A. Saxena, Thermal-hydraulic numerical simulation of fuel sub-assembly for Sodium-cooled Fast Reactor, 2014.

D. Tenchine, Status of Trio_U code for sodium cooled fast reactors, Nuclear Engineering and Design, vol.242, pp.307-315, 2012.

M. S. Chenaud, Computational thermal hydraulics schemes for SFR transients studies, vol.16, 2015.

G. Geffraye, CATHARE 2 V2.5_2: A single version for various applications, Nuclear Engineering and Design, vol.241, pp.4456-4463, 2011.

R. Lavastre, State of the Art of CATHARE Model for Transient safety Analysis of ASTRID SFR, Proceedings of NUTHOS-10, 2014.