Calcul des distributions de temperature dans les plaques combustibles de BR2 avec decollement du gainage ou inclusion d'uranium pur

R. De Meersman, Georges Minsart

    Research outputpeer-review

    11 Downloads (Pure)

    Abstract

    The equations of the heat diffusion are solved with the help of a neutron diffusion code. This method is used for the study of two kinds of defects in the fuel plates of the BR2 reactor: cIad bonding defect and uranium inclusion . The corresponding hot spot factors are computed . Defects of circular and rectangular section are studied.
    Original languageEnglish
    PublisherSCK CEN
    Number of pages41
    StatePublished - Dec 1962

    Publication series

    NameSCK•CEN Reports
    PublisherStudiecentrum voor Kernenergie
    No.BLG-188

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