The effect of residual stress on growth of oxide scale on zirconium alloys

E. Polatidis, P. G. Frankel, M. Preuss

    Research output: Chapter in Book/Conference proceedingConference contributionpeer-review

    Abstract

    Zirconium alloys have been extensively used in nuclear power reactors as cladding materials and structural fuel assembly components because of their low neutron absorption, adequate mechanical properties and corrosion resistance. However, corrosion of the cladding can be a life-limiting factor and a better understanding of the corrosion mechanisms could lead to improvement of the burn up efficiency. Residual stresses that develop in the oxide, due to the large difference of the molar volumes of zirconium and zirconium dioxide, are believed to play a key role in understanding the corrosion mechanism. In this work high-energy synchrotron X-ray diffraction, in transmission geometry, has been employed for residual stress measurement in zirconium oxides. Results from complementary finite element analysis have been related to the experimental results.
    Original languageEnglish
    Title of host publication14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009|Int. Conf. Environ. Degrad. Mater. Nucl. Power Syst. Water React.
    Place of PublicationOn CD
    PublisherAmerican Nuclear Society
    Pages1419-1426
    Number of pages7
    Volume2
    ISBN (Print)9781617388538
    Publication statusPublished - 2009
    Event714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 - Virginia Beach, VA
    Duration: 1 Jul 2009 → …

    Conference

    Conference714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
    CityVirginia Beach, VA
    Period1/07/09 → …

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