J. Rouault and A. , The SFR GENIV Technology Demonstrator Project: Where are we Where Do We Stand For?, Proceeding of ICAPP 2015, 2015.
URL : https://hal.archives-ouvertes.fr/cea-02509083

G. Keyser and J. Papin, The reactivity risk in fast reactors and the related international experimental programmes CABRI and SCARABEE, Progr. Nucl. Energ, vol.32, pp.631-638, 1998.

K. Konishi, The EAGLE project to eliminate the recriticality issue of fast reactors-progress and results of in-pile tests, Proceedings of the Fifth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS5), pp.465-471, 2006.

Y. S. Vassiliev, A. D. Vurim, V. A. Gaidachuk, A. A. Kolodeshnikov, V. Pakhnits et al., Research on problems of safety of Nuclear Power Reactors in the IGR Reactor: the Results of Medium-Scale Experiments Realised under the EAGLE Project, Proc. 13th Int Conf on Radiation Physics and Chemistry of Inorganic Materials, 2006.

C. Venard, The ASTRID core at the Midtime of the Conceptual Design Phase (AVP2), Proceeding of ICAPP 2015, 2015.

T. Suzuki, A preliminary evaluation of unprotected loss-of-flow accident for a prototype fastbreeder reactor, Nuclear Engineering and Technology, vol.47, pp.240-252, 2015.

H. Yamano, Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor, Science and Technology of Nuclear Installations, vol.2012

A. Bachrata, Unprotected Loss of Flow Simulation on ASTRID CFV V3 core, Proceeding of ICAPP 2015, 2015.

F. Serre, Status of the French R&D program on the Severe Accident Issue to Develop GENIV SFRs, Proceeding of ICAPP 2015, 2015.

G. Gaillard-groleas, Improvement in simulation tools to be developed within the framework of the ASTRID Project, Phenomenological analyses of corium propagation in LWRs: the PROCOR software platform, p.2015, 2016.

S. Kondo, SIMMER-III: An Advanced Computer Program for LMFBR Severe Accident, ANP'92, pp.40-45, 1992.

H. Yamano, Development of a threedimensional CDA analysis code: SIMMER-IV and its first application to reactor case, Nuclear Engineering and Design, vol.238, issue.1, pp.66-79, 2008.

J. Rouault, A. , and F. -. , Japan collaboration on ASTRID Program and Sodium Fast Reactor, Proceeding of ICAPP 2015, 2015.
URL : https://hal.archives-ouvertes.fr/cea-02506803

D. P. Weber, The SAS4A LMFBR Accident Analysis Code System, ANL/RAS, pp.83-121, 1988.

G. Berthoud and B. Duret, The freezing of molten Fuel : Reflections and new results', NURETH4 Conference, 1989.

G. Berthoud, H. Jacobs, and J. B. Knowles, Large scale fuel-sodium interactions: synthesis of European programs, Fast Reactor Coordinating Committee / Safety Working Group, vol.375, 1994.

C. Fochesato, Implementation of the Implicit-Continuous-Eulerian scheme for multiphase flows in the parallel DUNE framework, Proceeding of 2016 International Conference on Multiphase Flow

A. Dedner, R. Klöfkorn, M. Nolte, and M. Ohlberger, A generic interface for parallel and adaptive scientific computing: Abstraction principles and the DUNE-FEM module, Computing, vol.90, issue.3, pp.165-196, 2011.

G. Willermoz, C. Journeau, C. Suteau, J. F. Haquet, P. Piluso et al., PLINIUS-2 : A versatile platform for severe accident mitigation device and simulation assessments, Proceedings of ICAPP, 2014.

, Proceedings of ICAPP, 2016.

C. Journeau, L. Buffe, N. Cassiaut-louis, V. Bouyer, J. F. Haquet et al., PLINIUS 2 : A new versatile platform for Severe Accident Assesments, Proc. NUTHOS-10, 2014.

D. Magallon, H. Hohmann, and H. Schins, Pouring of 100-kg-scale molten UO 2 into sodium, Nucl. Technol, vol.98, pp.79-90, 1992.

S. Kondo, Experimental study on simulated molten jet-coolant interactions, Nuclear Engineering and Design, vol.155, pp.73-84, 1995.

V. Natarajan and K. Ravichandran, Experimental and Analytical Simulation of MFCI (Molten Fuel Coolant Interaction) during CDA (Core Disruptive Accident) in Sodium Cooled Fast Reactor