• Title of article

    Analysis on Lift-Off experiment in Halden reactor by FEMAXI-6 code

  • Author/Authors

    Suzuki، نويسنده , , M. and Kusagaya، نويسنده , , K. and Saitou، نويسنده , , H. and Fuketa، نويسنده , , T.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2004
  • Pages
    8
  • From page
    417
  • To page
    424
  • Abstract
    Analysis was conducted on the Lift-Off experiment IFA-610.1 in Halden reactor by the FEMAXI-6 code using detailed measured data in the test-irradiation. Fuel center temperature was calculated on the two assumptions, i.e. (1) an enhanced thermal conductance across the pellet-clad bonding layer is maintained during the cladding creep-out by over-pressurization, and (2) the bonding layer is broken by the cladding creep-out, and these results were compared with the measured data to analyze the effect of the creep-out by over-pressure inside the test pin. The measured center temperature rise was higher by a few tens of K than the prediction performed on the assumption (1), though this difference was much smaller than the predicted rise on the assumption (2). Therefore, it is appropriate to attribute the measured center temperature rise to the decrease of effective thermal conductance by irregular re-location of pellet fragments, etc. which was caused by cladding creep-out.
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2004
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1361164