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Title: Criticality safety analysis of the Latin American cask for transportation and interim storage of spent fuel from research reactors
metadata.dc.title.evento: Regional workshop on options for storage of spent fuel from research reactor
Authors: Dalle, Hugo Moura
Affiliation: Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil
Issue Date: 2003
Keywords: Research reactors;spent fuels;criticality;casks;computer codes;m codes
Abstract: This 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,
Access: L
Appears in Collections:Trabalho apresentado em evento

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