, Nuclear Engineering and Technology, vol.45, issue.6, pp.721-730, 2013.
, Validation of the JEFF-3.1 Nuclear Data Library, vol.23, 2013.
, , 2009.
« Overview of TRIPOLI-4® version 7 Continuous-Energy Monte Carlo Transport Code, Proceedings of ICAPP 2011, 2011. ,
Order Discrete Ordinate Transport in Hexagonal Geometry: a New Capability in ERANOS, Il Nuovo Cimento, p.33, 2010. ,
Handbook of Evaluated Criticality Safety Benchmark Evaluation Experiments, p.3, 2012. ,
Handbook of Evaluated Reactor Physics Benchmark Experiments, 2013. ,
, SINBAD Shielding Benchmark Experiments -Status and Planned Activities
, Biennial Topical Meeting of the Radiation Protection and Shielding Division, 2006.
« The place of EOLE, MINERVE and MASURCA facilities in the R&D Activities of the CEA, vol.10, 2005. ,
« Experimental Measurements at the MASURCA Facility, IEEE Trnasactions on Nuclear Science, vol.59, issue.6, pp.3180-3188, 2012. ,
, « An Overview of Superphénix Commissioning Tests, vol.106, pp.1-10, 1990.
, International Conference on Nuclear Data for Science and Technology ND2007, 2007.
Evaluation Code : Development Status and Perspectives, Nuclear Data Sheets, vol.118, pp.488-490, 2014. ,
« Retroactive Generation of Covariance Matrix of Nuclear Model Parameters using Marginalization Techniques, Nuclear Science and Engineering, vol.166, pp.276-287, 2010. ,
Updated users' guide for SAMMY : Multilevel R-Matrix fits to neutron data using Bayes' equations, ORNL Report ORNL, 2008. ,
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. ,
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. ,
« 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. ,
, 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.
« Influence of ab-initio nd cross sections in the critical heavy water benchmarks, Annals of Nuclear Energy, vol.54, pp.167-177, 2013. ,
« 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. ,
Measurement and analysis of the resolved resonance cross sections of the natural Hafnium isotopes, 2010. ,
« 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. ,
, User manual for CALENDF-2005», Rapport CEA Cadarache CEA-R6131, 2006.
« Continuous-Energy Adjoint Flux and Perturbation Calculations using the Iterated Fission Probability Method in Monte Carlo TRIPOLI-4® and Underlying Applications, 2013. ,
« Algorithmic features of the ECCO cell code for treating heterogeneous fast reactor assemblies, 1995. ,
Sublet, «ERANOS 2.1 : International Code System for GEN IV Fast Reactor Analysis, 2006. ,
« NJOY-99.0 : Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data, 2000. ,
30 years of history -The Heart of a reactor, 2004. ,