STP306

    The Irradiation and Examination of a Plutonium-Uranium Oxide Fast Reactor Fuel

    Published: Jan 1962


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    Abstract

    A program was carried out to study the irradiation behavior of a PuO2-UO2 fuel. Forty fuel specimens were fabricated, encapsulated, and irradiated in the General Electric Test Reactor to burnups ranging from 5000 to 99,000 Mw days per ton and heat fluxes ranging from 0.5 × 106 to 1.58 × 106 Btu per hr sq ft. A postirradiation examination of the fuel was made to determine the fuel condition, central void characteristics and fission gas release. The results of this program are presented and discussed.


    Author Information:

    Gerhart, JM
    General Electric Co., Atomic Power Equipment Department, Vallecitos Atomic Laboratory, Pleasanton, Calif.

    Siltanen, JN
    General Electric Co., Atomic Power Equipment Department, Vallecitos Atomic Laboratory, Pleasanton, Calif.

    Cochran, JS
    General Electric Co., Atomic Power Equipment Department, Vallecitos Atomic Laboratory, Pleasanton, Calif.


    Paper ID: STP44393S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP44393S


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