Reactivity initiated accident assessment for ATF cladding materials

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dc.contributor.authorGIOVEDI, C.pt_BR
dc.contributor.authorMARTINS, M.R.pt_BR
dc.contributor.authorABE, A.pt_BR
dc.contributor.authorREIS, R.pt_BR
dc.contributor.authorSILVA, A.T.pt_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoTECHNICAL MEETING ON MODELLING OF FUEL BEHAVIOUR IN DESIGN BASIS ACCIDENTS AND DESIGN EXTENSION CONDITIONSpt_BR
dc.date.accessioned2020-04-03T13:03:18Z
dc.date.available2020-04-03T13:03:18Z
dc.date.eventoMay 13-16, 2019pt_BR
dc.description.abstractFollowing the experience that came from the Fukushima Daiichi accident, one possible way of reducing risk in a nuclear power plant operation would be the replacement of the existing fuel rod cladding material (based on zirconium alloys) by another materials which could fulfill the requirements of the accident tolerant fuel (ATF) concept. In this sense, ATF should be able to keep the current fuel system performance under normal operation conditions; moreover, it should present superior performance than the existing conventional fuel system (zirconium-based alloys and uranium dioxide) under accident conditions. The most challenging and bounding accident scenarios for nuclear fuel systems in Pressurized Water Reactors (PWR) are Loss of Coolant Accident (LOCA) and Reactivity Initiated Accident (RIA), which are postulated accidents. This work addresses the performance of ATF using iron-based alloys as cladding material under RIA conditions. The evaluation is carried out using modified versions of the coupled system FRAPCON/FRAPTRAN. These codes were modified to include the material properties (thermal, mechanical, and physics) of an iron-based alloy, specifically FeCrAl alloy. The analysis is performed using data available in the open literature related to experiments using conventional PWR fuel system (zirconium-based alloys and uranium dioxide). The results obtained using the modified code versions are compared to those of the actual existing fuel system based on zircaloy-4 cladding using the original versions of the fuel performance codes (FRAPCON/FRAPTRAN).pt_BR
dc.format.extent155-161
dc.identifier.citationGIOVEDI, C.; MARTINS, M.R.; ABE, A.; REIS, R.; SILVA, A.T. Reactivity initiated accident assessment for ATF cladding materials. In: TECHNICAL MEETING ON MODELLING OF FUEL BEHAVIOUR IN DESIGN BASIS ACCIDENTS AND DESIGN EXTENSION CONDITIONS, May 13-16, 2019, Shenzhen, China. <b>Proceedings...</b> Vienna, Austria: International Atomic Energy Agency, 2020. p. 155-161. (IAEA-TECDOC-1913). Disponível em: http://repositorio.ipen.br/handle/123456789/31065.
dc.identifier.orcidhttps://orcid.org/0000-0002-7308-5784
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/31065
dc.localVienna, Austria
dc.local.eventoShenzhen, Chinapt_BR
dc.publisherInternational Atomic Energy Agency
dc.relation.ispartofseriesIAEA-TECDOC-1913
dc.rightsopenAccesspt_BR
dc.subjectaccident-tolerant nuclear fuels
dc.subjectcharges
dc.subjectcladding
dc.subjectcomparative evaluations
dc.subjectcurrents
dc.subjectfuel rods
dc.subjectfuel systems
dc.subjectfukushima daiichi nuclear power station
dc.subjecthazards
dc.subjectzircaloy 4
dc.subjectiron
dc.subjectloss of coolant
dc.subjectnuclear power plants
dc.subjectoperation
dc.subjectperformance
dc.subjectpwr type reactors
dc.subjectreactivity-initiated accidents
dc.subjectsteady-state conditions
dc.subjecturanium dioxide
dc.titleReactivity initiated accident assessment for ATF cladding materialspt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorREGIS REIS
ipen.autorANTONIO TEIXEIRA E SILVA
ipen.autorALFREDO YUUITIRO ABE
ipen.codigoautor10903
ipen.codigoautor1085
ipen.codigoautor7817
ipen.contributor.ipenauthorREGIS REIS
ipen.contributor.ipenauthorANTONIO TEIXEIRA E SILVA
ipen.contributor.ipenauthorALFREDO YUUITIRO ABE
ipen.date.recebimento20-04
ipen.event.datapadronizada2020pt_BR
ipen.identifier.ipendoc26855pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublicationb1be9ae6-f95d-458a-87ce-27094ec90764
relation.isAuthorOfPublication76359599-f842-443b-ab16-8a7caaac1bac
relation.isAuthorOfPublicationc9a80ee8-65ff-498b-a96b-79044dd4e4eb
relation.isAuthorOfPublication.latestForDiscoveryc9a80ee8-65ff-498b-a96b-79044dd4e4eb
sigepi.autor.atividadeSILVA, A.T.:1085:420:Npt_BR
sigepi.autor.atividadeREIS, R.:10903:420:Npt_BR
sigepi.autor.atividadeABE, A.:7817:420:Npt_BR
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