• Title of article

    The effect of corium composition and interaction vessel geometry on the prototypic steam explosion

  • Author/Authors

    Jin Ho Song، نويسنده , , Jong-Hwan Kim، نويسنده , , Seong Wan Hong، نويسنده , , Beong Tae Min، نويسنده , , Hee-Dong Kim، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2006
  • Pages
    15
  • From page
    1437
  • To page
    1451
  • Abstract
    This paper discusses the results of steam explosion experiments using molten material consisting of UO2 and ZrO2 mixture, which is called corium, to simulate a prototypic steam explosion in a nuclear reactor during a postulated severe accident. About 5–10 kg of molten material with enough superheat was poured into a pool of water in a test section at room temperature to simulate ex-vessel steam explosion in the reactor situation. Most of the experiments were externally triggered. The purpose of the experiments was to investigate the effect of material composition and average void fraction on the strength of a prototypic steam explosion, which were highlighted as major unresolved issues. The experiments were performed using two kinds of mixtures, one, corium A, at 70:30 weight percent composition of UO2 and ZrO2, close to eutectic composition, and the other, corium B, at 80:20 weight percent. Also, two kinds of cylindrical test sections having a different diameter were used. It turned out that corium A was likely to produce an energetic steam explosion, while corium B seldom led to an energetic steam explosion. The existence of mush phase for the non-eutectic mixture is suggested to be the reason for the difference. Comparative cross sectional views of the corium particles by scanning electron microscope supported the proposed argument. The tests performed with a narrow test section seldom led to an energetic steam explosion for both materials. An increase in average void is suggested to be the reason for the non-explosive behavior, which is consistent with the physical models employed in the current steam explosion computer codes.
  • Journal title
    Annals of Nuclear Energy
  • Serial Year
    2006
  • Journal title
    Annals of Nuclear Energy
  • Record number

    406248