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Please use this identifier to cite or link to this item: http://hdl.handle.net/1843/56849
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dc.creatorJean Anderson Dias Salomépt_BR
dc.creatorFabiano Cardoso da Silvapt_BR
dc.creatorCarlos Eduardo Velasquez Cabrerapt_BR
dc.creatorFernando Pereira Fariapt_BR
dc.creatorGraiciany de Paula Barrospt_BR
dc.creatorClaubia Pereira Bezerra Limapt_BR
dc.date.accessioned2023-07-21T17:46:15Z-
dc.date.available2023-07-21T17:46:15Z-
dc.date.issued2016-
dc.citation.issue5pt_BR
dc.citation.spage255pt_BR
dc.citation.epage262pt_BR
dc.identifier.doihttps://doi.org/10.1016/j.proche.2016.10.036pt_BR
dc.identifier.issn1876-6196pt_BR
dc.identifier.urihttp://hdl.handle.net/1843/56849-
dc.description.resumoThe aim of this study is to analyze and compare the discharged-spent fuel of three types of nuclear systems: a Very High-Temperature Gas Reactor (VHTR), a lead-cooled Accelerator-Driven System (ADS) and a standard Pressurized Water Reactor (PWR). The two first systems, VHTR, and ADS were designed to use reprocessed fuels. UREX+ and GANEX techniques were used for the reprocessing processes respectively. The fuel burnup simulated for the systems in other works have been used to obtain the final composition of the spent fuel discharged. After discharge, the radioactivity, the radiotoxicity, and the decay heat were evaluated through the ORIGEN 2.1 code until 107 years and compared to the literature.pt_BR
dc.languageporpt_BR
dc.publisherUniversidade Federal de Minas Geraispt_BR
dc.publisher.countryBrasilpt_BR
dc.publisher.departmentENG - DEPARTAMENTO DE ENGENHARIA NUCLEARpt_BR
dc.publisher.initialsUFMGpt_BR
dc.relation.ispartofInternational atalante conference on nuclear chemistry for sustainable fuel cyclespt_BR
dc.rightsAcesso Abertopt_BR
dc.subjectReactors VHTRpt_BR
dc.subjectADSpt_BR
dc.subjectPWRpt_BR
dc.subjectReprocessing fuelpt_BR
dc.subjectNuclear fuel cyclept_BR
dc.subjectSCALE 6.0pt_BR
dc.subjectMONTEBURNS and ORIGEN 2.1pt_BR
dc.subject.otherCombustivelpt_BR
dc.subject.otherReatores nuclearespt_BR
dc.titleVHTR, ADS, and PWR Spent Nuclear Fuel Analysispt_BR
dc.typeArtigo de Eventopt_BR
dc.url.externahttps://www.sciencedirect.com/science/article/pii/S187661961630078X?via%3Dihubpt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-2960-3150pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0001-7909-9063pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0001-5999-9961pt_BR
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