Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor

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dc.contributor.authorDOMINGOS, DOUGLAS B.pt_BR
dc.contributor.authorTEIXEIRA e SILVA, ANTONIOpt_BR
dc.contributor.authorUMBEHAUN, PEDRO E.pt_BR
dc.contributor.authorSILVA, JOSE E.R. dapt_BR
dc.contributor.authorCONTI, THADEU das N.pt_BR
dc.contributor.authorYAMAGUCHI, MITSUOpt_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1stpt_BR
dc.date.accessioned2014-11-17T18:19:56Zpt_BR
dc.date.accessioned2014-11-18T18:27:41Zpt_BR
dc.date.accessioned2015-04-02T03:22:04Z
dc.date.available2014-11-17T18:19:56Zpt_BR
dc.date.available2014-11-18T18:27:41Zpt_BR
dc.date.available2015-04-02T03:22:04Z
dc.date.eventoSeptember 27 - October 2, 2009pt_BR
dc.description.abstractNeutronic, thermal-hydraulics and accident analysis calculations were developed to estimate the safety of an irradiation device placed in the IEA-R1 reactor core. The irradiation device will be used to receive miniplates of U3O8-Al e U3Si2-Al dispersion fuels, LEU type (19.9% of 235U), with uranium densities of, respectively, 3.0 gU/cm3 and 4.8gU/cm3 . The fuel miniplates will be irradiated to nominal 235U burnup levels of 50% and 80%, in order to qualify the above high-density dispersion fuels to be used in the Brazilian Multipurpose Reactor, now in the conception phase. For the neutronic calculation, the computer code CITATION was utilized. The computer code FLOW was used to calculate the coolant flow rate in the irradiation device, allowing the determination of the fuel miniplate temperatures with the computer model MTRCR-IEA-R1. A postulated Loss of Coolant Accident (LOCA) was analyzed with the computer codes LOSS and TEMPLOCA, allowing the calculation of the fuel miniplate temperatures after the reactor pool draining. The calculations showed that the irradiation of the fuel miniplates will happen without any adverse consequence in the IEA-R1 reactor.
dc.event.siglaINAC; ENAN; ENFIR; ENINpt_BR
dc.identifier.citationDOMINGOS, DOUGLAS B.; TEIXEIRA e SILVA, ANTONIO; UMBEHAUN, PEDRO E.; SILVA, JOSE E.R. da; CONTI, THADEU das N.; YAMAGUCHI, MITSUO. Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1st, September 27 - October 2, 2009, Rio de Janeiro, RJ. <b>Proceedings...</b> Disponível em: http://repositorio.ipen.br/handle/123456789/16611.
dc.identifier.orcidhttps://orcid.org/0000-0001-6155-0637
dc.identifier.orcidhttps://orcid.org/0000-0001-7121-6632
dc.identifier.orcidhttps://orcid.org/0000-0002-2887-0759
dc.identifier.orcidhttps://orcid.org/0000-0002-7308-5784
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/16611pt_BR
dc.local.eventoRio de Janeiro, RJpt_BR
dc.publisherSao Paulo: ABEN, 2009pt_BR
dc.rightsopenAccesspt_BR
dc.subjectc codespt_BR
dc.subjectdispersion nuclear fuelspt_BR
dc.subjectf codespt_BR
dc.subjectflow ratept_BR
dc.subjectiear-1 reactorpt_BR
dc.subjectirradiation devicespt_BR
dc.subjectl codespt_BR
dc.subjectloss of coolantpt_BR
dc.subjectreactor corespt_BR
dc.subjectt codespt_BR
dc.subjectthermal hydraulicspt_BR
dc.subjecturanium oxides u3o8pt_BR
dc.titleNeutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactorpt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorMITSUO YAMAGUCHI
ipen.autorTHADEU DAS NEVES CONTI
ipen.autorJOSE EDUARDO ROSA DA SILVA
ipen.autorPEDRO ERNESTO UMBEHAUN
ipen.autorANTONIO TEIXEIRA E SILVA
ipen.autorDOUGLAS BORGES DOMINGOS
ipen.codigoautor1338
ipen.codigoautor284
ipen.codigoautor137
ipen.codigoautor754
ipen.codigoautor1085
ipen.codigoautor7482
ipen.contributor.ipenauthorMITSUO YAMAGUCHI
ipen.contributor.ipenauthorTHADEU DAS NEVES CONTI
ipen.contributor.ipenauthorJOSE EDUARDO ROSA DA SILVA
ipen.contributor.ipenauthorPEDRO ERNESTO UMBEHAUN
ipen.contributor.ipenauthorANTONIO TEIXEIRA E SILVA
ipen.contributor.ipenauthorDOUGLAS BORGES DOMINGOS
ipen.date.recebimento09-10pt_BR
ipen.event.datapadronizada2009pt_BR
ipen.identifier.ipendoc15265pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
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sigepi.autor.atividadeDOMINGOS, DOUGLAS B.:7482:420:Spt_BR
sigepi.autor.atividadeTEIXEIRA e SILVA, ANTONIO:1085:420:Npt_BR
sigepi.autor.atividadeUMBEHAUN, PEDRO E.:754:420:Npt_BR
sigepi.autor.atividadeSILVA, JOSE E.R. DA:137:420:Npt_BR
sigepi.autor.atividadeCONTI, THADEU DAS N.:284:420:Npt_BR
sigepi.autor.atividadeYAMAGUCHI, MITSUO:1338:420:Npt_BR
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