Title of article :
Effect of pressure on critical heat flux in uniformly heated vertical annulus under low flow conditions Original Research Article
Author/Authors :
Se-Young Chun، نويسنده , , Heung-June Chung، نويسنده , , Sang Ki Moon، نويسنده , , Sun-Kyu Yang، نويسنده , , Moon-Ki Chung، نويسنده , , Thomas Schoesse، نويسنده , , Masanori Aritomi، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2001
Pages :
16
From page :
159
To page :
174
Abstract :
Critical heat flux (CHF) experiments have been carried out in a wide range of pressure for an internally heated vertical annulus. The experimental conditions covered a range of pressure from 0.57 to 15.01 MPa, mass fluxes of 0 kg m−2 s−1 and from 200 to 650 kg m−2 s−1, and inlet subcoolings from 85 to 413 kJ kg−1. Most of the CHFs were identified to the dryout of the liquid film in the annular-mist flow. For the mass fluxes of 550 and 650 kg m−2 s−1, the CHFs had a maximum value at a pressure of 2–3 MPa, and the pressure at the maximum CHF values had a trend moving toward the pressure at the peak value of pool boiling CHF as the mass flux decreased. The CHF data under a zero mass flux condition indicate that both the effects of pressure and inlet subcooling on the CHF were smaller, compared with those for the CHF with a net water upflow. The Doerffer correlation using the 1995 CHF look-up table and the Bowring correlation show a good prediction capability for the present CHF data.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2001
Journal title :
Nuclear Engineering and Design Eslah
Record number :
889254
Link To Document :
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