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A. Santamarina and D. Bernard, The JEFF-3.1.1 Nuclear Data Library, 2009.
URL : https://hal.archives-ouvertes.fr/cea-02386210

M. B. Chadwick and P. Oblozinsky, ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology, Nuclear Data Sheets, vol.107, 2006.

P. Leconte, G. Truchet, J. Vidal, A. Santamarina, and P. Blaise, Validation of the APOLLO2.8 code package for the calculation of ?eff and kinetics parameters and the Inhour relation ? = f(T) based on the IPEN/MB-01 experiments, Proc. PHYSOR2016, 2016.
URL : https://hal.archives-ouvertes.fr/cea-02438724

A. Santamarina, P. Blaise, and L. Erradi, Calculation of LWR Kinetic Parameter ?eff. Validation on the MISTRAL Experiments, Annals of Nuclear Energy, vol.48, 2012.

A. Santamarina, V. Pascal, G. Truchet, and J. Vidal, Validation of LWR reactivity versus reactor period. Feedback on the delayed neutron data, Proc. Conf PHYSOR, 2018.
URL : https://hal.archives-ouvertes.fr/hal-02416252

G. D. Spriggs, J. M. Campbell, and V. M. Piksaikin, An 8-group delayed neutron model based on a consistent set of half-lives, Progress in Nuclear Energy, vol.41, pp.223-251, 2002.

G. R. Keepin, Physics of Nuclear Kinetics

R. J. Tuttle, Delayed neutron Data for Reactor Physics Analysis, Nucl. Sci. and Eng, vol.56, 1979.

S. Cathalau, P. Fougeras, P. Blaise, A. Santamarina, O. Litaize et al., Full MOX recycling in ALWR : Lessons drawn through the MISTRAL program, Proc. Conf PHYSOR 2002, Seoul (Korea), 2002.

O. Litaize, A. Santamarina, and C. Chabert, Analysis of the MISTRAL experiment with APOLLO2. Qualification of neutronic parameters of UOX and MOX cores, Proc. Conf PHYSOR 2002, Seoul (Korea), 2002.

G. Truchet, P. Leconte, A. Santamarina, E. Brun, F. Damian et al., Computing adjoint-weighted kinetics parameters in TRIPOLI-4 ® by the Iterated Fission Probability method, Ann. Nucl. Energy, vol.85, pp.17-26, 2015.
URL : https://hal.archives-ouvertes.fr/cea-02387020

A. Santamarina, D. Bernard, P. Blaise, P. Leconte, J. Palau et al., Validation of the new code package APOLLO2.8 for accurate PWR neutronics calculations, Proc M&C, vol.2013, 2013.

R. Sanchez, APOLLO2 Year 2010, Nucl. Eng. & Technology, vol.42, p.474, 2010.

N. Hfaiedh and A. Santamarina, Determination of the Optimized SHEM Mesh for Neutron Transport Calculation, Proc. M&C2005, 2005.

J. Both, Treatment of Cross Section Uncertainties in the Transport Monte Carlo Code TRIPOLI4, Journal of Nuclear Science and Technology, Supplement, vol.1, pp.420-422, 2000.

S. F. Mughabghab, Atlas of Neutron Resonances, 2006.