N. Alpy, Phenomenological Investigation of Sodium Boiling in a SFR Core during a postulated ULOF Transient with CATHARE 2 System Code: a Stabilized Boiling Case, Journal of Nuclear Science and Technology, vol.53, issue.5, pp.692-697, 2015.

J. M. Seiler, Sodium boiling stabilisation in a fast breeder subassembly during an unprotected loss of flow accident, Nuclear Engineering and Design, vol.240, pp.3329-3335, 2010.

D. Tenchine, Status of CATHARE code for sodium cooled fast reactors, Nuclear Engineering and Design, vol.245, pp.140-152, 2012.

D. Bestion, The physical closure laws in the CATHARE code, Nuclear Engineering and Design, vol.124, issue.3, pp.229-245, 1990.

R. Lockhart and R. Martinelli, Proposed correlation of data for isothermal two phase, two component flow in pipes, Chemical Engineering progress, vol.45, 1949.

H. M. Kottowski, Liquid metal thermal hydraulics, 1994.

E. Skupinski, Détermination des coefficients de convection d'un alliage sodium-potassium dans un tube circulaire, International Journal of Heat and Mass Transfer, vol.8, pp.937-951, 1965.

H. Ninokata, Six equation two phase flow model code SABENA for sodium boiling simulation, Grenoble, 11th meeting of the liquid metal boiling working group, 1991.

J. Perez, CATHARE 2 simulations of steady state air/water tests performed in a 1:1 scale SFR sub-assembly mock-up, Annals of nuclear Energy, vol.83, pp.283-297, 2015.

A. Chenu, Single-and Two-Phase Flow Modeling for Coupled Neutronics / Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors, 2011.

P. R. Blasius, Das Aehnlichkeitsgesetz bei Reibungsvorgangen in Flüssigkeiten, Mitteilung 131 über Forschungsarbeiten auf dem Gebiete des Ingenieurwesens, pp.1-41, 1913.

K. Rehme, Pressure drop correlations for fuel element spacers, Nuclear Technology, vol.17, issue.1, p.1973, 1973.

M. Anderhuber, Simulation of GR19 sodium boiling experiments with CATHARE-2 system code and TRIO_U MC subchannel code, 2015.

K. Haga, Decay heat removal under boiling condition in a pin-bundle geometry, 9th meeting of the liquid metal boiling working group, 1980.

K. Haga, Sodium Boiling Experiment in a 37-Pin Bundle under Loss-of-Flow Conditions, 10th meeting of the liquid metal boiling working group, 1982.

Y. Y. Vinogradova, SOCRAT-BN simulation of SIENA Loss Of Flow experiments, 2015.

H. Ninokata, Analysis of low-heat-flux sodium boiling test in a 37-pin bundle by the two-fluid model computer code SABENA, Nuclear Engineering and Design, vol.97, pp.233-246, 1986.