Nuclear fuel safety threshold determined by logistic regression plus uncertainty

dc.contributor.authorGOMES, D.S.
dc.contributor.authorSILVA, A.T.
dc.coverageInternacionalpt_BR
dc.date.accessioned2018-07-05T18:24:25Z
dc.date.available2018-07-05T18:24:25Z
dc.date.issued2017pt_BR
dc.description.abstractAnalysis of the uncertainty quantification related to nuclear safety margins applied to the nuclear reactor is an important concept to prevent future radioactive accidents. The nuclear fuel performance code may involve the tolerance level determined by traditional deterministic models producing acceptable results at burn cycles under 62 GWd/MTU. The behavior of nuclear fuel can simulate applying a series of material properties under irradiation and physics models to calculate the safety limits. In this study, theoretical predictions of nuclear fuel failure under transient conditions investigate extended radiation cycles at 75 GWd/MTU, considering the behavior of fuel rods in light-water reactors under reactivity accident conditions. The fuel pellet can melt due to the quick increase of reactivity during a transient. Large power excursions in the reactor are the subject of interest bringing to a treatment that is known as the Fuchs-Hansen model. The point kinetic neutron equations show similar characteristics of non-linear differential equations. In this investigation, the multivariate logistic regression is employed to a probabilistic forecast of fuel failure. A comparison of computational simulation and experimental results was acceptable. The experiments carried out use the pre-irradiated fuels rods subjected to a rapid energy pulse which exhibits the same behavior during a nuclear accident. The propagation of uncertainty utilizes the Wilk's formulation. The variables chosen as essential to failure prediction were the fuel burnup, the applied peak power, the pulse width, the oxidation layer thickness, and the cladding type.pt_BR
dc.format.extent622-628pt_BR
dc.identifier.citationGOMES, D.S.; SILVA, A.T. Nuclear fuel safety threshold determined by logistic regression plus uncertainty. <b>World Academy of Science, Engineering and Technology</b>, v. 11, n. 3, p. 622-628, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28904.
dc.identifier.fasciculo3pt_BR
dc.identifier.issn2010-376Xpt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-7308-5784
dc.identifier.orcidhttps://orcid.org/0000-0002-2181-8704
dc.identifier.percentilfiSem Percentilen
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/28904
dc.identifier.vol11pt_BR
dc.relation.ispartofWorld Academy of Science, Engineering and Technologypt_BR
dc.rightsopenAccesspt_BR
dc.subjectnuclear fuels
dc.subjectsafety
dc.subjectradiation protection
dc.subjectregression analysis
dc.subjectreactor accidents
dc.subjectfuel rods
dc.subjectfailures
dc.subjectsafety margins
dc.titleNuclear fuel safety threshold determined by logistic regression plus uncertaintypt_BR
dc.typeArtigo de periódicopt_BR
dspace.entity.typePublication
ipen.autorANTONIO TEIXEIRA E SILVA
ipen.autorDANIEL DE SOUZA GOMES
ipen.codigoautor1085
ipen.codigoautor7670
ipen.contributor.ipenauthorANTONIO TEIXEIRA E SILVA
ipen.contributor.ipenauthorDANIEL DE SOUZA GOMES
ipen.date.recebimento18-07pt_BR
ipen.identifier.fiSem F.I.pt_BR
ipen.identifier.ipendoc24688pt_BR
ipen.observacoesArtigo possui mais dois títulos de periódico: International Journal of Aerospace and Mechanical Engineering; e International Scholarly and Scientific Research & Innovationpt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublication76359599-f842-443b-ab16-8a7caaac1bac
relation.isAuthorOfPublication090e1d1e-dfb3-4120-8d6f-1374e82feb2b
relation.isAuthorOfPublication.latestForDiscovery090e1d1e-dfb3-4120-8d6f-1374e82feb2b
sigepi.autor.atividadeGOMES, D.S.:7670:420:Npt_BR
sigepi.autor.atividadeSILVA, A.T.:1085:420:Npt_BR

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