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

dc.contributor.authorLEE, S.M.pt_BR
dc.contributor.authorLAPA, N.S.pt_BR
dc.contributor.authorSABUNDJIAN, G.pt_BR
dc.coverageNacionalpt_BR
dc.date.accessioned2019-12-20T11:23:45Z
dc.date.available2019-12-20T11:23:45Z
dc.date.issued2019pt_BR
dc.description.abstractThe aim of this work was to simulate a severe accident at a typical PWR, initiated with a break in Emergency Core Cooling System line of a hot leg, using the MELCOR code. The model of this typical PWR was elaborated by the Global Research for Safety and provided to the CNEN for independent analysis of the severe accidents at Angra 2, which is similar to this typical PWR. Although both of them are not identical, the results obtained of that typical PWR may be valuable because of the lack of officially published simulation of severe accident at Angra 2. Relevant parameters such as pressure, temperature and water level in various control volumes, after the break at the hot leg, were calculated as well as degree of core degradation and hydrogen production within the 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 by implementing each measure in this model.pt_BR
dc.format.extent1-13pt_BR
dc.identifier.citationLEE, S.M.; LAPA, N.S.; SABUNDJIAN, G. Simulation of a severe accident at a typical PWR due to break of a hot leg ECCS injection line using MELCOR code. <b>Brazilian Journal of Radiation Sciences</b>, v. 7, n. 2B, p. 1-13, 2019. DOI: <a href="https://dx.doi.org/10.15392/bjrs.v7i2B.682">10.15392/bjrs.v7i2B.682</a>. Disponível em: http://repositorio.ipen.br/handle/123456789/30475.
dc.identifier.doi10.15392/bjrs.v7i2B.682pt_BR
dc.identifier.fasciculo2Bpt_BR
dc.identifier.issn2319-0612pt_BR
dc.identifier.orcid0000-0001-9544-4509pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0001-9544-4509
dc.identifier.percentilfiSem Percentilpt_BR
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/30475
dc.identifier.vol7pt_BR
dc.relation.ispartofBrazilian Journal of Radiation Sciencespt_BR
dc.rightsopenAccesspt_BR
dc.sourceMeeting on Nuclear Reactor Physics and Thermal Hydraulics (ENFIR), 20th, 22-27 de outubro, 2017, Belo Horizonte, MGpt_BR
dc.subjectgesellschaft fuer anlagen- und reaktorsicherheit
dc.subjectlbloca
dc.subjectm codes
dc.subjectpwr type reactors
dc.subjectreactor cores
dc.subjectboundary conditions
dc.subjectbrazilian cnen
dc.subjecteccs
dc.subjectcomputerized simulation
dc.titleSimulation of a severe accident at a typical PWR due to break of a hot leg ECCS injection line using MELCOR codept_BR
dc.typeArtigo de periódicopt_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.recebimento19-12
ipen.identifier.fiSem F.I.pt_BR
ipen.identifier.ipendoc26504pt_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, G.:202:420:Npt_BR
sigepi.autor.atividadeLEE, S.M.:6057:420:Spt_BR

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