A CFD analysis of blockage length on a partially blocked fuel rod

dc.contributor.authorSCURO, N.L.pt_BR
dc.contributor.authorUMBEHAUN, P.E.pt_BR
dc.contributor.authorANGELO, E.pt_BR
dc.contributor.authorANGELO, G.pt_BR
dc.contributor.authorANDRADE, D.A.pt_BR
dc.coverageNacionalpt_BR
dc.date.accessioned2019-11-28T12:20:19Z
dc.date.available2019-11-28T12:20:19Z
dc.date.issued2019pt_BR
dc.description.abstractAfter a loss of coolant accident (LOCA), fuel rods may balloon. The swelling can partially block the flow channel, affecting the coolability during reflood phase. In order to analyze the influence of blockage length, using a radial block-age of 90%, varying just the blockage length, many steady state numerical simulations has been done using Ansys-CFX code to verify thermal-hydraulic properties according to different forced cooled conditions. Temperature peaks are observed on cladding, followed by a temperature drop. A 5x5 fuel assembly, with 9 centered ballooned fuel rod, flow redistribution inside channels can also be captured, indicating an overheating zone. Therefore, this study conclude, for the same boundary conditions, the longer the blockage length originated after LOCA events, the higher are the clad temperatures, indicating the possibility of overheat during transient conditions on reflood.pt_BR
dc.format.extent1-20pt_BR
dc.identifier.citationSCURO, N.L.; UMBEHAUN, P.E.; ANGELO, E.; ANGELO, G.; ANDRADE, D.A. A CFD analysis of blockage length on a partially blocked fuel rod. <b>Brazilian Journal of Radiation Sciences</b>, v. 7, n. 2B, p. 1-20, 2019. DOI: <a href="https://dx.doi.org/10.15392/bjrs.v7i2B.437">10.15392/bjrs.v7i2B.437</a>. Disponível em: http://repositorio.ipen.br/handle/123456789/30369.
dc.identifier.doi10.15392/bjrs.v7i2B.437pt_BR
dc.identifier.fasciculo2Bpt_BR
dc.identifier.issn2319-0612pt_BR
dc.identifier.orcid0000-0002-6689-3011pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-6689-3011
dc.identifier.orcidhttps://orcid.org/0000-0002-2887-0759
dc.identifier.percentilfiSem Percentilpt_BR
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/30369
dc.identifier.vol7pt_BR
dc.relation.ispartofBrazilian Journal of Radiation Sciencespt_BR
dc.rightsopenAccesspt_BR
dc.sourceMeeting on Nuclear Reactor Physics and Thermal Hydraulics (ENFIR), 20th, 22-27 de outubro, 2017, Belo Horizonte, MGpt_BR
dc.subjectboundary conditions
dc.subjectcomputerized simulation
dc.subjectflow blockage
dc.subjectfluid mechanics
dc.subjectfuel rods
dc.subjectheat transfer
dc.subjectloss of coolant
dc.subjectnumerical analysis
dc.subjectsteady-state conditions
dc.subjectturbulence
dc.titleA CFD analysis of blockage length on a partially blocked fuel rodpt_BR
dc.typeArtigo de periódicopt_BR
dspace.entity.typePublication
ipen.autorGABRIEL ANGELO
ipen.autorDELVONEI ALVES DE ANDRADE
ipen.autorPEDRO ERNESTO UMBEHAUN
ipen.autorNIKOLAS LYMBERIS SCURO
ipen.codigoautor8770
ipen.codigoautor1258
ipen.codigoautor754
ipen.codigoautor14552
ipen.contributor.ipenauthorGABRIEL ANGELO
ipen.contributor.ipenauthorDELVONEI ALVES DE ANDRADE
ipen.contributor.ipenauthorPEDRO ERNESTO UMBEHAUN
ipen.contributor.ipenauthorNIKOLAS LYMBERIS SCURO
ipen.date.recebimento19-11
ipen.identifier.fiSem F.I.pt_BR
ipen.identifier.ipendoc26394pt_BR
ipen.identifier.iwosWoSpt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublication4f3518a7-495e-43cd-9167-91f53d064b30
relation.isAuthorOfPublication0eeb4436-68e5-4573-a603-35f5fc912178
relation.isAuthorOfPublicationc1502b5a-764f-4f7b-bae0-b04b2a264aae
relation.isAuthorOfPublication21cc9120-e6dd-4e0d-8a42-6fe0737cada6
relation.isAuthorOfPublication.latestForDiscovery21cc9120-e6dd-4e0d-8a42-6fe0737cada6
sigepi.autor.atividadeANDRADE, D.A.:1258:420:Npt_BR
sigepi.autor.atividadeANGELO, G.:8770:-1:Npt_BR
sigepi.autor.atividadeUMBEHAUN, P.E.:754:420:Npt_BR
sigepi.autor.atividadeSCURO, N.L.:14552:420:Spt_BR

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