Redistribution of alloying elements in Zircaloy-2 after in-reactor exposure

G. Sundell, M. Thuvander, P. Tejland, M. Dahlbäck, L. Hallstadius, H. O. Andrén

Research output: Contribution to journalArticlepeer-review

70 Scopus citations

Abstract

An atom probe tomography study of the microstructure of a Zircaloy-2 material subjected to 9 annual cycles of BWR exposure has been conducted. Upon dissolution of secondary phase particles, Fe and Cr are seen to reprecipitate in large numbers of clusters and particles of 1-5 nm sizes throughout the Zr metal matrix. Fe and Sn were observed to segregate to ring-shaped features in the metal that are interpreted to be 〈c〉-component vacancy loops. This implies that these two elements play a major role in the irradiation growth phenomenon in Zr alloys, which is believed to be caused by the formation of 〈c〉-loops. Similarly to autoclave-corroded Zr alloys, the formation of a sub-oxide layer of approximate composition ZrO was observed. On the other hand, no oxygen saturated metal phase was detected underneath the oxide scale.

Original languageEnglish
Pages (from-to)178-185
Number of pages8
JournalJournal of Nuclear Materials
Volume454
Issue number1-3
DOIs
StatePublished - Nov 2014
Externally publishedYes

Funding

The authors would like to thank Daniel Jädernäs at Studsvik Nuclear AB and the MUZIC-2 consortium for useful discussions about the manuscript. Financial support was provided by Westinghouse Electric Sweden AB , Sandvik Materials Technology AB , Vattenfall AB , the Electric Power Research Institute , Studsvik Nuclear AB and the Swedish Research Council .

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