High pressure simulation experiment on corium dispersion in direct containment heating

Q. Wu, S. Kim, M. Ishii, S. T. Revankar, R. Y. Lee

    Research output: Contribution to journalArticlepeer-review

    6 Scopus citations


    Purdue 1/10 scale direct containment heating separate effects experiments under a reactor vessel pressure up to 14.2 MPa are presented. With the test facility scaled to the Zion PWR geometry, these tests are mainly focused on the corium dispersion phenomenon in order to obtain a better understanding of the dominant driving mechanisms. Water and woods metal have been used separately to simulate the core melt, the reactor vessel being pressurized with nitrogen gas analogous to the steam in the prototypic case. The entire test transient lasted for a few seconds, and the liquid dispersion in the test cavity occurred within only 0.5 s. To synchronize the data acquisition and blowdown transient, the test initiation was triggered by breaking two rupture discs in the liquid/gas delivery system. Parameters characterizing the liquid transport were obtained via various instruments. Important information about the mean size and size distribution of the dispersed droplets in the test cavity, the liquid film flow transient, the subcompartment trapping, and the liquid carry-over to the containment has been obtained. These results, along with data from a previous low pressure (1.4 MPa) experiment carried out at Purdue University, form a solid database for further theoretical analysis.

    Original languageEnglish (US)
    Pages (from-to)257-269
    Number of pages13
    JournalNuclear Engineering and Design
    Issue number1-3
    StatePublished - Aug 1 1996

    All Science Journal Classification (ASJC) codes

    • Nuclear and High Energy Physics
    • Nuclear Energy and Engineering
    • Materials Science(all)
    • Safety, Risk, Reliability and Quality
    • Waste Management and Disposal
    • Mechanical Engineering


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