1. Aniel, S., et al. 2005. Flica4: Status of Numerical and Physical Models and Overview of Applications, en International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH11). Thermal-Hydraulics Division of the American Nuclear Society
2. The analytic coarse-mesh finite difference method for multigroup and multidimensional diffusion calculations;Aragones;Nucl. Sci. Eng.,2007
3. Basile, D., Chierici, R., Beghi, M., Salina, E., Brega, E., 1999. COBRA-EN, an Updated Version of the COBRA-3C/MIT Code for Thermal-Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores. Report 1010/1, ENEL-CRTN Compartimento di Milano.
4. Baudron, A.M., et al. 2006. CRONOS2.7 Reference Manual, Inf. Téc., SERMA/LENR/RT/06-3980/A CEA Saclay.
5. Beckert, C., Koch, R., 2005. Reactor cell calculations with the codes HELIOS, MCNP and TRANSFAY: Comparison of the results. Annual Report 2004 – Wissenschaftlich-Technische Berichte: FZR 155.