In-Reactor Deformation of Zirconium Alloy Components

    Volume 5, Issue 6 (June 2008)

    ISSN: 1546-962X


    Published Online: 10 June 2008

    Page Count: 16

    Holt, R. A.
    Department of Mechanical and Materials Engineering, Queen’s University, Kingston, Ontario

    (Received 17 July 2007; accepted 3 April 2008)


    This paper briefly reviews work by the author identifying and describing in-reactor deformation mechanisms of materials and structures used in nuclear reactors, in particular, Zircaloy-2, Zircaloy-4, and Zr-2.5Nb, and the CANDU fuel channel (comprising Zr alloy pressure tubes, calandria tubes, and spacers). The discussion is set in the context of contemporary findings of other workers in the international community. The following themes are highlighted: The contributions of creep and growth to deformation; c-component dislocations and the fluence dependence of irradiation growth; anisotropy of irradiation growth; deformation equations and pressure tube-to-calandria tube contact in CANDU reactors; low temperature flux (damage rate) dependence of deformation rates. The first developments were reported in 1976 at the third conference in this series and there are ongoing developments in all areas. The linear low temperature flux dependence of creep and growth rates is yet to be satisfactorily explained.

    Paper ID: JAI101354

    DOI: 10.1520/JAI101354

    ASTM International is a member of CrossRef.

    Title In-Reactor Deformation of Zirconium Alloy Components
    Symposium 15th International Symposium on Zirconium in the Nuclear Industry, 2007-06-28
    Committee B10