Modification of TRANSURANUS fuel performance code in the ATF framework

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dc.contributor.authorABE, ALFREDO Y.pt_BR
dc.contributor.authorMELO, CAIOpt_BR
dc.contributor.authorGIOVEDI, CLAUDIApt_BR
dc.contributor.authorSILVA, ANTONIO T.pt_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2020-02-20T13:10:30Z
dc.date.available2020-02-20T13:10:30Z
dc.date.eventoOctober 21-25, 2019pt_BR
dc.description.abstractThe standard fuel system based on UO2–zirconium alloy has been utilized on nearly 90% of worldwide nuclear power light water reactors. After the Fukushima Daiichi accident, alternative cladding materials to zirconium-based alloys are being investigated in the framework of accident tolerance fuel (ATF) program. One of the concepts of ATF is related to cladding materials that could delay the onset of high temperature oxidation, as well as ballooning and burst, in order to improve reactor safety systems, and consequently increase the coping time for the reactor operators in accident condition, especially under Loss-of-Coolant Accident (LOCA) scenario. The ferritic iron-chromium-aluminum (FeCrAl) alloys have been identified as an alternative to replace current zirconium-based alloys based on its outstanding resistance to oxidation under superheated steam environment due to the development of alumina oxide on the alloy surface in case of LOCA; moreover, FeCrAl alloys present quite well performance under normal operation conditions due to the thin oxide rich in chromium that acts as a protective layer. The assessment and performance of new fuel systems rely on experimental irradiation program and fuel performance code simulation, therefore the aim of this work is to contribute to the computational modeling capabilities in the framework of the ATF concept. The well-known TRANSURANUS fuel performance code that is used by safety authorities, industries, laboratories, research centers and universities was modified in order to support FeCrAl alloy as cladding material. The modification of the TRANSURANUS code was based on existing data (material properties) from open literature and as verification process was performed considering LOCA accident scenario.pt_BR
dc.event.siglaINACpt_BR
dc.format.extent5036-5045pt_BR
dc.identifier.citationABE, ALFREDO Y.; MELO, CAIO; GIOVEDI, CLAUDIA; SILVA, ANTONIO T. Modification of TRANSURANUS fuel performance code in the ATF framework. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. <b>Proceedings...</b> Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5036-5045. Disponível em: http://repositorio.ipen.br/handle/123456789/30814.
dc.identifier.orcidhttps://orcid.org/0000-0002-7308-5784
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/30814
dc.localRio de Janeiropt_BR
dc.local.eventoSantos, SPpt_BR
dc.publisherAssociação Brasileira de Energia Nuclear
dc.rightsopenAccesspt_BR
dc.subjectaccident-tolerant nuclear fuels
dc.subjectaluminium alloys
dc.subjectchromium alloys
dc.subjectcladding
dc.subjectcomparative evaluations
dc.subjectfuel rods
dc.subjectiron alloys
dc.subjectloss of coolant
dc.subjectperformance
dc.subjectt codes
dc.subjectzirconium alloys
dc.titleModification of TRANSURANUS fuel performance code in the ATF frameworkpt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorANTONIO TEIXEIRA E SILVA
ipen.autorALFREDO YUUITIRO ABE
ipen.codigoautor1085
ipen.codigoautor7817
ipen.contributor.ipenauthorANTONIO TEIXEIRA E SILVA
ipen.contributor.ipenauthorALFREDO YUUITIRO ABE
ipen.date.recebimento20-02
ipen.event.datapadronizada2019pt_BR
ipen.identifier.ipendoc26363pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublication76359599-f842-443b-ab16-8a7caaac1bac
relation.isAuthorOfPublicationc9a80ee8-65ff-498b-a96b-79044dd4e4eb
relation.isAuthorOfPublication.latestForDiscoveryc9a80ee8-65ff-498b-a96b-79044dd4e4eb
sigepi.autor.atividadeSILVA, ANTONIO T.:1085:420:Npt_BR
sigepi.autor.atividadeABE, ALFREDO Y.:7817:-1:Spt_BR
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