Experimental investigation of critical velocity in fuel element for the RMB reactor

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dc.contributor.authorCASTRO, ALFREDO J.A. de
dc.contributor.authorANDRADE, DELVONEI A. de
dc.coverageInternacionalpt_BR
dc.creator.eventoBRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17thpt_BR
dc.date.accessioned2019-03-01T11:51:29Z
dc.date.available2019-03-01T11:51:29Z
dc.date.eventoNovember 25-28, 2018pt_BR
dc.description.abstractThe fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminum-coated fuel plates containing the core of uranium silica (U3Si2) dispersed in an aluminum matrix. These plates have a thickness of the order of millimeters and are much longer in relation to their thickness. They are arranged in parallel inside the fuel element assembly to form channel gaps between them of only a few millimeters wide through which the coolant flows. This configuration, combined with the need for a flow at high flow rates to ensure the cooling of the fuel element in operation, may create problems of mechanical failure of fuel plate due to the vibration induced by the flow in the channels. In the case of critical velocity, excessive permanent deflections of the plates can cause blockage of the flow channel in the reactor core and, lead to overheating in the plates. For this work an experimental loop capable of high volume flows and a test section that simulates a plate-like fuel element with three cooling channels was developed. The dimensions of the test section were based on the dimensions of the Fuel Element of the Brazilian Multipurpose Reactor (RMB), whose project is being coordinated by the National Commission of Nuclear Energy (CNEN). The experiments performed had the objective of reaching Miller's critical velocity condition. The critical velocity was reached with 14.5 m/s leading to the consequent plastic deformation of the flow channel plates.pt_BR
dc.description.sponsorshipConselho Nacional de Desenvolvimento Científico e Tecnológico (CNPq)pt_BR
dc.description.sponsorshipIDCNPq: 481193/2012-0pt_BR
dc.event.siglaENCITpt_BR
dc.identifier.citationCASTRO, ALFREDO J.A. de; ANDRADE, DELVONEI A. de. Experimental investigation of critical velocity in fuel element for the RMB reactor. In: BRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17th, November 25-28, 2018, Águas de Lindóia, SP. <b>Proceedings...</b> Rio de Janeiro: Associação Brasileira de Engenharia e Ciências Mecânicas, 2018. Disponível em: http://repositorio.ipen.br/handle/123456789/29743.
dc.identifier.orcidaguardandopt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-6689-3011
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/29743
dc.localRio de Janeiropt_BR
dc.local.eventoÁguas de Lindóia, SPpt_BR
dc.publisherAssociação Brasileira de Engenharia e Ciências Mecânicaspt_BR
dc.rightsopenAccesspt_BR
dc.subjectcritical velocity
dc.subjectdeformation
dc.subjectexperimental data
dc.subjectfluid flow
dc.subjectfuel assemblies
dc.subjectfuel plates
dc.subjectmtr reactor
dc.subjectrmb reactor
dc.subjectreactor cores
dc.subjectnuclear fuels
dc.subjectfuel elements
dc.titleExperimental investigation of critical velocity in fuel element for the RMB reactorpt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorDELVONEI ALVES DE ANDRADE
ipen.autorALFREDO JOSE ALVIM DE CASTRO
ipen.codigoautor1258
ipen.codigoautor1255
ipen.contributor.ipenauthorDELVONEI ALVES DE ANDRADE
ipen.contributor.ipenauthorALFREDO JOSE ALVIM DE CASTRO
ipen.date.recebimento19-03pt_BR
ipen.event.datapadronizada2018pt_BR
ipen.identifier.ipendoc25523pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublication0eeb4436-68e5-4573-a603-35f5fc912178
relation.isAuthorOfPublicationaf144b86-4313-42af-ba10-fcebb8fa4463
relation.isAuthorOfPublication.latestForDiscoveryaf144b86-4313-42af-ba10-fcebb8fa4463
sigepi.autor.atividadeCASTRO, ALFREDO J.A. DE:1255:420:Spt_BR
sigepi.autor.atividadeANDRADE, DELVONEI A. DE:1258:420:Npt_BR
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