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    Fission Fragment Damage in Ceramic Nuclear Fuels


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    Post-irradiation examinations of several ceramic nuclear fuels are summarized, emphasizing the identification and characterization of fission induced defects. The lattice parameter and electrical resistivity were significantly altered with fission damage in all fuels. A remarkable reduction, however, was found in the irradiation induced changes of both physical properties in uranium dioxide (UO2), uranium nitrite (UN), and uranium sesquicarbide (U2C3) at high fission doses, probably because of a preferential annihilation of extended defects in the damage process. An effect of the extended defects in irradiated single crystalline UC was a greater increased resistivity at low temperature, indicating a contribution of interstitial-type defects. The irradiation induced physical properties, on the other hand, were annealed out, within a few recovery steps in all the fuels, exhibiting some dependence on the extent of the fission damage. It was of great interest that a drastic change was observed in the magnetic property changes in some magnetic substances, such as uranium monosulfide (US) and UN. All the magnetic parameters changed with fission damage and recovered to the original values in successive annealing processes.


    fission damage, ceramic nuclear fuels, lattice parameters, electrical resistivity, magnetic properties, recovery annealing

    Author Information:

    Matsui, H
    Nagoya University, Nagoya,

    Horiki, M
    Nagoya University, Nagoya,

    Tamaki, M
    Nagoya University, Nagoya,

    Kirihara, T
    Nagoya University, Nagoya,

    Committee/Subcommittee: E10.14

    DOI: 10.1520/STP25675S