Please use this identifier to cite or link to this item:
http://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1054
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 |
Files in This Item:
There are no files associated with this item.
Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.