Title of article :
Critical heat flux and flow pattern for water flow in annular geometry Original Research Article
Author/Authors :
Jae-Wook Park، نويسنده , , Won Pil Baek، نويسنده , , Soon Heung Chang، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 1997
Pages :
19
From page :
137
To page :
155
Abstract :
An experimental study on critical heat flux (CHF) and two-phase flow visualization has been performed for water flow in internally-heated, vertical, concentric annuli under near atmospheric pressure. Tests have been done under stable forced-circulation, upward and downward flow conditions with three test sections of relatively large gap widths (heated length = 0.6 m, inner diameter = 19 mm, outer diameter = 29, 35 and 51 mm). The outer wall of the test section was made up of the transparent Pyrex tube to allow the observation of flow patterns near the CHF occurrence. The CHF mechanism was changed in the order of flooding, churn-to-annular flow transition and local dryout under a large bubble in churn flow as the flow rate was increased from zero to higher values. Observed parametric trends are consistent with the previous understanding except that the CHF for downward flow is considerably lower than that for the upward flow. In addition to the experiment, selected CHF correlations for annuli are assessed based on 1156 experimental data from various sources. The Doerffer et al. (1994); Barnett (1966); Jannsen and Kervinen (1963); Levitan and Lantsman (1977) correlations show reasonable predictions for wide parameter ranges, among which the Doerffer et al. (1994) correlation shows the widest parameter ranges and a possibility of further improvement. However, there is no correlation predicting the low-pressure, low-flow CHF satisfactorily.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
1997
Journal title :
Nuclear Engineering and Design Eslah
Record number :
888263
Link To Document :
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