Transmission electron microscopy investigation of UALx based MTR fuel

    Research outputpeer-review

    Abstract

    High enriched, low density UAlx dispersion fuel has been successfully used in research and test reactors for several decades. However, publications of detailed post irradiation examinations are limited. In this paper, a sample of a high enriched uranium fuel plate (90% 235U enriched UAlx fuel dispersed in an Al matrix), irradiated to a burn-up of 21% 235U, is investigated with transmission electron microscopy. It is observed that the fuel became completely amorphous during irradiation. The Al matrix is found to remain crystalline and contains a large number of radiation induced defects. Neither in the fuel nor in the Al matrix, fission gas bubbles were observed.
    Original languageEnglish
    Title of host publicationTransactions RRFM
    Place of PublicationBrussels, Belgium
    StatePublished - Mar 2010
    Event2010 - RRFM - 14th ENS Topical Meeting on Research Reactor Fuel Management - European Nuclear Society, Marrakech
    Duration: 21 Mar 201025 Mar 2010
    http://www.euronuclear.org/meetings/rrfm2010/

    Conference

    Conference2010 - RRFM - 14th ENS Topical Meeting on Research Reactor Fuel Management
    Country/TerritoryMorocco
    CityMarrakech
    Period2010-03-212010-03-25
    Internet address

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