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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|
|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,|
|Appears in Collections:||Trabalho apresentado em evento|
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