Qualification process of dispersion fuels in the IEA-R1 research reactor

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dc.contributor.authorDOMINGOS, D.B.pt_BR
dc.contributor.authorSILVA, A.T.pt_BR
dc.contributor.authorSILVA, J.E.R.pt_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 14thpt_BR
dc.date.accessioned2014-11-17T18:38:29Zpt_BR
dc.date.accessioned2014-11-18T18:59:05Zpt_BR
dc.date.accessioned2015-04-02T04:09:26Z
dc.date.available2014-11-17T18:38:29Zpt_BR
dc.date.available2014-11-18T18:59:05Zpt_BR
dc.date.available2015-04-02T04:09:26Z
dc.date.eventoMarch 21-25, 2010pt_BR
dc.description.abstractNeutronic, thermal-hydraulics and accident analysis calculations were developed to estimate the safety of a miniplate irradiation device (MID) to be placed in the IEAR1 reactor core. The irradiation device will be used to receive miniplates of U3O8-Al and U3Si2-Al dispersion fuels, LEU type (19,9% of 235U) with uranium densities of, respectively, 3.0 gU/cm3 and 4.8 gU/cm3 . The fuel miniplates will be irradiated to nominal 235U burnup levels of 50% and 80%, in order to qualify the above highdensity dispersion fuels to be used in the Brazilian Multipurpose Reactor (RMB), now in the conception phase. For the neutronic calculation, the computer codes CITATION and TWODB were 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 code LOSS and TEMPLOCA, allowing the calculation of the fuel miniplate temperatures after the reactor pool draining. This paper also presents a system designed for fuel swelling evaluation. The determination of the fuel swelling will be performed by means of the fuel miniplate thickness measurements along the irradiation time.
dc.event.siglaRRFM 2010pt_BR
dc.identifier.citationDOMINGOS, D.B.; SILVA, A.T.; SILVA, J.E.R. Qualification process of dispersion fuels in the IEA-R1 research reactor. In: INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 14th, March 21-25, 2010, Marrakech, Morocco. <b>Proceedings...</b> Disponível em: http://repositorio.ipen.br/handle/123456789/17801.
dc.identifier.orcidhttps://orcid.org/0000-0001-7121-6632
dc.identifier.orcidhttps://orcid.org/0000-0002-7308-5784
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/17801pt_BR
dc.local.eventoMarrakech, Moroccopt_BR
dc.rightsopenAccesspt_BR
dc.subjectiear-1 reactorpt_BR
dc.subjectdispersion nuclear fuelspt_BR
dc.subjectswellingpt_BR
dc.titleQualification process of dispersion fuels in the IEA-R1 research reactorpt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorJOSE EDUARDO ROSA DA SILVA
ipen.autorANTONIO TEIXEIRA E SILVA
ipen.autorDOUGLAS BORGES DOMINGOS
ipen.codigoautor137
ipen.codigoautor1085
ipen.codigoautor7482
ipen.contributor.ipenauthorJOSE EDUARDO ROSA DA SILVA
ipen.contributor.ipenauthorANTONIO TEIXEIRA E SILVA
ipen.contributor.ipenauthorDOUGLAS BORGES DOMINGOS
ipen.date.recebimento10-08pt_BR
ipen.event.datapadronizada2010pt_BR
ipen.identifier.ipendoc15593pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublication176dc3e9-77d6-48f1-bec8-49f7e791e96f
relation.isAuthorOfPublication76359599-f842-443b-ab16-8a7caaac1bac
relation.isAuthorOfPublication9fe4d620-da87-4871-9b24-aa27767d4a07
relation.isAuthorOfPublication.latestForDiscovery9fe4d620-da87-4871-9b24-aa27767d4a07
sigepi.autor.atividadeDOMINGOS, D.B.:7482:420:Spt_BR
sigepi.autor.atividadeSILVA, A.T.:1085:420:Npt_BR
sigepi.autor.atividadeSILVA, J.E.R.:137:420:Npt_BR
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