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Microstructure degradation of austenitic stainless steels after 45 years of operation as VVER-440 reactor internals

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dc.contributor.authorFedotova, S. V.
dc.contributor.authorGurovich, B. A.
dc.contributor.authorFrolov, A. S.
dc.contributor.authorMaltsev, D. A.
dc.contributor.authorKuleshova, E. A.
dc.contributor.authorКулешова, Евгения Анатольевна
dc.date.accessioned2024-11-25T17:23:41Z
dc.date.available2024-11-25T17:23:41Z
dc.date.issued2020
dc.description.abstract© 2020 Elsevier B.V.Specimens of reactor vessel internals (RVI) made of 18Cr–10Ni–Ti steel from the decommissioned VVER-440 unit after 45 years of operation were investigated. The aim was to assess the structure degradation degree responsible for the properties changes of RVI components. Radiation-induced structural elements of RVI baffle, former, and flux thimble specimens with the damaging dose 7.9–43.0 dpa and irradiation temperature 280–315 °C were studied using TEM, SEM, and APT methods. TEM-studies showed the negligible swelling under these conditions with a slight increase of radiation swelling due to the formation of the low-density large void population in case of higher temperature irradiation. APT-studies revealed the formation of the high-density Ni–Si-rich clusters (presumably G- and γ′- phase precursors) and an increase of its volume fraction with the temperature increase. The Orowan equation was used to assess the hardening contribution of different radiation-induced structural elements. The observed yield strength increase is insignificant under the studied conditions.
dc.identifier.citationMicrostructure degradation of austenitic stainless steels after 45 years of operation as VVER-440 reactor internals / Fedotova, S.V. [et al.] // Journal of Nuclear Materials. - 2020. - 533. - 10.1016/j.jnucmat.2020.152124
dc.identifier.doi10.1016/j.jnucmat.2020.152124
dc.identifier.urihttps://www.doi.org/10.1016/j.jnucmat.2020.152124
dc.identifier.urihttps://www.scopus.com/record/display.uri?eid=2-s2.0-85082167668&origin=resultslist
dc.identifier.urihttp://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=Alerting&SrcApp=Alerting&DestApp=WOS_CPL&DestLinkType=FullRecord&UT=WOS:000529937700041
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/20465
dc.relation.ispartofJournal of Nuclear Materials
dc.titleMicrostructure degradation of austenitic stainless steels after 45 years of operation as VVER-440 reactor internals
dc.typeArticle
dspace.entity.typePublication
oaire.citation.volume533
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relation.isAuthorOfPublication.latestForDiscovery2704f298-c30b-4066-935e-d8bb478560c3
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