• 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