Small break loss of coolant accident of 200 cm² in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation

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dc.contributor.authorBORGES, EDUARDO M.pt_BR
dc.contributor.authorSABUNDJIAN, GAIANEpt_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2020-01-15T18:35:17Z
dc.date.available2020-01-15T18:35:17Z
dc.date.eventoOctober 21-25, 2019pt_BR
dc.description.abstractThe aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and 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 200cm2 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 ANGRA 2 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.format.extent5479-5490pt_BR
dc.identifier.citationBORGES, EDUARDO M.; SABUNDJIAN, GAIANE. Small break loss of coolant accident of 200 cm² in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. <b>Proceedings...</b> Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5479-5490. Disponível em: http://repositorio.ipen.br/handle/123456789/30728.
dc.identifier.orcid0000-0001-9544-4509pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0001-9544-4509
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/30728
dc.localRio de Janeiropt_BR
dc.local.eventoSantos, SPpt_BR
dc.publisherAssociação Brasileira de Energia Nuclear
dc.rightsopenAccesspt_BR
dc.subjectangra-2 reactor
dc.subjectcladding
dc.subjecteccs
dc.subjectheat transfer
dc.subjectprimary coolant circuits
dc.subjectreactor accident simulation
dc.subjectreactor cores
dc.subjectsbloca
dc.subjectsteady-state conditions
dc.subjecttwo-phase flow
dc.subjectvoid fraction
dc.titleSmall break loss of coolant accident of 200 cm² in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluationpt_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.recebimento20-01
ipen.event.datapadronizada2019pt_BR
ipen.identifier.ipendoc26381pt_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.atividadeSABUNDJIAN, GAIANE:202:420:Npt_BR
sigepi.autor.atividadeBORGES, EDUARDO M.:11597:-1:Spt_BR
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