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Determination of 232U and 236Pu Weight Contents of Spent Nuclear Fuel

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dc.contributor.authorErin, E. A.
dc.contributor.authorVolkov, A. Y.
dc.contributor.authorMomotov, V. N.
dc.contributor.authorBaranov, A. Y.
dc.date.accessioned2024-11-25T17:25:42Z
dc.date.available2024-11-25T17:25:42Z
dc.date.issued2020
dc.description.abstract© 2020, Pleiades Publishing, Inc.A procedure has been developed for the determination of 232U and 236Pu content by alpha spectrometry by ion-exchange isolation and purification of uranium and plutonium fractions from irradiated fuel solution. The proposed procedure has been utilized to determine weight concentrations of 232U and 236Pu in samples of uranium oxide fuel irradiated in VVER-1000 and RBMK-1000 reactors, as well as in mixed uranium-plutonium nitride fuel irradiated in a BN-600 reactor.
dc.format.extentС. 95-100
dc.identifier.citationDetermination of 232U and 236Pu Weight Contents of Spent Nuclear Fuel / Erin, E.A. [et al.] // Radiochemistry. - 2020. - 62. - № 1. - P. 95-100. - 10.1134/S1066362220010129
dc.identifier.doi10.1134/S1066362220010129
dc.identifier.urihttps://www.doi.org/10.1134/S1066362220010129
dc.identifier.urihttps://www.scopus.com/record/display.uri?eid=2-s2.0-85082519817&origin=resultslist
dc.identifier.urihttp://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=Alerting&SrcApp=Alerting&DestApp=WOS_CPL&DestLinkType=FullRecord&UT=WOS:000521154600012
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/20471
dc.relation.ispartofRadiochemistry
dc.titleDetermination of 232U and 236Pu Weight Contents of Spent Nuclear Fuel
dc.typeArticle
dspace.entity.typePublication
oaire.citation.issue1
oaire.citation.volume62
relation.isOrgUnitOfPublication9ee05942-b1d9-4513-a450-ef7a8d2894af
relation.isOrgUnitOfPublication.latestForDiscovery9ee05942-b1d9-4513-a450-ef7a8d2894af
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