1. Repositório Institucional da UFMG
  2. Publicações Científicas e Culturais
  3. Artigo de Periódico
Please use this identifier to cite or link to this item: http://hdl.handle.net/1843/56885
Full metadata record
DC FieldValueLanguage
dc.creatorClarysson Alberto Mello da Silvapt_BR
dc.creatorCarlos Eduardo Velasquez Cabrerapt_BR
dc.creatorMichel Cleberson Bernardo de Almeidapt_BR
dc.creatorRochkhudon Batista de Fariapt_BR
dc.creatorClaubia Pereira Bezerra Limapt_BR
dc.date.accessioned2023-07-24T19:16:28Z-
dc.date.available2023-07-24T19:16:28Z-
dc.date.issued2020-
dc.citation.volume8pt_BR
dc.citation.issue3pt_BR
dc.citation.spage1pt_BR
dc.citation.epage22pt_BR
dc.identifier.doihttps://doi.org/10.15392/bjrs.v8i3.1219pt_BR
dc.identifier.issn2319-0612pt_BR
dc.identifier.urihttp://hdl.handle.net/1843/56885-
dc.description.resumoThe spent fuel from a PWR still contains some amount of fissile materials depending on their initial enrichment and the burnup. Thus, spent fuel from PWRs containing about 1.5% of fissile material could be used as fuel for CANDU reactors after some fission products are removed from it. Thus, an important proposal is the DUPIC cycle, where spent fuels from a PWR are packaged into a CANDU fuel bundle using mechanical reprocessing but without the need of chemical reprocessing. When it is refueled with reprocessed fuel, the reactivity of the system increases, and this behavior may affect the safety parameters of the reactor. Therefore, this work studies the neutronic parameters of two reprocessing fuel techniques: AIROX and OREOX, which are evaluated for two different cores configuration. The first one considers heavy water as a moderator and coolant. The second one considers heavy water and light water as moderator and coolant, respectively. These studies evaluate the core behavior based on the different number of reprocessed fuels channels and compare them with the reference core. To perform the simulation, MCNPX was used to calculate the effective multiplication factor, void reactivity coefficient, and neutron flux, which were evaluated at steady state condition for the different cases. The results show that the presence of parasitic absorbers in the reprocessed fuels hardens the neutron spectrum. This behavior provokes an increase in the core reactivity, and in the void reactivity coefficient. Among these parameters, the use of light water reduces the core reactivity but does not improve the void reactivity coefficient.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.ispartofBrazilian Journal of Radiation Sciencespt_BR
dc.rightsAcesso Abertopt_BR
dc.subjectCANDU reactorpt_BR
dc.subjectDUPIC cyclept_BR
dc.subjectAIROXpt_BR
dc.subjectOREOXpt_BR
dc.subjectMCNPX 2.6.0pt_BR
dc.subject.otherReatores nuclearespt_BR
dc.titleNeutronic evaluation of candu-6 core using reprocessed fuelspt_BR
dc.typeArtigo de Periódicopt_BR
dc.url.externahttps://www.bjrs.org.br/revista/index.php/REVISTA/article/view/1219pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-3082-644Xpt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-2960-3150pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0003-0198-6249pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0003-0264-9148pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0001-5999-9961pt_BR
Appears in Collections:Artigo de Periódico

Files in This Item:
File Description SizeFormat 
Neutronic evaluation of CANDU-6 core using reprocessed fuels.pdf715.1 kBAdobe PDFView/Open
Show simple item record


Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.