Please use this identifier to cite or link to this item: http://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1034
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dc.contributor.authorMesquita, Amir Zacarias-
dc.contributor.authorRezende, Hugo Cesar-
dc.contributor.authorCosta, Antônio Carlos L. da-
dc.coverage.spatialBelo Horizonte-
dc.date.accessioned2016-08-29T19:21:18Z-
dc.date.available2007-04-15-
dc.date.available2016-08-29T19:21:18Z-
dc.date.issued2005-
dc.identifier.urihttp://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1034-
dc.description.abstractThis work presents the experiments and theoretical analysis to determine the temperature parameter of the uranium zirconium hydride fuel elements, used in the TRIGA IPR-R1 research nuclear reactor.-
dc.language.isoInglês-
dc.publisherCDTN-
dc.rightsL-
dc.subjectTRIGA-Brazil reactor-
dc.subjectheat transfer-
dc.subjectfuel rods-
dc.subjecturanium hydrides-
dc.subjectzirconium hydrides-
dc.titleExperimental determination of heat transfer coeficients in uranium zirconium hydride fuel rod-
dc.typeTrabalho Apresentado em Evento-
dc.coverage.spatialeventoSantos^BSP^CBrazil-
dc.creator.affiliationCentro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil-
dc.creator.affiliationCentro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil-
dc.creator.affiliationCentro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil-
dc.date.evento28 Aug-2 Sep 2005-
dc.identifier.eventoExperimental determination of heat transfer coeeficients in uranium zirconium hydride fuel rod-
dc.title.eventoINAC International Nuclear Atlantic Conference, ENFIR Meeting on Reactor Physics and Thermal Hydraulics, 14-
Appears in Collections:Trabalho apresentado em evento

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