Chemical decladding of non-irradiated stainless-steel canned uranium dioxide fuel elements

Georges Dumont, Walter Goossens

    Research outputpeer-review

    5 Downloads (Pure)

    Abstract

    In reprocessing nuclear fuel it is necessary to remove the clad prior to treating the fuel itself adequately. For stainless-steel cladded fuel, gaseous mixtures of hydrogen fluoride and oxygen at temperatures above 550° C can be used.
    Data obtained for non-irradiated stainless-steel Al SI 304 L cladded uranium dioxide pellets are described.
    Experiments were performed in a boat reactor and in chemical columns up to 10
    cm in diameter for assemblies up to 19 elements 5O cm long. These studies
    revealed the main factors for scale-up such as the geometry of the bundle,
    the absence or presence of fluidized alumina, the prefluorination of the correct type of alumina and the influence of the self-regulative character of the reaction.
    Original languageEnglish
    PublisherSCK CEN
    Number of pages44
    StatePublished - Jan 1969

    Publication series

    NameSCK CEN Reports
    PublisherSCK CEN
    No.BLG-435

    Cite this