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dc.contributor.authorGalashev, A. Y.en
dc.date.accessioned2024-04-22T15:53:18Z-
dc.date.available2024-04-22T15:53:18Z-
dc.date.issued2022-
dc.identifier.citationGalashev, AY 2022, 'Recovery of actinides and fission products from spent nuclear fuel via electrolytic reduction: Thematic overview', International Journal of Energy Research, Том. 46, № 4, стр. 3891-3905. https://doi.org/10.1002/er.7458harvard_pure
dc.identifier.citationGalashev, A. Y. (2022). Recovery of actinides and fission products from spent nuclear fuel via electrolytic reduction: Thematic overview. International Journal of Energy Research, 46(4), 3891-3905. https://doi.org/10.1002/er.7458apa_pure
dc.identifier.issn0363-907X
dc.identifier.otherFinal2
dc.identifier.otherAll Open Access; Bronze Open Access3
dc.identifier.otherhttps://doi.org/10.1002/er.74581
dc.identifier.otherhttps://doi.org/10.1002/er.7458pdf
dc.identifier.urihttp://elar.urfu.ru/handle/10995/132419-
dc.description.abstractSpent nuclear fuel (SNF) from modern light water or thermal reactors containing uranium oxide with small concentrations of plutonium and other actinide oxides is converted into metal by the electrolytic reduction. The obtained metal must be subjected to further processing (electrorefining). This review reflects the achievements in development SNF electrolytic processing, concepts of the technological operations, and a model describing the electrochemical process. The technological scheme for the electrochemical reduction of SNF and MOX fuel is considered. The complexity of a carbon anode application in the process of UO2 electrolytic reduction is reflected. The reduction processes of alkali, alkaline earth (AE), and rare earth metal oxides as well as oxide compounds of zirconium are demonstrated. The reduction of lanthanum oxide and oxy-chloride to the metallic form by adding metallic nickel to the molten salt is discussed. The solubility of Li2O in molten salts is interpreted depending on the amount of dissolved alkali and AE metal chlorides. The considered pyroprocessing technology enables a much greater release of the energy accumulated in uranium ore, and recycling all actinides allows reducing significantly the amount of nuclear waste and the time it must be isolated. © 2021 John Wiley & Sons Ltd.en
dc.description.sponsorshipState Atomic Energy Corporation ROSATOM, ROSATOMen
dc.description.sponsorshipThis work was supported by the State Atomic Energy Corporation Rosatom (Government agreement number H.4o.241.19.21.1070 dated 16 April 2021 «Development of the technology and facility for the pyrochemical reprocessing of the spent nuclear fuel of the fast neutron reactors. 2021 stage»).en
dc.format.mimetypeapplication/pdfen
dc.language.isoenen
dc.publisherJohn Wiley and Sons Ltden
dc.rightsinfo:eu-repo/semantics/openAccessen
dc.rightscc-byother
dc.sourceInternational Journal of Energy Research2
dc.sourceInternational Journal of Energy Researchen
dc.subjectACTINIDEen
dc.subjectFISSION PRODUCTSen
dc.subjectPLUTONIUMen
dc.subjectSALT MELTen
dc.subjectSPENT NUCLEAR FUELen
dc.subjectURANIUMen
dc.subjectCHLORINE COMPOUNDSen
dc.subjectELECTROLYTIC REDUCTIONen
dc.subjectFUSED SALTSen
dc.subjectLIGHT WATER REACTORSen
dc.subjectLITHIUM COMPOUNDSen
dc.subjectMETALSen
dc.subjectMOLTEN SALT REACTORen
dc.subjectNUCLEAR FUEL REPROCESSINGen
dc.subjectORESen
dc.subjectRARE EARTHSen
dc.subjectURANIUM DIOXIDEen
dc.subjectACTINIDE OXIDESen
dc.subjectELECTROREFININGen
dc.subjectLIGHT WATERen
dc.subjectMOLTEN SALTen
dc.subjectSALT MELTen
dc.subjectSMALL CONCENTRATIONen
dc.subjectSPENT NUCLEAR FUELSen
dc.subjectTHERMAL REACTORSen
dc.subjectURANIAen
dc.subjectWATER REACTORSen
dc.subjectFISSION PRODUCTSen
dc.titleRecovery of actinides and fission products from spent nuclear fuel via electrolytic reduction: Thematic overviewen
dc.typeReviewen
dc.typeinfo:eu-repo/semantics/reviewen
dc.typeinfo:eu-repo/semantics/publishedVersionen
dc.identifier.rsi49798526-
dc.identifier.doi10.1002/er.7458-
dc.identifier.scopus85119977665-
local.contributor.employeeGalashev A.Y., Institute of High-Temperature Electrochemistry, Ural Branch, Russian Academy of Sciences, Yekaterinburg, Russian Federation, Ural Federal University (named after the first President of Russia B.N. Yeltsin), Yekaterinburg, Russian Federationen
local.description.firstpage3891
local.description.lastpage3905
local.issue4
local.volume46
dc.identifier.wos000722746700001-
local.contributor.departmentInstitute of High-Temperature Electrochemistry, Ural Branch, Russian Academy of Sciences, Yekaterinburg, Russian Federationen
local.contributor.departmentUral Federal University (named after the first President of Russia B.N. Yeltsin), Yekaterinburg, Russian Federationen
local.identifier.pureea26875b-44e9-4b0a-b8d5-b814422da9a3uuid
local.identifier.pure29827292-
local.identifier.eid2-s2.0-85119977665-
local.identifier.wosWOS:000722746700001-
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