. Cd-adapco, STAR-CCM+ User Guide Version 9, p.2

P. and L. Coz, Sodium-Cooled Fast Reactors: the ASTRID Plant Project, Proceedings o f ICAPP 2011, 2011.

G. S. Was, Fundamentals of radiation materials science, Metals and alloys, 2007.

N. Schmidt, Endommagement de la gaine des éléments combustibles du réacteur à neutron s rapides PHENIX. Réalisation et analyse d'expériences de chargement limite. Validation et optimisation de la méthodologie de dimensionnement RAMSES 2, 1992.

E. Baglietto, A quantitative CFD benchmark for Sodium Fast Reactor fuel assembly modeling, Annals of Nuclear Energ y, vol.64, pp.32-42, 2014.

W. Pointer, RANS-based CFD simulations of sodium fast reactor wire-wrapped pin bundles, American Nuclear Society -International Conference on Mathematics. Computatio nal Methods and Reactor Physics, vol.4, pp.2212-2224, 2009.

K. D. Hamman, A CFD simulation process for fast reactor fuel assemblies, Idaho N ational Laboratory, P.O. Box, vol.1625, pp.2304-2312, 2010.

P. Petiot and J. Seiler, Physical properties of sodium : a contribution to the estimation of cr itical coordinates, High Temperature and High Pressure, vol.16, pp.289-293, 1984.

. Smith, Predictions in CFD simulations of wire-wrapped SFR fuel assemblies, 2009.

S. K. Chen, N. Todreas, and N. Nguyen, Evaluation of existing correlations for the pred iction of pressure drop in wire-wrapped hexagonal array pin bundles, Nuclear Engineering and Design, vol.267, pp.109-131, 2014.

N. E. Todreas and K. S. Mujid, Nuclear Systems II : Elements of thermal hydraulic design, 1990.

E. Bubelis and M. Schikorr, Review and proposal for best fit of wire-wrapped fuel bundle fri ction factor and pressure drop predictions using various existing correlations, Nuclear Engi neering and Design, vol.238, pp.3299-3320, 2008.

M. P. Surth, J. Sturgeon, and W. Wolfer, Radiation swelling behavior and its dependence on temperature, dose rate, and dislocation structure evolution, Journal of Nuclear Materials, vol.336, pp.217-224, 2004.

M. and L. Flem, French R&D on materials for the core components of Sodium Fast R eactors, 2013.

F. Acosta, Evaluation of thermal-hydraulics and thermomechanics coupling strategies for the modeling of the performance of fuel assemblies of Sodium-cooled Fast Reactors under irradiation, 2018.

G. Gaillard-groleas, New simulation tools to be developed for the ASTRID program, 2014.