Improving performance with accident tolerant-fuels

dc.contributor.authorGOMES, DANIEL S.
dc.contributor.authorMUNIZ, RAFAEL O.R.
dc.contributor.authorGIOVEDI, CLAUDIA
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2018-01-02T15:35:46Z
dc.date.available2018-01-02T15:35:46Z
dc.date.eventoOctober 22-27, 2017pt_BR
dc.description.abstractAfter the Fukushima reactor accident, efforts to improve risk management in nuclear operations have included the intensification of research on accident-tolerant fuels (ATFs). In this investigation, the physical properties of recently developed ATFs were compared with those of the current standard fuel, UO2–Zr. The goals for innovative fuel design include a rigorous characterization of the thermal, mechanical, and chemical considerations. The intentions are to lengthen the burnup cycle, raise the power density, and improve safety. Fuels must have a high uranium density—above that supported by UO2—and possess a coating that exhibits better oxidation resistance than Zircaloys. ATFs such as U3Si2, UN, and UC contain a higher uranium density and thermal conductivity than UO2, providing significant benefits. The ideal combination of fuel and cladding must increase performance in a loss-of-coolant accident. However, U3Si2, UN, and UC have a disadvantage; their respective swelling rates are higher than that of UO2. These ATFs also have thermal conductivities approximately four times higher than that of UO2. A study was conducted investigating the hydrogen generated by the oxidation of zirconium alloys in contact with steam using cladding options such as Fe-Cr-Al and silicon carbide. It was confirmed that ferritic alloys offer a better response under severe conditions, because of their mechanical properties as creep rate. The findings of this study indicate that advanced fuels should replace UO2–Zr as the fuel system of choice.pt_BR
dc.event.siglaINACpt_BR
dc.identifier.citationGOMES, DANIEL S.; MUNIZ, RAFAEL O.R.; GIOVEDI, CLAUDIA. Improving performance with accident tolerant-fuels. 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/123456789/28190.
dc.identifier.orcidhttps://orcid.org/0000-0002-2181-8704
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/28190
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.subjectaluminium
dc.subjectchromium
dc.subjectcladding
dc.subjectcomparative evaluations
dc.subjectiron
dc.subjectoxidation
dc.subjectphysical properties
dc.subjectswelling
dc.subjecturanium oxides
dc.subjectwater cooled reactors
dc.subjectzirconium alloys
dc.titleImproving performance with accident tolerant-fuelspt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorRAFAEL OLIVEIRA RONDOM MUNIZ
ipen.autorDANIEL DE SOUZA GOMES
ipen.codigoautor3487
ipen.codigoautor7670
ipen.contributor.ipenauthorRAFAEL OLIVEIRA RONDOM MUNIZ
ipen.contributor.ipenauthorDANIEL DE SOUZA GOMES
ipen.date.recebimento18-01pt_BR
ipen.event.datapadronizada2017pt_BR
ipen.identifier.ipendoc24015pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublicationd7711d57-fb3f-43d2-9d03-a1b408954c9e
relation.isAuthorOfPublication090e1d1e-dfb3-4120-8d6f-1374e82feb2b
relation.isAuthorOfPublication.latestForDiscovery090e1d1e-dfb3-4120-8d6f-1374e82feb2b
sigepi.autor.atividadeGOMES, DANIEL S.:7670:420:Spt_BR
sigepi.autor.atividadeMUNIZ, RAFAEL O.R.:3487:420:Npt_BR

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