Preliminary numerical analysis of the flow distribution in the core of a research reactor

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dc.contributor.authorSCURO, NIKOLAS L.pt_BR
dc.contributor.authorANGELO, GABRIELpt_BR
dc.contributor.authorANGELO, E.pt_BR
dc.contributor.authorTORRES, WALMIR M.pt_BR
dc.contributor.authorUMBEHAUN, PEDRO E.pt_BR
dc.contributor.authorANDRADE, DELVONEI A. dept_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2020-01-15T19:05:00Z
dc.date.available2020-01-15T19:05:00Z
dc.date.eventoOctober 21-25, 2019pt_BR
dc.description.abstractThe thermal-hydraulic safety analysis of research reactors establishes the safety criteria to ensure the integrity of the fuel elements in the reactor core. It assures that all core components are being adequately cooled during operation. It is necessary to know if the average mass flow rate (and their standard deviation) among the fuel assemblies are enough to cool the power generated during operation. Once satisfied such condition, it allows the calculation of the maximum heat flux transferred from fuel assemblies to the coolant, and if the maximum cladding temperatures are below the limits set by the safety criteria. Among the objectives, this study presents a methodology for a preliminary three-dimensional numerical analysis of the flow distribution in the core of the IEA-R1 research reactor, under steady state condition. For this, the ANSYS-CFX® commercial code was used to analyze the flow dynamics in the core, and to visualize the velocity field. It was possible to conclude that a homogeneous flow distribution for all standard fuel assemblies were found, with 2.7% deviation from the average mass flow. What turned out to be negligible and can be assumed that there is a homogeneous distribution in the core. Complex structures were find in the computational domain. Once known the core flow dynamics, it allows future studies to determine whether the heat flux and temperature conditions abbeys thermal-hydraulic safety criteria.pt_BR
dc.event.siglaINACpt_BR
dc.format.extent5667-5674pt_BR
dc.identifier.citationSCURO, NIKOLAS L.; ANGELO, GABRIEL; ANGELO, E.; TORRES, WALMIR M.; UMBEHAUN, PEDRO E.; ANDRADE, DELVONEI A. de. Preliminary numerical analysis of the flow distribution in the core of a research reactor. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. <b>Proceedings...</b> Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5667-5674. Disponível em: http://repositorio.ipen.br/handle/123456789/30732.
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.urihttp://repositorio.ipen.br/handle/123456789/30732
dc.localRio de Janeiropt_BR
dc.local.eventoSantos, SPpt_BR
dc.publisherAssociação Brasileira de Energia Nuclear
dc.rightsopenAccesspt_BR
dc.subjectboundary conditions
dc.subjectc codes
dc.subjectflow models
dc.subjectfuel assemblies
dc.subjectiear-1 reactor
dc.subjectnumerical analysis
dc.subjectreactor cores
dc.subjectresearch reactors
dc.subjectsafety
dc.subjectsteady-state conditions
dc.subjectthermal hydraulics
dc.titlePreliminary numerical analysis of the flow distribution in the core of a research reactorpt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorGABRIEL ANGELO
ipen.autorDELVONEI ALVES DE ANDRADE
ipen.autorPEDRO ERNESTO UMBEHAUN
ipen.autorWALMIR MAXIMO TORRES
ipen.autorNIKOLAS LYMBERIS SCURO
ipen.codigoautor8770
ipen.codigoautor1258
ipen.codigoautor754
ipen.codigoautor188
ipen.codigoautor14552
ipen.contributor.ipenauthorGABRIEL ANGELO
ipen.contributor.ipenauthorDELVONEI ALVES DE ANDRADE
ipen.contributor.ipenauthorPEDRO ERNESTO UMBEHAUN
ipen.contributor.ipenauthorWALMIR MAXIMO TORRES
ipen.contributor.ipenauthorNIKOLAS LYMBERIS SCURO
ipen.date.recebimento20-01
ipen.event.datapadronizada2019pt_BR
ipen.identifier.ipendoc26385pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
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relation.isAuthorOfPublicationc1502b5a-764f-4f7b-bae0-b04b2a264aae
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relation.isAuthorOfPublication21cc9120-e6dd-4e0d-8a42-6fe0737cada6
relation.isAuthorOfPublication.latestForDiscovery21cc9120-e6dd-4e0d-8a42-6fe0737cada6
sigepi.autor.atividadeANDRADE, DELVONEI A. de:1258:420:Npt_BR
sigepi.autor.atividadeUMBEHAUN, PEDRO E.:754:420:Npt_BR
sigepi.autor.atividadeTORRES, WALMIR M.:188:450:Npt_BR
sigepi.autor.atividadeANGELO, GABRIEL:8770:-1:Npt_BR
sigepi.autor.atividadeSCURO, NIKOLAS L.:14552:420:Spt_BR
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