Evaluation of mechanical stability of nuclear fuel plates under axial flow conditions

dc.contributor.advisorMiguel Mattar Netopt_BR
dc.contributor.authorMANTECON, JAVIER G.
dc.coverageNacionalpt_BR
dc.date.accessioned2019-04-18T19:40:04Z
dc.date.available2019-04-18T19:40:04Z
dc.date.issued2019pt_BR
dc.description.abstractSeveral nuclear research reactors use or are planned with cores containing flat-plate- type fuel elements. The nuclear fuel is contained in parallel plates that are separated by narrow channels through which the fluid flows to remove the heat generated by fission reactions. One of the problems of this fuel element design is the mechanical stability of the fuel plates. High-velocity coolant flowing through the channels can cause large deflections of these plates leading to local overheating, structural failure or plate collapse. As a consequence, the safe operation of the reactor may be affected. In this work, a numerical fluid-structure interaction study was conducted for evaluating the mechanical stability of nuclear fuel plates under axial flow conditions. Five different cases were analyzed. In all cases, the system consisted of two fuel plates bounded by fluid channels but, in case 5, a support comb at the leading edge of the plates was inserted. The pressure loadings caused by the fluid flow were calculated using a Computational Fluid Dynamics model created with ANSYS CFX. The structural response was determined by means of a Finite Element Analysis model generated with ANSYS Mechanical. Both models were coupled using the two-way fluid-structure interaction approach. The results from Case 1 allowed proposing a methodology to predict the critical velocity of the assembly without an inlet support comb. The maximum deflection of the plates was detected at their leading edges. It was detected that, for flow rates in the channels less than a certain value, the maximum deflection increased linearly with the square of the coolant velocity. In contrast, for greater flow rates, a nonlinear behavior was observed. Therefore, that fluid velocity was identified as the critical velocity of the system. Besides, above the critical velocity, an extra deflection peak was observed near the trailing edge of the plates. In cases 2, 3 and 4, the influence of manufacturing deviations and the change of materials properties due to the increment of temperature on the critical velocity was investigated. With these conditions, the critical velocity of the system was found at lower values. Lastly, in Case 5, the effectiveness of using a support comb at the leading edge of the plates was investigated. The results showed that the static divergence at the inlet end is effectively eliminated with the installation of the comb. In addition, the flow-induced deflections along the length of the plates were significantly diminished with the comb.pt_BR
dc.description.notasgeraisTese (Doutorado em Tecnologia Nuclear)pt_BR
dc.description.notasteseIPEN/Tpt_BR
dc.description.sponsorshipCoordenação de Aperfeiçoamento de Pessoal de Nível Superior (CAPES)
dc.description.sponsorshipIDCAPES: 88882.333453/2019-01
dc.description.teseinstituicaoInstituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SPpt_BR
dc.format.extent102pt_BR
dc.identifier.citationMANTECON, JAVIER G. <b>Evaluation of mechanical stability of nuclear fuel plates under axial flow conditions</b>. Orientador: Miguel Mattar Neto. 2019. 102 f. Tese (Doutorado em Tecnologia Nuclear) - Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP, São Paulo. DOI: <a href="https://dx.doi.org/10.11606/T.85.2019.tde-18032019-164244">10.11606/T.85.2019.tde-18032019-164244</a>. Disponível em: http://repositorio.ipen.br/handle/123456789/29866.
dc.identifier.doi10.11606/T.85.2019.tde-18032019-164244
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/29866
dc.localSão Paulopt_BR
dc.rightsopenAccesspt_BR
dc.subjectnuclear fuels
dc.subjectplates
dc.subjectfluid flow
dc.subjecttransition heat
dc.subjecttemperature distribution
dc.subjectaxial-vector currents
dc.subjectmechanical structures
dc.subjectfuel-coolant interactions
dc.subjectthermal degradation
dc.subjectfinite element method
dc.subjectnumerical solution
dc.subjectcomputer calculations
dc.subjectcomputerized simulation
dc.subjectreactor operation
dc.subjectfuel element failure
dc.subjectresearch reactors
dc.titleEvaluation of mechanical stability of nuclear fuel plates under axial flow conditionspt_BR
dc.title.alternativeAvaliação de estabilidade mecânica de placas de combustível nuclear sob condições de fluxo axialpt_BR
dc.typeTesept_BR
dspace.entity.typePublication
ipen.autorJAVIER GONZALES MANTECON
ipen.codigoautor14222
ipen.contributor.ipenauthorJAVIER GONZALES MANTECON
ipen.date.recebimento19-04pt_BR
ipen.identifier.ipendoc25642pt_BR
ipen.meioeletronicohttp://www.teses.usp.br/teses/disponiveis/85/85133/tde-18032019-164244/pt-br.phppt_BR
ipen.type.genreTese
relation.isAuthorOfPublication26c32a1b-ab2b-411c-b2f7-8e2474177393
relation.isAuthorOfPublication.latestForDiscovery26c32a1b-ab2b-411c-b2f7-8e2474177393
sigepi.autor.atividadeMANTECON, JAVIER G.:14222:420:Spt_BR

Licença do Pacote

Agora exibindo 1 - 1 de 1
Carregando...
Imagem de Miniatura
Nome:
license.txt
Tamanho:
1.71 KB
Formato:
Item-specific license agreed upon to submission
Descrição:

Coleções