Microstructure Evolution in ZrC Irradiated with Kr ions

    Published: Jan 2006

      Format Pages Price  
    PDF (980K) 7 $25   ADD TO CART
    Complete Source PDF (17M) 7 $98   ADD TO CART


    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.


    ZrC, Kr ions, microstructure, irradiation, dislocation, lattice expansion

    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

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP37591S

    CrossRef ASTM International is a member of CrossRef.