M. S. Chenaud, N. Devictor, G. Mignot, F. Varaine, C. Vénard et al., Nuclear Engineering and Technology, vol.45, issue.6, pp.721-730, 2013.

A. Koning, C. Dean, U. Fischer, and R. Mills, Validation of the JEFF-3.1 Nuclear Data Library, vol.23, 2013.

A. Santamarina, D. Bernard, P. Blaise, M. Coste, A. Courcelle et al., , 2009.

E. Brun, E. Dumonteil, F. X. Hugot, N. Huot, Y. K. Lee et al., « Overview of TRIPOLI-4® version 7 Continuous-Energy Monte Carlo Transport Code, Proceedings of ICAPP 2011, 2011.

R. Letellier, C. Suteau, D. Fournier, J. M. Ruggieri, and . High, Order Discrete Ordinate Transport in Hexagonal Geometry: a New Capability in ERANOS, Il Nuovo Cimento, p.33, 2010.

. Oecd/nea, Handbook of Evaluated Criticality Safety Benchmark Evaluation Experiments, p.3, 2012.

. Oecd/nea, Handbook of Evaluated Reactor Physics Benchmark Experiments, 2013.

I. Kodeli, E. Sartori, and B. Kirk, SINBAD Shielding Benchmark Experiments -Status and Planned Activities

, Biennial Topical Meeting of the Radiation Protection and Shielding Division, 2006.

P. Fougeras, A. Chabre, and C. Mergui, « The place of EOLE, MINERVE and MASURCA facilities in the R&D Activities of the CEA, vol.10, 2005.

W. Assal, J. C. Bosq, and F. Mellier, « Experimental Measurements at the MASURCA Facility, IEEE Trnasactions on Nuclear Science, vol.59, issue.6, pp.3180-3188, 2012.

J. Gourdon, B. Mesnage, J. L. Voitellier, and M. Suescun, « An Overview of Superphénix Commissioning Tests, vol.106, pp.1-10, 1990.

A. J. Koning, S. Hilaire, M. C. Duijvestijn, and «. Talys, International Conference on Nuclear Data for Science and Technology ND2007, 2007.

P. Archier, C. De-saint-jean, O. Litaize, G. Noguère, L. Berge et al., Evaluation Code : Development Status and Perspectives, Nuclear Data Sheets, vol.118, pp.488-490, 2014.

B. Habert, C. De-saint-jean, G. Noguère, L. Leal, and Y. Rugama, « Retroactive Generation of Covariance Matrix of Nuclear Model Parameters using Marginalization Techniques, Nuclear Science and Engineering, vol.166, pp.276-287, 2010.

N. M. Larson, Updated users' guide for SAMMY : Multilevel R-Matrix fits to neutron data using Bayes' equations, ORNL Report ORNL, 2008.

D. Bernard, O. Fabbris, and . Post, Irradiation Experiment Analysis using the APOLLO-2 deterministic tool -Validation of JEFF-3.1.1 thermal and epithermal actinides neutron induced cross sections through MELUSINE experiments, 2012.

D. Bernard, O. Bouland, and . Americium, 241 phase I: reevaluation for JEFF-3.1.1 and a step forward, Journal of Nuclear Science and Technology, vol.40, issue.1, pp.132-166, 2012.

P. Archier, « New JEFF-3.2 Sodium Neutron Induced Cross-sections Evaluation for Neutron Fast Reactors Applications : from 0 to 20 MeV, Nuclear Data Sheets, vol.118, pp.140-143, 2014.

M. B. Chadwick, ENDFB-VII.1 Nuclear Data for Science and Technology : Cross Sections, Covariances, Fission Product Yields and Decay Data», Nuclear Data Sheets, vol.112, pp.2887-2996, 2011.

B. Morillon, R. Lazauskas, and J. Carbonell, « Influence of ab-initio nd cross sections in the critical heavy water benchmarks, Annals of Nuclear Energy, vol.54, pp.167-177, 2013.

C. J. Diez, A. Stankovskiy, E. Malambu, G. Zerovnik, P. Schillebeeckx et al., « Review of the nat C(n, g) cross section and criticality calculations of the graphite moderator reactor BR1, Annals of Nuclear Energy, vol.60, pp.210-217, 2013.

T. Ware, Measurement and analysis of the resolved resonance cross sections of the natural Hafnium isotopes, 2010.

P. Pereslavtsev, A. Konobeyev, U. Fischer, and L. Leal, « Evaluation of 50 Cr, 52 Cr, 30 Cr, 40 Cr Neutron Cross Sections Data for Energies up to 200 MeV, Journal of the Korean Physical Society, vol.59, pp.931-934, 2011.

J. C. Sublet, P. Ribon, and M. Coste-delclaux, User manual for CALENDF-2005», Rapport CEA Cadarache CEA-R6131, 2006.

G. Truchet, P. Leconte, Y. Pénéliau, A. Santamarina, and F. Malvagi, « Continuous-Energy Adjoint Flux and Perturbation Calculations using the Iterated Fission Probability Method in Monte Carlo TRIPOLI-4® and Underlying Applications, 2013.

G. Rimpault, « Algorithmic features of the ECCO cell code for treating heterogeneous fast reactor assemblies, 1995.

J. M. Ruggieri, J. Tommasi, J. F. Lebrat, C. Suteau, D. Plisson-rieunier et al., Sublet, «ERANOS 2.1 : International Code System for GEN IV Fast Reactor Analysis, 2006.

R. E. Macfarlane and D. M. Muir, « NJOY-99.0 : Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data, 2000.

J. F. Sauvage and «. Phenix, 30 years of history -The Heart of a reactor, 2004.