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)