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|Title:||Shielding and criticality safety analyses of a Latin American cask for transportation and interim storage of spent fuel from research reactors|
|metadata.dc.title.evento:||International conference on research reactor utilization, safety, decommissioning, fuel and waste management|
|Authors:||Dalle, Hugo Moura|
|Affiliation:||Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil|
Universidade Estadual de Campinas/UNICAMP, SP, Brasil
|Keywords:||Spent fuel;research reactors;casks;shielding;criticality;safety analysis;computer codes|
|Abstract:||Shieldind and criticality safety calculations carried out for the Latin American interim storage and transportation cask are presented. Such dual purpose cask is being designed to the spent fuel elements of research reactors in the region. The Monte Carlo transport code MCNP4B was utilized for the criticality safety analysis part and SCALE4.4A for shielding. The analyses considered two types of fuel assemblies utilized in the region and the results show that both types can be loaded in the designed cask baskets in compliance with the safety criteria.|
|Appears in Collections:||Trabalho apresentado em evento|
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