MELCOR simulation of a severe accident scenario derived from a small break loca in a typical PWR with passive autocatalytic recombiners

Página do item simplificado
dc.contributor.authorLEE, SEUNG M.pt_BR
dc.contributor.authorLAPA, NELBIA S.pt_BR
dc.contributor.authorSABUNDJIAN, GAIANEpt_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2020-01-15T17:58:55Z
dc.date.available2020-01-15T17:58:55Z
dc.date.eventoOctober 21-25, 2019pt_BR
dc.description.abstractThis work presents the simulation of a severe accident scenario in a referential model of pressurized water reactor, which came about from a rupture of 20cm2 in a cold leg of a reactor cooling system. The simulation was carried out on the MELCOR code using a model elaborated by the Global Research for Safety – Germany, with the passive autocatalytic recombiners implemented in almost every compartment in the containment. The efficacy and effectiveness of this well-known mitigating measure of severe accident management are demonstrated by means of a comparison with the case previously simulated without this measure using the same model. This referential reactor is important and very useful for the independent analysis of severe accidents in the Brazilian Angra 2 nuclear power plant in virtue of the similarity between both of them, so that after some proper modifications on this referential reactor’s model, it could be applied for the study of severe accidents in the other. In this sense, the result presented in this work is to be taken as an important reference for the severe accident analysis of Angra 2.pt_BR
dc.event.siglaINACpt_BR
dc.format.extent5346-5359pt_BR
dc.identifier.citationLEE, SEUNG M.; LAPA, NELBIA S.; SABUNDJIAN, GAIANE. MELCOR simulation of a severe accident scenario derived from a small break loca in a typical PWR with passive autocatalytic recombiners. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. <b>Proceedings...</b> Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5346-5359. Disponível em: http://repositorio.ipen.br/handle/123456789/30720.
dc.identifier.orcid0000-0001-9544-4509pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0001-9544-4509
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/30720
dc.localRio de Janeiropt_BR
dc.local.eventoSantos, SPpt_BR
dc.publisherAssociação Brasileira de Energia Nuclear
dc.rightsopenAccesspt_BR
dc.subjectboundary conditions
dc.subjectcladding
dc.subjectloss of coolant
dc.subjectm codes
dc.subjectmelt-through
dc.subjectpwr type reactors
dc.subjectradiation protection
dc.subjectreactor accident simulation
dc.subjectreactor cooling systems
dc.titleMELCOR simulation of a severe accident scenario derived from a small break loca in a typical PWR with passive autocatalytic recombinerspt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorGAIANE SABUNDJIAN
ipen.autorSEUNG MIN LEE
ipen.codigoautor202
ipen.codigoautor6057
ipen.contributor.ipenauthorGAIANE SABUNDJIAN
ipen.contributor.ipenauthorSEUNG MIN LEE
ipen.date.recebimento20-01
ipen.event.datapadronizada2019pt_BR
ipen.identifier.ipendoc26373pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublication915b9343-9eaf-4b03-b709-85699f77b71c
relation.isAuthorOfPublication69d76f4d-78f0-482e-be90-d5e2187fcf32
relation.isAuthorOfPublication.latestForDiscovery69d76f4d-78f0-482e-be90-d5e2187fcf32
sigepi.autor.atividadeSABUNDJIAN, GAIANE:202:420:Npt_BR
sigepi.autor.atividadeLEE, SEUNG M.:6057:420:Spt_BR
Pacote Original
Agora exibindo 1 - 1 de 1
Imagem de Miniatura
Nome:
26373.pdf
Tamanho:
1.35 MB
Formato:
Adobe Portable Document Format
Descrição:
Baixar
Licença do Pacote
Agora exibindo 1 - 1 de 1
Nenhuma Miniatura disponível
Nome:
license.txt
Tamanho:
1.71 KB
Formato:
Item-specific license agreed upon to submission
Descrição:
Baixar
Coleções
Eventos