Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation

dc.contributor.authorLIMA, LEONARDO S.pt_BR
dc.contributor.authorMELO, CAIOpt_BR
dc.contributor.authorFARIA, DANILO P.pt_BR
dc.contributor.authorBERRETA, JOSEpt_BR
dc.contributor.authorABATI, AMANDApt_BR
dc.contributor.authorGIOVEDI, CLAUDIApt_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2020-02-20T13:06:18Z
dc.date.available2020-02-20T13:06:18Z
dc.date.eventoOctober 21-25, 2019pt_BR
dc.description.abstractDuring operation of a Pressurized Water Reactor, the cladding of the fuel rod is subjected to various loads, such as: temperature, internal pressure, and external pressure which generate dimensional and geometric variations in the cladding tube. In the fuel rod, at the operating temperature, the internal pressure comes from the initial pre-pressurizing with Helium gas and the release of fission gases by the UO2 pellets during the irradiation. The external pressure is assumed to be the same as that of the coolant. In this paper, it was proposed the study of a mathematical model for computational simulation using the Finite Element Method to calculate and analyze the mechanical stresses acting on the internal and external surfaces of the fuel rod, adopting the normal operating condition, at 0 W of power. The boundary conditions, such as temperature and pressure profile, come from a modified version of a fuel performance code, considering as cladding material an iron-based alloy (austenitic stainless steel). The fuel rod was modeled and simulated using the Solidworks and ANSYS softwares, respectively. The values of the stresses acting on the cladding tube obtained by simulation were compared to the values obtained by analytical calculation. Then, it was checked the consistency of the adopted mathematical model, in order to ensure the reliability of the computational simulation as a tool to evaluate the stresses acting on the internal and external surfaces of the fuel rod under a PWR environment.pt_BR
dc.event.siglaINACpt_BR
dc.format.extent4950-4961pt_BR
dc.identifier.citationLIMA, LEONARDO S.; MELO, CAIO; FARIA, DANILO P.; BERRETA, JOSE; ABATI, AMANDA; GIOVEDI, CLAUDIA. Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. <b>Proceedings...</b> Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 4950-4961. Disponível em: http://repositorio.ipen.br/handle/123456789/30813.
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/30813
dc.localRio de Janeiropt_BR
dc.local.eventoSantos, SPpt_BR
dc.publisherAssociação Brasileira de Energia Nuclear
dc.rightsopenAccesspt_BR
dc.subjecta codes
dc.subjectaustenitic steels
dc.subjectboundary conditions
dc.subjectcladding
dc.subjectcomputerized simulation
dc.subjectfinite element method
dc.subjectfuel rods
dc.subjectiron alloys
dc.subjectpwr type reactors
dc.subjects codes
dc.subjectstresses
dc.titleAnalysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulationpt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorCLAUDIA GIOVEDI MOTTA
ipen.autorAMANDA ABATI AGUIAR
ipen.codigoautor3870
ipen.codigoautor3150
ipen.contributor.ipenauthorCLAUDIA GIOVEDI MOTTA
ipen.contributor.ipenauthorAMANDA ABATI AGUIAR
ipen.date.recebimento20-02
ipen.event.datapadronizada2019pt_BR
ipen.identifier.ipendoc26357pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublication7bcf728c-4262-4074-83d1-bfcf73178984
relation.isAuthorOfPublicationb7c49d87-9d1a-4630-a819-63efab827023
relation.isAuthorOfPublication.latestForDiscoveryb7c49d87-9d1a-4630-a819-63efab827023
sigepi.autor.atividadeGIOVEDI, CLAUDIA:3870:-1:Npt_BR
sigepi.autor.atividadeABATI, AMANDA:3150:-1:Npt_BR
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