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

Gustav Sundell (Institutionen för teknisk fysik, Materialens mikrostruktur ) ; Mattias Thuvander (Institutionen för teknisk fysik, Materialens mikrostruktur ) ; Pia Tejland ; Mats Dahlbäck ; Lars Hallstadius ; Hans-Olof Andrén (Institutionen för teknisk fysik, Materialens mikrostruktur )
Journal of Nuclear Materials (0022-3115). Vol. 454 (2014), 1-3, p. 178-185.
[Artikel, refereegranskad vetenskaplig]

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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Denna post skapades 2014-12-02. Senast ändrad 2015-03-30.
CPL Pubid: 207126


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Institutioner (Chalmers)

Institutionen för teknisk fysik, Materialens mikrostruktur (2012-2015)


Defekter och diffusion

Chalmers infrastruktur

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Atomic Scale Degradation of Zirconium Alloys for Nuclear Applications