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Degradation of Fuel Cladding Materials Based on Zirconium after Operation in VVER-Type Reactors

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dc.contributor.authorFrolov, A. S.
dc.contributor.authorGurovich, B. A.
dc.contributor.authorMaltsev, D. A.
dc.contributor.authorSafonov, D. V.
dc.contributor.authorKuleshova, E. A.
dc.contributor.authorКулешова, Евгения Анатольевна
dc.date.accessioned2024-11-21T15:11:44Z
dc.date.available2024-11-21T15:11:44Z
dc.date.issued2019
dc.description.abstract© 2019, Pleiades Publishing, Ltd.Abstract: The paper presents microstructural studies of specimens cut from fuel elements made of E110 spongy zirconium-based alloy after operation in a VVER-1000 before reaching the burnup of ~35 MWd/kg U. As a result of exposure to high temperatures and neutron irradiation, significant changes in the phase composition of fuel cladding materials appear: change in the size, density, and composition of β-Nb particles; change in the composition of the Laves phase; formation of dislocation loops of α type, as well as δ and γ hydrides. The main structural elements determining the degradation of the mechanical properties of the E110 alloy under irradiation are dislocation loops and fine-phase precipitates owing to their relatively large density. The data obtained can be used to construct dose dependences of microstructural changes with the aim of predicting the residual life of claddings and fuel assemblies as a whole.
dc.format.extentС. 1461-1470
dc.identifier.citationDegradation of Fuel Cladding Materials Based on Zirconium after Operation in VVER-Type Reactors / Frolov, A.S. [et al.] // Inorganic Materials: Applied Research. - 2019. - 10. - № 6. - P. 1461-1470. - 10.1134/S2075113319060091
dc.identifier.doi10.1134/S2075113319060091
dc.identifier.urihttps://www.doi.org/10.1134/S2075113319060091
dc.identifier.urihttps://www.scopus.com/record/display.uri?eid=2-s2.0-85075941666&origin=resultslist
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/18982
dc.relation.ispartofInorganic Materials: Applied Research
dc.titleDegradation of Fuel Cladding Materials Based on Zirconium after Operation in VVER-Type Reactors
dc.typeArticle
dspace.entity.typePublication
oaire.citation.issue6
oaire.citation.volume10
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relation.isAuthorOfPublication.latestForDiscovery2704f298-c30b-4066-935e-d8bb478560c3
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