B. Roque, P. Archier, P. Bourdot, C. De, F. Jean et al., APOLLO3 roadmap for a new generation of simulation tools devoted to the neutronic core calculation of the ASTRID prototype, Proc. Int. Conf. on Fast reactors and related fuel cycles, FR13, 2013.

M. Lainet, V. Bouineau, T. Helfer, and M. Pelletier, Recent modelling improvements in fuel performance code GERMINAL for SFR oxide fuel pins, IAEA-CN-199/241, International Conference on Fast Reactors and Related Fuel Cycles (FR13), 2013.

P. Lamagnère, S. Dardour, R. Santos, A. Freiermuth, M. Marqués et al., objective optimization of subassemblies design towards static mechanical equilibrium of sodium-cooled fast reactor core, 2015.

D. Broc, J. Cardolaccia, and L. Martin, Physical and numerical methods for the dynamic behavior of the fact reactor cores. ASME Pressure Vessel &Piping Division Conference, 2014.

A. Conti, A. Gerschenfeld, and Y. Gorsse, Numerical analysis of core thermal-hydraulic for sodium cooled fast reactors, 16th International Topical Meeting on Nuclear Thermal-Hydraulics (NURETH-16), p.12980, 2015.
URL : https://hal.archives-ouvertes.fr/cea-02489500

M. Chenaud, S. Li, M. Anderhuber, L. Matteo, and A. Gershenfeld, Computational thermal hydraulic shemes for SFR transient studies, 16th International Topical Meeting on Nuclear Thermal-Hydraulics (NURETH-16), p.13084, 2015.

F. Serre, F. Bertrand, C. Journeau, C. Suteau, D. Verwaerde et al., « Status of the French R&D program on the Severe Accident Issue to Develop GENIV SFRs, ICAPP, p.15373, 2015.

J. Rouault, P. Le, J. Coz, J. Garnier, H. Hamy et al., France collaboration on the ASTRID program and sodium fast reactor » ICAPP, p.15440, 2015.