Please use this identifier to cite or link to this item: http://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1018

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DC Field	Value	Language
dc.coverage.spatial	Belo Horizonte
dc.date.accessioned	2016-08-29T19:21:14Z	-
dc.date.available	200704
dc.date.available	2016-08-29T19:21:14Z	-
dc.date.issued	2006
dc.identifier.uri	http://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1018	-
dc.description.abstract	The heat generated by nuclear fission is transferred from fuel elements to the cooling system through the fuel-to-cladding gap and the cladding to coolant interfaces. The fuel thermal conductivity and the heat transfer coefficient from the cladding to the coolant were evaluated experimentally. Results of this study indicated that subcooled boiling occurs at the cladding surface in the central channels of the reactor core at power levels approximately 60kW.
dc.language.iso	Inglês
dc.publisher	CDTN
dc.rights	L
dc.subject	Brazil-TRIGA reactor
dc.subject	heat trabsfer
dc.type	Trabalho Apresentado em Evento
dc.coverage.spatialevento	Belo Horizonte^BMG^CBrazil
dc.creator.affiliation	Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil
dc.creator.affiliation	Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil
dc.date.evento	22-25 Aug 2006
dc.identifier.evento	Experimental heat transfer analysis of the IPR-R1 TRIGA reactor
dc.title.evento	World TRIGA users conference, 3
Appears in Collections:	Trabalho apresentado em evento

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