STP223: Measurement of Cladding Thickness on Uranium by Autoradiography

    Bradley, G. E.
    Argonne National Laboratory, Lemont, Ill.

    McGonnagle, W. J.
    Argonne National Laboratory, Lemont, Ill.

    Gonzales, P. R.
    Argonne National Laboratory, Lemont, Ill.

    Pages: 10    Published: Jan 1958


    Abstract

    Fuel elements for nuclear reactors consist of a core of fissionable material-uranium—and usually source materials or diluents surrounded by an inert corrosion-resistant jacket or cladding. The cladding material stops fission products from escaping, eliminates any reaction or solution between the fuel and coolant, restrains the fuel to a limited extent from warping and surface roughening, and reduces the danger of toxic materials being dispersed in the coolant system.


    Paper ID: STP42006S

    Committee/Subcommittee: E07.01

    DOI: 10.1520/STP42006S


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