Title of article :
Critical heat flux of water in vertical round tubes at low pressure and low flow conditions Original Research Article
Author/Authors :
Hong-Chae Kim، نويسنده , , Won Pil Baek، نويسنده , , Soon Heung Chang، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2000
Pages :
25
From page :
49
To page :
73
Abstract :
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∼1.77 m; pressure of 106∼951 kPa; mass flux of 20∼277 kg m−2 s−1; and inlet subcooling of 50∼654 kJ kg−1, thermodynamic equilibrium critical quality of 0.323∼1.251 and CHF of 108∼1598 kW m−2. Flow regime analysis based on Mishima & 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 film 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 for future reference.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2000
Journal title :
Nuclear Engineering and Design Eslah
Record number :
889143
Link To Document :
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