Volume 5, Issue 1 (January 2008)

    Microstructure Evolution in Zr Alloys during Irradiation: Dose, Dose Rate, and Impurity Dependence

    (Received 15 March 2007; accepted 1 November 2007)

    Published Online: 2007

    CODEN: JAIOAD

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    Abstract

    The performance of zirconium alloys in BWR, PWR, and PHWR nuclear reactors is dependent on the microstructure. Accordingly, the characterization of the microstructure is an integral part of any study conducted to develop models for in-reactor performance. Although the as-fabricated microstructure (texture, grain size, dislocation density, and phase or precipitate distribution) determines the basic physical properties of a given component, there are changes that occur during irradiation that can have a significant effect on these properties. Microstructures that illustrate specific features of the radiation damage that forms in Zr alloys will be illustrated and discussed in terms of the dose, dose rate, and impurity factors that are applicable.


    Author Information:

    Griffiths, M.
    Senior Scientist, AECL, Ontario,


    Stock #: JAI101146

    ISSN: 1546-962X

    DOI: 10.1520/JAI101146

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    Author
    Title Microstructure Evolution in Zr Alloys during Irradiation: Dose, Dose Rate, and Impurity Dependence
    Symposium 15th International Symposium on Zirconium in the Nuclear Industry, 2007-06-28
    Committee B10