Analysis of UO2-BEO fuel under transient using fuel performance code

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dc.contributor.authorGOMES, DANIEL S.
dc.contributor.authorABE, ALFREDO Y.
dc.contributor.authorMUNIZ, RAFAEL O.R.
dc.contributor.authorGIOVEDI, CLAUDIA
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2018-01-02T12:15:44Z
dc.date.available2018-01-02T12:15:44Z
dc.date.eventoOctober 22-27, 2017pt_BR
dc.description.abstractRecent research has appointed the need to replace the classic fuel concept, used in light water reactors. Uranium dioxide has a weak point due to the low thermal conductivity, that produce high temperatures on the fuel. The ceramic composite fuel formed of uranium dioxide (UO2), with the addition of beryllium oxide (BeO), presents high thermal conductivity compared with UO2. The oxidation of zirconium generates hydrogen gas that can create a detonation condition. One of the preferred options are the ferritic alloys formed of iron-chromium and aluminum (FeCrAl), that should avoid the hydrogen release due to oxidation. In general, the FeCrAl alloys containing 10–20Cr, 3–5Al, and 0–0.12Y in weight percent. The FeCrAl alloys should exhibit a slow oxidation kinetics due to chemical composition. Resistance to oxidation in the presence of steam is improved as a function of the content of chromium and aluminum. In this way, the thermal and mechanical properties of the UO2-BeO-10%vol, composite fuel were coupled with FeCrAl alloys and added to the fuel codes. In this work, we examine the fuel rod behavior of UO2-10%vol-BeO/FeCrAl, including a simulated transient of reactivity. The fuels behavior shown reduced temperature with UO2-BeO/Zr, UO2-BeO/FeCrAl also were compared with UO2/Zr system. The case reactivity initiated accident analyzed, reproducing the fuel rod called VA-1 using UO2/Zr alloys and compared with UO2-BeO/FeCrAl.pt_BR
dc.event.siglaINACpt_BR
dc.identifier.citationGOMES, DANIEL S.; ABE, ALFREDO Y.; MUNIZ, RAFAEL O.R.; GIOVEDI, CLAUDIA. Analysis of UO2-BEO fuel under transient using fuel performance code. 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/123456789/28184.
dc.identifier.orcidhttps://orcid.org/0000-0002-2181-8704
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/28184
dc.localRio de Janeiro, RJpt_BR
dc.local.eventoBelo Horizonte, MGpt_BR
dc.publisherAssociação Brasileira de Energia Nuclearpt_BR
dc.rightsopenAccesspt_BR
dc.subjectaluminium alloys
dc.subjectberyllium oxides
dc.subjectchromium alloys
dc.subjectcomposite materials
dc.subjectcomputerized simulation
dc.subjectcoupling
dc.subjectf codes
dc.subjectfuel rods
dc.subjectiron alloys
dc.subjectmechanical properties
dc.subjectnuclear fuels
dc.subjectthermodynamic properties
dc.subjecttransients
dc.subjecturanium dioxide
dc.subjectzirconium
dc.titleAnalysis of UO2-BEO fuel under transient using fuel performance codept_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorRAFAEL OLIVEIRA RONDOM MUNIZ
ipen.autorALFREDO YUUITIRO ABE
ipen.autorDANIEL DE SOUZA GOMES
ipen.codigoautor3487
ipen.codigoautor7817
ipen.codigoautor7670
ipen.contributor.ipenauthorRAFAEL OLIVEIRA RONDOM MUNIZ
ipen.contributor.ipenauthorALFREDO YUUITIRO ABE
ipen.contributor.ipenauthorDANIEL DE SOUZA GOMES
ipen.date.recebimento18-01pt_BR
ipen.event.datapadronizada2017pt_BR
ipen.identifier.ipendoc24009pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublicationd7711d57-fb3f-43d2-9d03-a1b408954c9e
relation.isAuthorOfPublicationc9a80ee8-65ff-498b-a96b-79044dd4e4eb
relation.isAuthorOfPublication090e1d1e-dfb3-4120-8d6f-1374e82feb2b
relation.isAuthorOfPublication.latestForDiscovery090e1d1e-dfb3-4120-8d6f-1374e82feb2b
sigepi.autor.atividadeGOMES, DANIEL S.:7670:420:Spt_BR
sigepi.autor.atividadeABE, ALFREDO Y.:7817:-1:Npt_BR
sigepi.autor.atividadeMUNIZ, RAFAEL O.R.:3487:420:Npt_BR
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