STP306: Effects of Burnup on Certain Ceramic Fuel Materials

    Bleiberg, M L
    Bettis Atomic Power Laboratory, Pittsburgh, Pa.

    Yeniscavich, W
    Bettis Atomic Power Laboratory, Pittsburgh, Pa.

    Gray, R G
    Bettis Atomic Power Laboratory, Pittsburgh, Pa.

    Pages: 22    Published: Jan 1962


    Abstract

    The effect of irradiation in pressurized hot water loops on bulk UO2, UO2 dispersed in BeO, and UO2 dispersed in Al2O3 are compared. It is shown that when UO2 is irradiated to high exposures, the material increases in volume, and increased amounts of fission gases are released. In addition to this effect in BeO and Al2O3, swelling occurs due to fission fragment destruction of the matrix phase. The parameters influencing this behavior are discussed.


    Paper ID: STP44386S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP44386S


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