TEM examinations of the metal-oxide interface of zirconium based alloys irradiated in a pressurized water reactor

S. Abolhassani, R. Restani, T. Rebac, F. Groeschel, W. Hoffelner, G. Bart, W. Goll, F. Aeschbach, B. Cox, B. Kammenzind, B. Cheng, A. Motta

Research output: Chapter in Book/Report/Conference proceedingConference contribution

17 Scopus citations

Abstract

Metal-oxide interfaces of three different materials irradiated in a pressurized water reactor have been analyzed by TEM and AEM. Standard Zircaloy-4, low-tin Zircaloy-4, and Zr-2.5%Nb were used for this study. The microstructure of the material on the two sides of the metal-oxide interface, the geometry of the interface, the distribution of different alloying elements, and the oxygen profile have been examined in each material. Results of the examinations showed that the three materials had different microstructure and oxygen distribution on the two sides of the metal-oxide interface. In particular, the following parameters were noticed: a) the geometry of the interface seems to be of a different nature in the case of Zr-2.5%Nb alloy. Unlike the Zircaloy-4 alloys, which show an undulated interface, this material has a "jigsaw" type interface. This point is discussed, and its role on the oxidation is considered, b) Hydrides are observed and analyzed in the vicinity of the interface in the case of low-tin Zircaloy-4, and it is shown that they can have an influence on the occurrence of cracks in this material. c) The origins of stress are discussed, and it is shown that it can have different sources. The crystal structure of the oxides is mainly monoclinic. A tetragonal oxide is observed at some regions, in particular in the standard Zircaloy-4.

Original languageEnglish (US)
Title of host publicationZirconium in the NUCLEAR INDUSTRY - Fourteenth International Symposium
PublisherAmerican Society for Testing and Materials
Pages467-493
Number of pages27
Edition1467
ISBN (Print)0803134932, 9780803134935
StatePublished - Jan 1 2005
Event14th International Symposium on Zirconium in the NUCLEAR INDUSTRY - Stockholm, Sweden
Duration: Jun 13 2004Jun 17 2004

Publication series

NameASTM Special Technical Publication
Number1467
ISSN (Print)0066-0558

Other

Other14th International Symposium on Zirconium in the NUCLEAR INDUSTRY
CountrySweden
CityStockholm
Period6/13/046/17/04

All Science Journal Classification (ASJC) codes

  • Engineering(all)

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    Abolhassani, S., Restani, R., Rebac, T., Groeschel, F., Hoffelner, W., Bart, G., Goll, W., Aeschbach, F., Cox, B., Kammenzind, B., Cheng, B., & Motta, A. (2005). TEM examinations of the metal-oxide interface of zirconium based alloys irradiated in a pressurized water reactor. In Zirconium in the NUCLEAR INDUSTRY - Fourteenth International Symposium (1467 ed., pp. 467-493). (ASTM Special Technical Publication; No. 1467). American Society for Testing and Materials.