Sensitivity assessment of fuel performance codes for loca accident scenario

dc.contributor.authorABE, ALFREDO
dc.contributor.authorGIOVEDI, CLAUDIA
dc.contributor.authorGOMES, DANIEL
dc.contributor.authorSILVA, ANTONIO T. e
dc.contributor.authorMUNIZ, RAFAEL O.R.
dc.contributor.authorMARTINS, MARCELO
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2018-01-02T17:52:00Z
dc.date.available2018-01-02T17:52:00Z
dc.date.eventoOctober 22-27, 2017pt_BR
dc.description.abstractFRAPCON code predicts fuel rod performance in LWR (Light Water Reactor) by modeling fuel responses under normal operating conditions and anticipated operational occurrences; FRAPTRAN code is applied for fuel transient under fast transient and accident conditions. The codes are well known and applied for different purposes and one of the use is to address sensitivity analysis considering fuel design parameters associated to fabrication, moreover can address the effect of physical models bias. The objective of this work was to perform an assessment of fuel manufacturing parameters tolerances and fuel models bias using FRAPCON and FRAPTRAN codes for Loss of Coolant Accident (LOCA) scenario. The preliminary analysis considered direct approach taken into account most relevant manufacturing tolerances (lower and upper bounds) related to design parameters and physical models bias without considering their statistical distribution. The simulations were carried out using the data available in the open literature related to the series of LOCA experiment performed at the Halden reactor (specifically IFA-650.5). The manufacturing tolerances associated to design parameters considered in this paper were: enrichment, cladding thickness, pellet diameter, pellet density, and filling gas pressure. The physical models considered were: fuel thermal expansion, fission gas release, fuel swelling, irradiation creep, cladding thermal expansion, cladding corrosion, and cladding hydrogen pickup. The results obtained from sensitivity analysis addressed the impact of manufacturing tolerances and physical models in the fuel cladding burst time observed for the IFA-650.5 experiment.pt_BR
dc.event.siglaINACpt_BR
dc.identifier.citationABE, ALFREDO; GIOVEDI, CLAUDIA; GOMES, DANIEL; SILVA, ANTONIO T. e; MUNIZ, RAFAEL O.R.; MARTINS, MARCELO. Sensitivity assessment of fuel performance codes for loca accident scenario. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. <b>Proceedings...</b> Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28196.
dc.identifier.orcidhttps://orcid.org/0000-0002-2181-8704
dc.identifier.orcidhttps://orcid.org/0000-0002-7308-5784
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/28196
dc.localRio de Janeiro, RJpt_BR
dc.local.eventoBelo Horizonte, MGpt_BR
dc.publisherAssociação Brasileira de Energia Nuclearpt_BR
dc.rightsopenAccesspt_BR
dc.subjectaccident-tolerant nuclear fuels
dc.subjectcomputerized simulation
dc.subjectf codes
dc.subjectfuel rods
dc.subjectfuel-cladding interactions
dc.subjectloss of coolant
dc.subjectsensitivity analysis
dc.subjecttransients
dc.subjectwater cooled reactors
dc.titleSensitivity assessment of fuel performance codes for loca accident scenariopt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorDANIEL DE SOUZA GOMES
ipen.autorRAFAEL OLIVEIRA RONDOM MUNIZ
ipen.autorANTONIO TEIXEIRA E SILVA
ipen.autorALFREDO YUUITIRO ABE
ipen.codigoautor7670
ipen.codigoautor3487
ipen.codigoautor1085
ipen.codigoautor7817
ipen.contributor.ipenauthorDANIEL DE SOUZA GOMES
ipen.contributor.ipenauthorRAFAEL OLIVEIRA RONDOM MUNIZ
ipen.contributor.ipenauthorANTONIO TEIXEIRA E SILVA
ipen.contributor.ipenauthorALFREDO YUUITIRO ABE
ipen.date.recebimento18-01pt_BR
ipen.event.datapadronizada2017pt_BR
ipen.identifier.ipendoc24021pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublication090e1d1e-dfb3-4120-8d6f-1374e82feb2b
relation.isAuthorOfPublicationd7711d57-fb3f-43d2-9d03-a1b408954c9e
relation.isAuthorOfPublication76359599-f842-443b-ab16-8a7caaac1bac
relation.isAuthorOfPublicationc9a80ee8-65ff-498b-a96b-79044dd4e4eb
relation.isAuthorOfPublication.latestForDiscoveryc9a80ee8-65ff-498b-a96b-79044dd4e4eb
sigepi.autor.atividadeABE, ALFREDO:7817:-1:Spt_BR
sigepi.autor.atividadeGOMES, DANIEL:7670:420:Npt_BR
sigepi.autor.atividadeSILVA, ANTONIO T. E:1085:420:Npt_BR
sigepi.autor.atividadeMUNIZ, RAFAEL O.R.:3487:420:Npt_BR

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