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/Report/Conference proceedingConference PaperResearchpeer-review

1 Citation (Scopus)

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
Pages1419-1426
Number of pages8
Publication statusPublished - 2009
Externally publishedYes
EventInternational Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 - Virginia Beach, United States of America
Duration: 23 Aug 200927 Aug 2009
Conference number: 14th

Publication series

Name14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Volume2

Conference

ConferenceInternational Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Country/TerritoryUnited States of America
CityVirginia Beach
Period23/08/0927/08/09

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