Assessment of ANSYS LS-DYNA capabilities for analysis of drop tests of nuclear fuel element transportation casks

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dc.contributor.authorCARVALHO, DANIEL S.M. dept_BR
dc.contributor.authorMATTAR NETO, MIGUELpt_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2020-01-15T18:58:58Z
dc.date.available2020-01-15T18:58:58Z
dc.date.eventoOctober 21-25, 2019pt_BR
dc.description.abstractDuring the transportation of fuel elements, the cask has to provide shielding to protect workers, the public and the environment against the effects of radiation, to prevent an unwanted chain reaction, damage caused by heat and also to provide protection against dispersion of the contents. In order to standardize the design of fuel assembly transportation devices by numerical analysis, a set of dynamic analyzes was conducted to converge in a representative way the phenomena found in the drop tests used in the project qualification. Thus, this paper aims to present and discuss updated recommendations for contacts, material models and general configurations in three benchmarks. These benchmarks represent the phenomena found in numerical simulations of drop trials. Moreover, they are important to obtain an adequate correlation with the lowest possible use of computational resources. From the simulations, it was possible to observe the influence of an analysis carried out in plane strain and another one performed with the complete geometry modeled in scale 1:4 in relation to the computational cost and the precision of the results. A methodology was proposed to calibrate the stiffness and the damping control of the contacts and, mainly, their influence on the behavior of the structure.pt_BR
dc.event.siglaINACpt_BR
dc.format.extent5551-5563pt_BR
dc.identifier.citationCARVALHO, DANIEL S.M. de; MATTAR NETO, MIGUEL. Assessment of ANSYS LS-DYNA capabilities for analysis of drop tests of nuclear fuel element transportation casks. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. <b>Proceedings...</b> Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5551-5563. Disponível em: http://repositorio.ipen.br/handle/123456789/30731.
dc.identifier.orcid0000-0002-2295-1021pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-2295-1021
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/30731
dc.localRio de Janeiropt_BR
dc.local.eventoSantos, SPpt_BR
dc.publisherAssociação Brasileira de Energia Nuclear
dc.rightsopenAccesspt_BR
dc.subjectbenchmarks
dc.subjectboundary conditions
dc.subjectcasks
dc.subjectcomputerized simulation
dc.subjectdamping
dc.subjectfinite element method
dc.subjectflexibility
dc.subjectfuel assemblies
dc.subjectfuel elements
dc.subjectmathematical models
dc.subjectnuclear fuels
dc.subjectrecommendations
dc.subjecttesting
dc.subjecttransport
dc.titleAssessment of ANSYS LS-DYNA capabilities for analysis of drop tests of nuclear fuel element transportation caskspt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorMIGUEL MATTAR NETO
ipen.codigoautor70
ipen.contributor.ipenauthorMIGUEL MATTAR NETO
ipen.date.recebimento20-01
ipen.event.datapadronizada2019pt_BR
ipen.identifier.ipendoc26384pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublicationf529c318-12eb-4cdc-b0ad-8fc1d9fee754
relation.isAuthorOfPublication.latestForDiscoveryf529c318-12eb-4cdc-b0ad-8fc1d9fee754
sigepi.autor.atividadeMATTAR NETO, MIGUEL:70:420:Npt_BR
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