journal article·2014-11

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

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

Journal of Nuclear Materials· Volume 454· Issue 1-3
Publisher page

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 -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 -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.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Advanced Materials Characterization Techniques · Fusion materials and technologies

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