Nodal finite element approximations for the neutron transport equation. - Jean-Pierre Hennart; Edmundo del Valle (Math. Comput. Simul., 2010)

Lagrangian Approach for the Study of Heat Transfer in a Nuclear Reactor Core Using the SPH Methodology. - F. Pahuamba-Valdez; E. Mayoral-Villa; Carlos E. Alvarado-Rodríguez; Jaime Klapp; A. M. Gómez-Torres; Edmundo del-Valle-Gallegos (ISUM, 2019)

AZTUSIA: A new application software for Uncertainty and Sensitivity analysis for nuclear reactors. - Melisa Reyes-Fuentes; Edmundo del-Valle-Gallegos; Julian Duran-Gonzalez; Javier Ortíz-Villafuerte; Rogelio Castillo-Durán; Armando Gómez-Torres; Cesar Queral (Reliab. Eng. Syst. Saf., 2021)