Long-Term Oxidation of Zirconium Alloy in Simulated Nuclear Reactor Primary Coolant—Experiments and Modeling

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creativework.keywordscompressive stress, electrochemical impedance spectroscopy, ionic space charge, nuclear reactor primary coolant, oxidation model, zirconium alloy
creativework.publisherMDPIen
dc.contributor.authorBetova I.
dc.contributor.authorBojinov M.
dc.contributor.authorKarastoyanov V.
dc.date.accessioned2024-07-10T14:27:05Z
dc.date.accessioned2024-07-10T14:50:38Z
dc.date.available2024-07-10T14:27:05Z
dc.date.available2024-07-10T14:50:38Z
dc.date.issued2023-04-01
dc.description.abstractOxidation of Zr-1%Nb fuel cladding alloy in simulated primary coolant of a pressurized water nuclear reactor is followed by in-situ electrochemical impedance spectroscopy. In-depth composition and thickness of the oxide are estimated by ex-situ analytical techniques. A kinetic model of the oxidation process featuring interfacial reactions of metal oxidation and water reduction, as well as electron and ion transport through the oxide governed by diffusion-migration, is parameterized by quantitative comparison to impedance data. The effects of compressive stress on diffusion and ionic space charge on migration of ionic point defects are introduced to rationalize the dependence of transport parameters on thickness (or oxidation time). The influence of ex-situ and in-situ hydrogen charging on kinetic and transport parameters is also studied.
dc.identifier.doi10.3390/ma16072577
dc.identifier.issn1996-1944
dc.identifier.scopusSCOPUS_ID:85152712121en
dc.identifier.urihttps://rlib.uctm.edu/handle/123456789/821
dc.language.isoen
dc.source.urihttps://www.scopus.com/inward/record.uri?partnerID=HzOxMe3b&scp=85152712121&origin=inward
dc.titleLong-Term Oxidation of Zirconium Alloy in Simulated Nuclear Reactor Primary Coolant—Experiments and Modeling
dc.typeArticle
oaire.citation.issue7
oaire.citation.volume16
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