STP223: Thermal Testing of Reactor Fuel Elements

    Monaweck, J. H.
    Argonne National Laboratory, Lemont, Ill.

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

    Pages: 6    Published: Jan 1958


    Abstract

    Thermal tests have been used to determine the integrity of the cladding and the bond between the uranium metal and the cladding in reactor fuel elements. Two of the techniques will be described, the isothermal frost test and thermography.


    Paper ID: STP42012S

    Committee/Subcommittee: E07.07

    DOI: 10.1520/STP42012S


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