Please use this identifier to cite or link to this item: http://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1054
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dc.contributor.authorDalle, Hugo Moura
dc.coverage.spatialBelo Horizonte
dc.date.accessioned2016-08-29T19:21:22Z-
dc.date.available200610
dc.date.available2016-08-29T19:21:22Z-
dc.date.issued2003
dc.identifier.urihttp://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1054-
dc.description.abstractThis report presents the criticality safety calculations carried out for the Latin American interim storage and transportation cask. Such cask is being designed to spent fuel elements of research reactors in the region. The Monte Carlo transport code MCNP4B was utilized in the analyses,
dc.language.isoInglês
dc.publisherCDTN
dc.rightsL
dc.subjectResearch reactors
dc.subjectspent fuels
dc.subjectcriticality
dc.subjectcasks
dc.subjectcomputer codes
dc.subjectm codes
dc.titleCriticality safety analysis of the Latin American cask for transportation and interim storage of spent fuel from research reactors
dc.typeTrabalho Apresentado em Evento
dc.coverage.spatialeventoBelo Horizonte^BMG^CBrazil
dc.creator.affiliationCentro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil
dc.date.eventoMay 2003
dc.title.eventoRegional workshop on options for storage of spent fuel from research reactor
Appears in Collections:Trabalho apresentado em evento

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