P. Sciora, « A break even oxide fuel core for an innovative french sodium-cooled fast reactor : neutronic Studies Results, 2009.

P. Sciora, Low void effect core design applied on 2400 MWth SFR reactor, Proceedings of ICAPP 2011, 2011.

C. Bouret, Etudes des contre-réactions dans un réacteur à neutrons rapides à caloporteur sodium: impact de la conception et de la neutronique sur les incertitudes, 2014.

A. Gandini, Time-Depend Generalized Perturbation Methods for Burn-up Analysis, Comitato Nazionale per l'Energia Nucleare, 1975.

M. L. Williams, Development of Depletion Perturbation Thoery for Coupled Neutron/Nuclide Fields Feasibility, Nucl. Sci. Eng, vol.118, pp.14-25, 1978.

G. Rimpault, The ERANOS Code and Data System for Fast Reactor Neutronic Analyses, Proc. of the PHYSOR2002, 2002.

T. Zu, C. Yang, L. Cao, and H. Wu, Nuclear data uncertainty propagation analysis for depletion calculation in PWR and FR pin-cells, Annals of Nuclear Energy, vol.94, pp.399-408, 2016.

A. Koning, The JEFF-3.1 Nuclear Data Library, Nuclear Energy Agency Data Bank, vol.21, p.6190, 2006.

C. De and . Jean, Evaluation of Cross-Sections Uncertainties using Physical Constraints Focus on Integral experiments, Nuclear Data Sheet, vol.123, pp.178-184, 2015.

P. Archier, New JEFF-3.2 sodium induced cross-sections evaluation for neutron fast reactors applications: from 0 to 20 MeV, Nuclear Data Sheet, vol.118, pp.140-143, 2014.