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Experimental Modeling of Technetium(VII) Recovery from Raffinates after Extractive Reprocessing of Spent Nuclear Fuel

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dc.contributor.authorSafiulina, A. M.
dc.contributor.authorLizunov, A. V.
dc.contributor.authorLogunov, M. V.
dc.contributor.authorDvoeglazov, K. N.
dc.contributor.authorAnan'ev, A. V.
dc.contributor.authorTuiza, M.
dc.date.accessioned2024-11-27T10:49:53Z
dc.date.available2024-11-27T10:49:53Z
dc.date.issued2020
dc.description.abstract© 2020, Pleiades Publishing, Ltd.Abstract: Experimental justification has been provided for the possibility of extractive isolation of technetium from raffinate of technical process of affinage of uranium–plutonium product resulting from hydrometallurgical reprocessing of spent nuclear fuel (SNF). Technetium (VII) from aqueous solution of Zr(IV) (10 g/L) and 4 mol/L HNO3 with small content of ZrOb+ and Zr2O3b+ oxocations is recovered by 80% in 30% TBP in hydrocarbon diluent over seven stages of counter-current continuous cascade at ratio O : A = 1 : 1. Variation in phase flow ratio for cascade part leads to virtually complete Tc(VII) extraction in organic phase over ten stages. Technetium(VII) is selectively back extracted from loaded organic phase with water virtually completely over eleven stages of counter-current continuous cascade. Technological extraction scheme for technetium isolation from SNF solutions has been proposed.
dc.format.extentС. 1928-1934
dc.identifier.citationExperimental Modeling of Technetium(VII) Recovery from Raffinates after Extractive Reprocessing of Spent Nuclear Fuel / Safiulina, A.M. [et al.] // Russian Journal of Inorganic Chemistry. - 2020. - 65. - № 12. - P. 1928-1934. - 10.1134/S0036023620120141
dc.identifier.doi10.1134/S0036023620120141
dc.identifier.urihttps://www.doi.org/10.1134/S0036023620120141
dc.identifier.urihttps://www.scopus.com/record/display.uri?eid=2-s2.0-85097592959&origin=resultslist
dc.identifier.urihttp://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=Alerting&SrcApp=Alerting&DestApp=WOS_CPL&DestLinkType=FullRecord&UT=WOS:000599170100015
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/22700
dc.relation.ispartofRussian Journal of Inorganic Chemistry
dc.titleExperimental Modeling of Technetium(VII) Recovery from Raffinates after Extractive Reprocessing of Spent Nuclear Fuel
dc.typeArticle
dspace.entity.typePublication
oaire.citation.issue12
oaire.citation.volume65
relation.isOrgUnitOfPublicationba0b4738-e6bd-4285-bda5-16ab2240dbd1
relation.isOrgUnitOfPublication.latestForDiscoveryba0b4738-e6bd-4285-bda5-16ab2240dbd1
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