Use of selective laser fusion in Zircaloy and tungsten alloy for employ in end-caps for nuclear fuel element rods and shielding

dc.contributor.authorPEREIRA, L.T.pt_BR
dc.contributor.authorROSSI, J.L.pt_BR
dc.contributor.authorFASANO, A.C.pt_BR
dc.contributor.authorMUCSI, C.S.pt_BR
dc.contributor.authorBEHMER, W.pt_BR
dc.contributor.authorLUIZ, L.pt_BR
dc.contributor.authorFLORENTINO, E.pt_BR
dc.coverageNacionalpt_BR
dc.creator.eventoCONGRESSO BRASILEIRO DE ENGENHARIA E CIÊNCIA DOS MATERIAIS, 24.pt_BR
dc.date.accessioned2023-02-09T15:32:06Z
dc.date.available2023-02-09T15:32:06Z
dc.date.evento6-10 de novembro, 2022pt_BR
dc.description.abstractThis study shows that it is possible to obtain parts of zirconium alloy called Zircaloy-4 (Zry-4) through selective laser melting (SLM), using metal chips as raw material. Additive manufacturing technology is emerging in Brazil, whose principle is the manufacture of a piece layer by layer from a metallic powder. Zirconium alloys are widely used in nuclear reactors, mainly in fuel element cladding and grids. The closing of the ends of the rods is done by end-caps, which is machined and generates large amounts of chips, which are a valuable source for the reuse of zirconium, having the advantage of being hafnium-free. After hydriding the Zircaloy it becomes zirconium hydride (ZrH2) and can be ground, obtaining the alloy in powder form to be used in SLM. A tungsten alloy with SLM technology was also studied due to its high melting temperature, high density and high mechanical strength, which can be used in shielding against radiation. In this study, a thin layer of alloys was cast on a substrate, which were evaluated for chemical composition, microstructure, hardness and roughness, whose results indicated values compatible with the stipulated requirements.pt_BR
dc.event.siglaCBECiMatpt_BR
dc.identifier.citationPEREIRA, L.T.; ROSSI, J.L.; FASANO, A.C.; MUCSI, C.S.; BEHMER, W.; LUIZ, L.; FLORENTINO, E. Use of selective laser fusion in Zircaloy and tungsten alloy for employ in end-caps for nuclear fuel element rods and shielding. In: CONGRESSO BRASILEIRO DE ENGENHARIA E CIÊNCIA DOS MATERIAIS, 24., 6-10 de novembro, 2022, Águas de Lindóia, SP. <b>Resumo...</b> Disponível em: http://repositorio.ipen.br/handle/123456789/33791.
dc.identifier.orcid0000-0002-8304-9939pt_BR
dc.identifier.orcid0000-0001-5835-5320pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-8304-9939
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/33791
dc.local.eventoÁguas de Lindóia, SPpt_BR
dc.rightsopenAccesspt_BR
dc.titleUse of selective laser fusion in Zircaloy and tungsten alloy for employ in end-caps for nuclear fuel element rods and shieldingpt_BR
dc.typeResumo de eventos científicospt_BR
dspace.entity.typePublication
ipen.autorEMERSON FARIAS FLORENTINO
ipen.autorCRISTIANO STEFANO MUCSI
ipen.autorJESUALDO LUIZ ROSSI
ipen.autorLUIZ ALBERTO TAVARES PEREIRA
ipen.codigoautor15284
ipen.codigoautor507
ipen.codigoautor502
ipen.codigoautor9165
ipen.contributor.ipenauthorEMERSON FARIAS FLORENTINO
ipen.contributor.ipenauthorCRISTIANO STEFANO MUCSI
ipen.contributor.ipenauthorJESUALDO LUIZ ROSSI
ipen.contributor.ipenauthorLUIZ ALBERTO TAVARES PEREIRA
ipen.date.recebimento23-02
ipen.event.datapadronizada2022pt_BR
ipen.identifier.ipendoc29425pt_BR
ipen.notas.internasResumopt_BR
ipen.type.genreResumo
relation.isAuthorOfPublicatione8595010-cc22-4021-842f-033dae985028
relation.isAuthorOfPublication58fc8404-272e-4946-9a1d-b32060dcb5ec
relation.isAuthorOfPublicationc30c7f95-0303-41bd-aa41-1fc8c12ec2ab
relation.isAuthorOfPublicatione3e60c88-c315-4b2f-87b4-1aa467b6fb62
relation.isAuthorOfPublication.latestForDiscoverye3e60c88-c315-4b2f-87b4-1aa467b6fb62
sigepi.autor.atividadeFLORENTINO, E.:15284:730:Npt_BR
sigepi.autor.atividadeMUCSI, C.S.:507:730:Npt_BR
sigepi.autor.atividadeROSSI, J.L.:502:730:Npt_BR
sigepi.autor.atividadePEREIRA, L.T.:9165:730:Spt_BR

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