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Fast Reactor Core Analysis Using AZNHEX Neutron Diffusion Code

Juan Galicia-Aragon, Juan Luis Francois, Guillermo-Elias Bastida-Ortiz (Univ. Nacioanl Autonoma de Mexico), Edmundo del-Valle-Gallegos (Inst. Politecnico Nacional), Armando Gómez-Torres (Inst. Nacional de Investigaciones Nucleares Carretera Mexico)

Transactions / Volume 116 / Number 1 / June 2017 / Pages 1213-1216

Reactor Physics

 
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