Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium
File(s)Manuscript clean rev 3.pdf (2.86 MB)
Accepted version
Author(s)
Podgurschi, V
King, DJM
Smutna, J
Kermode, JR
Wenman, MR
Type
Journal Article
Abstract
In water reactors, iodine stress corrosion cracking is considered the cause of pellet-cladding interaction failures, but the mechanism and chemistry are debated and the protective effect of oxygen is not understood. Density functional theory calculations were used to investigate the interaction of iodine and oxygen with bulk and surface Zr under applied hydrostatic strain (2% to +3%) to simulate crack tip conditions in Zr to ZrO, using a variety of intermediate suboxides (ZrO, ZrO, ZrO and ZrO). The formation energy of an iodine octahedral interstitial in Zr was found to decrease with increasing hydrostatic strain, whilst the energy of an iodine substitutional defect was found to be relatively insensitive to strain. As the oxygen content increased, the formation energy of an iodine interstitial increased from 1.03 eV to 8.61 eV supporting the idea that oxygen has a protective effect. At the same time, a +3% tensile hydrostatic strain caused the iodine interstitial formation energy to decrease more in structures with higher oxygen content: 4.56 eV decrease in ZrO compared to 1.47 eV decrease for pure Zr. Comparison of the substitutional and interstitial energies of iodine, to the adsorption energy of iodine, in the presence of oxygen, shows the substitutional energy of iodine onto a Zr site is more favourable for all strains and even interstitial iodine is favourable between strains of +1-5%. Although substitutional defects are preferred to octahedral interstitial defects, in the ordered suboxides, a 3% tensile strain significantly narrows the energy gap and higher strains could cause interstitial defects to form.
Date Issued
2022-01-01
Date Acceptance
2021-11-04
Citation
Journal of Nuclear Materials, 2022, 558, pp.1-10
ISSN
0022-3115
Publisher
Elsevier
Start Page
1
End Page
10
Journal / Book Title
Journal of Nuclear Materials
Volume
558
Copyright Statement
© 2021 Elsevier B.V. All rights reserved.
Sponsor
Rolls-Royce Plc
Engineering & Physical Science Research Council (E
Identifier
http://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcApp=PARTNER_APP&SrcAuth=LinksAMR&KeyUT=WOS:000725051900001&DestLinkType=FullRecord&DestApp=ALL_WOS&UsrCustomerID=1ba7043ffcc86c417c072aa74d649202
Grant Number
6000-00298281
PO 2073974
Subjects
Science & Technology
Technology
Materials Science, Multidisciplinary
Nuclear Science & Technology
Materials Science
Zirconium
Iodine
Oxygen
Iodine stress corrosion cracking
Atomistic modelling studies
Corrosion
Effects of strain
STRESS-CORROSION CRACKING
POPULATION ANALYSIS
1ST PRINCIPLES
DIFFUSION
ZIRCALOY-4
OXIDATION
SURFACES
Publication Status
Published online
Article Number
ARTN 153394
Date Publish Online
2021-11-16