Identification of flow regimes and heat transfer modes in ANGRA2 core during the simulation of the small break loss of coolant accident of 250 cm2 in the cold leg of primary loop using RELAP5 code

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dc.contributor.authorBORGES, EDUARDO M.
dc.contributor.authorSABUNDJIAN, GAIANE
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2018-01-03T10:12:11Z
dc.date.available2018-01-03T10:12:11Z
dc.date.eventoOctober 22-27, 2017pt_BR
dc.description.abstractThe aim of this paper is to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 250cm2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. The results obtained for Angra2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core.pt_BR
dc.event.siglaINACpt_BR
dc.identifier.citationBORGES, EDUARDO M.; SABUNDJIAN, GAIANE. Identification of flow regimes and heat transfer modes in ANGRA2 core during the simulation of the small break loss of coolant accident of 250 cm2 in the cold leg of primary loop using RELAP5 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/123456789/28201.
dc.identifier.orcidhttps://orcid.org/0000-0001-9544-4509
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/28201
dc.localRio de Janeiro, RJpt_BR
dc.local.eventoBelo Horizonte, MGpt_BR
dc.publisherAssociação Brasileira de Energia Nuclearpt_BR
dc.rightsopenAccesspt_BR
dc.subjectflow models
dc.subjectfluid flow
dc.subjectheat transfer
dc.subjectloss of coolant
dc.subjectr codes
dc.subjectreactor accident simulation
dc.subjectreactor cores
dc.subjectvoid fraction
dc.subjectangra-2 reactor
dc.titleIdentification of flow regimes and heat transfer modes in ANGRA2 core during the simulation of the small break loss of coolant accident of 250 cm2 in the cold leg of primary loop using RELAP5 codept_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorGAIANE SABUNDJIAN
ipen.autorEDUARDO MADEIRA BORGES
ipen.codigoautor202
ipen.codigoautor11597
ipen.contributor.ipenauthorGAIANE SABUNDJIAN
ipen.contributor.ipenauthorEDUARDO MADEIRA BORGES
ipen.date.recebimento18-01pt_BR
ipen.event.datapadronizada2017pt_BR
ipen.identifier.ipendoc24026pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublication915b9343-9eaf-4b03-b709-85699f77b71c
relation.isAuthorOfPublication0874438b-9df3-431a-9017-cff45ec95482
relation.isAuthorOfPublication.latestForDiscovery0874438b-9df3-431a-9017-cff45ec95482
sigepi.autor.atividadeBORGES, EDUARDO M.:11597:420:Spt_BR
sigepi.autor.atividadeSABUNDJIAN, GAIANE:202:420:Npt_BR
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