English
Article Type
Article
Keywords

SEVERE ACCIDENT; REACTOR VESSEL

Citation

NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.41 - 48

ISSN
0029-5493
URI
http://hdl.handle.net/10203/73902
Appears in Collection
NE-Journal Papers(저널논문)
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