From solid solution to cluster formation of Fe and Cr in α-Zr
File(s)ZrA_3.1_Final version.pdf (3.8 MB)
Accepted version
Author(s)
Type
Journal Article
Abstract
To understand the mechanisms by which the re-solution of Fe and Cr additions increase the corrosion rate of irradiated Zr alloys, the solubility and clustering of Fe and Cr in model binary Zr alloys was investigated using a combination of experimental and modelling techniques — atom probe tomography (APT), x-ray diffraction (XRD), thermoelectric power (TEP) and density functional theory (DFT). Cr occupies both interstitial and substitutional sites in the α-Zr lattice; Fe favours interstitial sites, and a low-symmetry site that was not previously modelled is found to be the most favourable for Fe. Lattice expansion as a function of Fe and Cr content in the α-Zr matrix deviates from Vegard's law and is strongly anisotropic for Fe additions, expanding the c-axis while contracting the a-axis. Matrix content of solutes cannot be reliably estimated from lattice parameter measurements, instead a combination of TEP and APT was employed. Defect clusters form at higher solution concentrations, which induce a smaller lattice strain compared to the dilute defects. In the presence of a Zr vacancy, all two-atom clusters are more soluble than individual point defects and as many as four Fe or three Cr atoms could be accommodated in a single Zr vacancy. The Zr vacancy is critical for the increased apparent solubility of defect clusters; the implications for irradiation induced microstructure changes in Zr alloys are discussed.
Date Issued
2015-10-09
Date Acceptance
2015-10-01
Citation
Journal of Nuclear Materials, 2015, 467 (Part 1), pp.320-331
ISSN
1873-4820
Publisher
Elsevier
Start Page
320
End Page
331
Journal / Book Title
Journal of Nuclear Materials
Volume
467
Issue
Part 1
Copyright Statement
© 2015 Elsevier. Licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International http://creativecommons.org/licenses/by-nc-nd/4.0/
Sponsor
Australian Nuclear Science and Technology Organisation (ANSTO)
Identifier
http://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcApp=PARTNER_APP&SrcAuth=LinksAMR&KeyUT=WOS:000365602800034&DestLinkType=FullRecord&DestApp=ALL_WOS&UsrCustomerID=1ba7043ffcc86c417c072aa74d649202
Grant Number
NA
Subjects
Science & Technology
Technology
Physical Sciences
Materials Science, Multidisciplinary
Nuclear Science & Technology
Mining & Mineral Processing
Materials Science
ATOM-PROBE TOMOGRAPHY
DOSE NEUTRON-IRRADIATION
THERMOELECTRIC-POWER MEASUREMENTS
POINT-DEFECT DIFFUSION
2ND PHASE PARTICLES
ZIRCONIUM ALLOYS
HCP-ZR
MICROSTRUCTURE EVOLUTION
PRECIPITATE STABILITY
SELF-INTERSTITIALS
Energy
0912 Materials Engineering
Publication Status
Published