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|metadata.dc.title.evento:||Workshop on characterization of spent fuel, 2|
|Affiliation:||Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil|
|Keywords:||Research reactors;spent fuels;computer codes;m codes;o codes|
|Abstract:||Monte Carlo simulation of the RA-3 research reactor with Monteburns code system is presented in this paper. Monteburns is an automated computational tool that links the Monte Carlo code MCNP with the burnup anddecay code ORIGEN2.1. The characterization of an U3Si2-A1 MTR fuel assembly prototype irradiated in this reactor is carried out. Calculated values of mass of several nuclides, activity, heatload and radiotoxicities of the prototype after burning its fuel are presented.|
|Appears in Collections:||Trabalho apresentado em evento|
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