Title of article
Critical heat flux under zero flow conditions in vertical annulus with uniformly and non-uniformly heated sections Original Research Article
Author/Authors
Se-Young Chun، نويسنده , , Sang Ki Moon، نويسنده , , Heung-June Chung، نويسنده , , Sun-Kyu Yang، نويسنده , , Moon-Ki Chung، نويسنده , , Masanori Aritomi، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2001
Pages
15
From page
265
To page
279
Abstract
The experimental study of water CHF (critical heat flux) under zero flow conditions has been carried out in an annulus flow channel with uniformly and non-uniformly heated sections over a pressure range of 0.52–14.96 MPa. In the present boiling system, the CHFs occur in the upper region of the heated section, in contrast to the results in the experiments for boiling tubes conducted by several investigators. The general trend of the CHF with pressure is that the CHF increases up to a medium pressure of about 6–8 MPa and decreases as the pressure is further increased. A comparison of the present data with the existing flooding CHF correlations shows that the correlations depend greatly on the effect of the heat flux distribution. When the correction terms with the density ratio and the effect of the heat flux distribution proposed in the present work are used with the CHF correlation based on the Wallis flooding correlation, it predicts the measured flooding CHF within an RMS error of 9.0%.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2001
Journal title
Nuclear Engineering and Design Eslah
Record number
889316
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