Volume 3, Issue 4 (April 2006)

    Microstructure Evolution in ZrC Irradiated with Kr ions

    (Received 14 June 2005; accepted 9 October 2005)

    CODEN: JAIOAD

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    Abstract

    The gas-cooled fast reactor (GFR) is one of six concepts for the Generation-IV nuclear energy system. The fuel for the GFR requires both a high heavy metal loading and the ability to withstand temperatures up to 1600°C during a loss of coolant accident. ZrC is among the few potential refractory ceramic materials with necessary properties to be considered as matrix materials for a dispersed carbide fuel. The radiation response of ZrC to high dose and temperature is a critical research need. This work investigated the microstructure of ZrC irradiated with 1 MeV Kr ions to doses of 10 and 30 dpa at 27°C and 10 and 70 dpa at 800°C with a damage rate approximately 3.0 × 10−3 dpa/s. No radiation-induced amorphization was found. A lattice expansion of approximately 7 % was observed for ZrC irradiated to 70 dpa at 800°C.


    Author Information:

    Gan, J
    Research Scientist, Idaho National Laboratory, Idaho Falls, ID

    Meyer, MK
    Research Scientist, Idaho National Laboratory, Idaho Falls, ID

    Birtcher, RC
    Physicist, Argonne National Laboratory, Argonne, IL

    Allen, TR
    Professor, The University of Wisconsin, Madison, WI


    Stock #: JAI12376

    ISSN: 1546-962X

    DOI: 10.1520/JAI12376

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    Author
    Title Microstructure Evolution in ZrC Irradiated with Kr ions
    Symposium Effects of Radiation on Materials: 22nd International Symposium, 2004-06-10
    Committee E10