Crystal structure of the zro phase at zirconium/zirconium oxide interfaces
Zirconium-based alloys are used in water-cooled nuclear reactors for both nuclear fuel cladding and structural components. Under this harsh environment, the main factor limiting the service life of zirconium cladding, and hence fuel burn-up efficiency, is water corrosion. This oxidation process has...
Main Authors: | , , , , , , , , |
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Format: | Journal article |
Language: | English |
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Wiley-VCH
2015
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_version_ | 1797057386450518016 |
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author | Nicholls, R Ni, N Lozano-Perez, S London, A Mccomb, D Nellist, P Grovenor, C Pickard, C Yates, JR |
author_facet | Nicholls, R Ni, N Lozano-Perez, S London, A Mccomb, D Nellist, P Grovenor, C Pickard, C Yates, JR |
author_sort | Nicholls, R |
collection | OXFORD |
description | Zirconium-based alloys are used in water-cooled nuclear reactors for both nuclear fuel cladding and structural components. Under this harsh environment, the main factor limiting the service life of zirconium cladding, and hence fuel burn-up efficiency, is water corrosion. This oxidation process has recently been linked to the presence of a sub-oxide phase with well-defined composition but unknown structure at the metal-oxide interface. In this paper, the combination of first-principles materials modeling and high-resolution electron microscopy is used to identify the structure of this sub-oxide phase, bringing us a step closer to developing strategies to mitigate aqueous oxidation in Zr alloys and prolong the operational lifetime of commercial fuel cladding alloys. © 2014 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim. |
first_indexed | 2024-03-06T19:35:35Z |
format | Journal article |
id | oxford-uuid:1ef04f97-4d4a-4585-9726-c7d90b5e37cf |
institution | University of Oxford |
language | English |
last_indexed | 2024-03-06T19:35:35Z |
publishDate | 2015 |
publisher | Wiley-VCH |
record_format | dspace |
spelling | oxford-uuid:1ef04f97-4d4a-4585-9726-c7d90b5e37cf2022-03-26T11:19:06ZCrystal structure of the zro phase at zirconium/zirconium oxide interfacesJournal articlehttp://purl.org/coar/resource_type/c_dcae04bcuuid:1ef04f97-4d4a-4585-9726-c7d90b5e37cfEnglishSymplectic Elements at OxfordWiley-VCH2015Nicholls, RNi, NLozano-Perez, SLondon, AMccomb, DNellist, PGrovenor, CPickard, CYates, JRZirconium-based alloys are used in water-cooled nuclear reactors for both nuclear fuel cladding and structural components. Under this harsh environment, the main factor limiting the service life of zirconium cladding, and hence fuel burn-up efficiency, is water corrosion. This oxidation process has recently been linked to the presence of a sub-oxide phase with well-defined composition but unknown structure at the metal-oxide interface. In this paper, the combination of first-principles materials modeling and high-resolution electron microscopy is used to identify the structure of this sub-oxide phase, bringing us a step closer to developing strategies to mitigate aqueous oxidation in Zr alloys and prolong the operational lifetime of commercial fuel cladding alloys. © 2014 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim. |
spellingShingle | Nicholls, R Ni, N Lozano-Perez, S London, A Mccomb, D Nellist, P Grovenor, C Pickard, C Yates, JR Crystal structure of the zro phase at zirconium/zirconium oxide interfaces |
title | Crystal structure of the zro phase at zirconium/zirconium oxide interfaces |
title_full | Crystal structure of the zro phase at zirconium/zirconium oxide interfaces |
title_fullStr | Crystal structure of the zro phase at zirconium/zirconium oxide interfaces |
title_full_unstemmed | Crystal structure of the zro phase at zirconium/zirconium oxide interfaces |
title_short | Crystal structure of the zro phase at zirconium/zirconium oxide interfaces |
title_sort | crystal structure of the zro phase at zirconium zirconium oxide interfaces |
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