Heat transfer mode in the core of the Angra 2 nuclear power plant during small break loca obtained with RELAP5 code

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dc.contributor.authorSABUNDJIAN, GAIANE
dc.contributor.authorBELCHIOR JUNIOR, ANTONIO
dc.contributor.authorCONTI, THADEU das N.
dc.contributor.authorROCHA, MARCELO da S.
dc.contributor.authorANDRADE, DELVONEI A. de
dc.contributor.authorTORRES, WALMIR M.
dc.contributor.authorMACEDO, LUIZ A.
dc.contributor.authorUMBEHAUN, PEDRO E.
dc.contributor.authorMESQUITA, ROBERTO N. de
dc.contributor.authorLIMA, ANA C. de S.
dc.coverageNacionalpt_BR
dc.creator.eventoREUNIÃO DE TRABALHO SOBRE FÍSICA NUCLEAR NO BRASIL, 36.pt_BR
dc.date.accessioned2017-07-06T13:40:57Z
dc.date.available2017-07-06T13:40:57Z
dc.date.evento1-5 de Setembro, 2013pt_BR
dc.description.abstractThis work aims to identify the heat transfer mode with RELAP5/MOD3.2.gama code in the core of Angra 2 facility. The postulate accident is the Loss of Coolant Accident (LOCA) in the primary circuit for Small Break (SB), which is described in Chapter 15 of the Final Safety Analysis Report of Angra 2 (FSAR). The accident consists basically of the total break of the cold leg of Angra 2 facility. The rupture area considered was 380 cm2, which represents 100% of the primary circuit pipe °ow area. The Emergency Core Cooling System (ECCS) e±ciency is also tested in this accident. In this simulation, failure and repair criteria are adopted for the ECCS components in order to verify the system operation e±ciency - preserving the integrity of the reactor core and guaranteeing its cooling - as expected by the project design. SBLOCA accidents are characterized by a fast blowdown in the primary circuit to values that activate the low pressure injection system followed by the water injection from the accumulators. The thermal-hydraulic processes inherent to the accident phenomenon, such as hot leg vaporization and consequently core vaporization cause inappropriate °ow distribution in the reactor core that can lead to reduction in the core liquid level, up to the point that the ECCS is able to re°ood it. This work shows the mode numbers and the wall convection heat transfer used in the RELAP5 code that were accessed during the execution of the program. The results showed that the numerical simulations with RELAP5 were satisfactory and that the ECCS worked e±ciently, guaranteeing the integrity of the reactor core.pt_BR
dc.event.siglaRTFNBpt_BR
dc.format.extent1-1pt_BR
dc.identifier.citationSABUNDJIAN, GAIANE; BELCHIOR JUNIOR, ANTONIO; CONTI, THADEU das N.; ROCHA, MARCELO da S.; ANDRADE, DELVONEI A. de; TORRES, WALMIR M.; MACEDO, LUIZ A.; UMBEHAUN, PEDRO E.; MESQUITA, ROBERTO N. de; LIMA, ANA C. de S. Heat transfer mode in the core of the Angra 2 nuclear power plant during small break loca obtained with RELAP5 code. In: REUNIÃO DE TRABALHO SOBRE FÍSICA NUCLEAR NO BRASIL, 36., 1-5 de Setembro, 2013, São Sebastião, SP. <b>Resumo...</b> São Paulo: Sociedade Brasileira de Física, 2013. p. 1-1. Disponível em: http://repositorio.ipen.br/handle/123456789/27635.
dc.identifier.orcidhttps://orcid.org/0000-0003-2445-1298
dc.identifier.orcidhttps://orcid.org/0000-0002-5355-0925
dc.identifier.orcidhttps://orcid.org/0000-0002-2887-0759
dc.identifier.orcidhttps://orcid.org/0000-0002-6689-3011
dc.identifier.orcidhttps://orcid.org/0000-0001-6155-0637
dc.identifier.orcidhttps://orcid.org/0000-0001-9544-4509
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/27635
dc.localSão Paulopt_BR
dc.local.eventoSão Sebastião, SPpt_BR
dc.publisherSociedade Brasileira de Físicapt_BR
dc.rightsopenAccesspt_BR
dc.titleHeat transfer mode in the core of the Angra 2 nuclear power plant during small break loca obtained with RELAP5 codept_BR
dc.typeResumo de eventos científicospt_BR
dspace.entity.typePublication
ipen.autorMARCELO DA SILVA ROCHA
ipen.autorWALMIR MAXIMO TORRES
ipen.autorANA CECILIA DE SOUZA LIMA
ipen.autorROBERTO NAVARRO DE MESQUITA
ipen.autorPEDRO ERNESTO UMBEHAUN
ipen.autorLUIZ ALBERTO MACEDO
ipen.autorDELVONEI ALVES DE ANDRADE
ipen.autorTHADEU DAS NEVES CONTI
ipen.autorANTONIO BELCHIOR JUNIOR
ipen.autorGAIANE SABUNDJIAN
ipen.codigoautor7992
ipen.codigoautor188
ipen.codigoautor9685
ipen.codigoautor1375
ipen.codigoautor754
ipen.codigoautor737
ipen.codigoautor1258
ipen.codigoautor284
ipen.codigoautor6367
ipen.codigoautor202
ipen.contributor.ipenauthorMARCELO DA SILVA ROCHA
ipen.contributor.ipenauthorWALMIR MAXIMO TORRES
ipen.contributor.ipenauthorANA CECILIA DE SOUZA LIMA
ipen.contributor.ipenauthorROBERTO NAVARRO DE MESQUITA
ipen.contributor.ipenauthorPEDRO ERNESTO UMBEHAUN
ipen.contributor.ipenauthorLUIZ ALBERTO MACEDO
ipen.contributor.ipenauthorDELVONEI ALVES DE ANDRADE
ipen.contributor.ipenauthorTHADEU DAS NEVES CONTI
ipen.contributor.ipenauthorANTONIO BELCHIOR JUNIOR
ipen.contributor.ipenauthorGAIANE SABUNDJIAN
ipen.date.recebimento17-07pt_BR
ipen.event.datapadronizada2013pt_BR
ipen.identifier.ipendoc23885pt_BR
ipen.notas.internasResumopt_BR
ipen.type.genreResumo
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sigepi.autor.atividadeSABUNDJIAN, GAIANE:202:420:Spt_BR
sigepi.autor.atividadeBELCHIOR JUNIOR, ANTONIO:6367:420:Npt_BR
sigepi.autor.atividadeCONTI, THADEU DAS N.:284:420:Npt_BR
sigepi.autor.atividadeROCHA, MARCELO DA S.:7992:-1:Npt_BR
sigepi.autor.atividadeANDRADE, DELVONEI A. DE:1258:420:Npt_BR
sigepi.autor.atividadeTORRES, WALMIR M.:188:420:Npt_BR
sigepi.autor.atividadeMACEDO, LUIZ A.:737:420:Npt_BR
sigepi.autor.atividadeUMBEHAUN, PEDRO E.:754:420:Npt_BR
sigepi.autor.atividadeMESQUITA, ROBERTO N. DE:1375:420:Npt_BR
sigepi.autor.atividadeLIMA, ANA C. DE S.:9685:420:Npt_BR
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