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