Simulation of a severe accident at a typical PWR due to break of a hot leg ECCS line using melcor code

dc.contributor.authorLEE, SEUNG M.
dc.contributor.authorSABUNDJIAN, GAIANE
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2018-01-03T09:59:38Z
dc.date.available2018-01-03T09:59:38Z
dc.date.eventoOctober 22-27, 2017pt_BR
dc.description.abstractThe aim of this work was to simulate a severe accident at a typical PWR caused by break in Emergency Core Cooling System (ECCS) line of a hot leg using the MELCOR code. The nodalization of this typical PWR was elaborated by the Global Research for Safety (GRS) and provided to the CNEN for analysis of the severe accidents at the Angra 2, which is similar to that PWR. Although both of them are not identical the results obtained for that typical PWR may be valuable because of the lack of officially published calculation for Angra 2. Relevant parameters such as pressure, temperature and water level in various control volumes after the break in the hot leg were calculated as well as degree of core degradation and hydrogen concentration in containment. The result obtained in this work could be considered satisfactory in the sense that the physical phenomena reproduced by the simulation were in general very reasonable, and most of the events occurred within acceptable time intervals. However, the uncertainty analysis was not carried out in this work. Furthermore, this scenario could be used as a base for the study of the effectiveness of some preventive or/and mitigating measures of Severe Accident Management (SAMG) by adding associated conditions for each measure in its input.pt_BR
dc.event.siglaINACpt_BR
dc.identifier.citationLEE, SEUNG M.; SABUNDJIAN, GAIANE. Simulation of a severe accident at a typical PWR due to break of a hot leg ECCS line using melcor 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/123456789/28199.
dc.identifier.orcidhttps://orcid.org/0000-0001-9544-4509
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/28199
dc.localRio de Janeiro, RJpt_BR
dc.local.eventoBelo Horizonte, MGpt_BR
dc.publisherAssociação Brasileira de Energia Nuclearpt_BR
dc.rightsopenAccesspt_BR
dc.subjectboundary conditions
dc.subjectcomputerized simulation
dc.subjecteccs
dc.subjectgesellschaft fuer anlagen- und reaktorsicherheit
dc.subjectlbloca
dc.subjectm codes
dc.subjectpwr type reactors
dc.subjectreactor cores
dc.titleSimulation of a severe accident at a typical PWR due to break of a hot leg ECCS line using melcor codept_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.recebimento18-01pt_BR
ipen.event.datapadronizada2017pt_BR
ipen.identifier.ipendoc24024pt_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.atividadeLEE, SEUNG M.:6057:420:Spt_BR
sigepi.autor.atividadeSABUNDJIAN, GAIANE:202:420:Npt_BR

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