Please use this identifier to cite or link to this item: http://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1083

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DC Field	Value	Language
dc.coverage.spatial	Belo Horizonte
dc.date.accessioned	2016-08-29T19:21:26Z	-
dc.date.available	11/01/2011
dc.date.available	2016-08-29T19:21:26Z	-
dc.date.issued	2010
dc.identifier.uri	http://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1083	-
dc.description.abstract	The IPR-R1 TRIGA reactor, located at CDTN (Belo Horizonte/Brazil), is a typical 100 kW Mark I light-water reactor cooled by assisted natural convection with an annular graphite reflector. In order to study the safety aspects connected with the increase of the maximum steady state power of the IPR-R1 TRIGA reactor, experimental measures were taken. This paper summarizes the experimental program and some recent results and procedures of the neutronic and thermalhydraulic experiments carried out in the IPR-R1 TRIGA reactor.
dc.language.iso	Inglês
dc.publisher	CDTN
dc.rights	L
dc.subject	Triga-Brazil reactor
dc.subject	safety
dc.subject	neutron flux
dc.subject	termal hydraulics
dc.type	Trabalho Apresentado em Evento
dc.coverage.spatialevento	Barcelona^BSpain
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	30 May-2 June 2010
dc.identifier.evento	Neutronic and thermal-hydraulic experimental program in the IPR-R1 Triga reactor at CDTN
dc.title.evento	ENC European nuclear confrence
Appears in Collections:	Trabalho apresentado em evento

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