1. Mexican Platform for Analysis and Design of Nuclear Reactors,2015
2. Verification of the Multi-Group Code AZNHEX Using the OECD/NEA UAM Sodium Fast Reactor Benchmark;Ann. Nucl. Energy,2018
3. Verification of the Neutron Diffusion Code AZNHEX by Means of the Serpent-DYN3D and Serpent-PARCS Solution of the OECD/NEA SFR Benchmark,2017
4. Durigen,
S., 2013, “
Neutron Transport in Hexagonal Reactor Cores Modeled by Trigonal-Geometry Diffusion and Simplified P3 Nodal Methods,” Ph.D. thesis,
Karlsruhe Institute of Technology (KIT), Department of Mechanical Engineering, Karlsruhe, Germany.
5. Asymptotic Derivation of the Simplified PN Equations,1993