J. P. Van-dorsselaere, Technical Area 2 -Severe Accidents, 2013.

G. Bruna, Identification of Research Areas in response to the Fukushima Accident, SNE-TP Report, 2013.

, Global Vision report, Nuclear Gen II and III Association, 2015.

A. Miassoedev, Severe Accident Facilities for European Safety Targets. The SAFEST Project, Proc. ERMSAR, 2015.

W. Klein-hessling, Conclusions on severe accident research priorities, Ann. Nucl. Ener, vol.74, pp.4-11, 2014.

A. Suzuki, K. Sato, and T. Terei, Thermodynamic calculation on possible chemical forms of released fission products from failed fuel rod in severe accident conditions, 2nd Asian Nuclear Fuel Cycle Conference (ANFC2014), 2014.

M. Steinbrück, M. Grosse, L. Sepold, and J. Stuckert, Synopsis and outcome of the QUENCH experimental programme, Nucl. Eng. Des, vol.240, pp.1714-1727, 2010.

Z. Hozer, Quenching of high temperature VVER fuel after long term oxidation in hydrogen rich steam, Nucl. Eng. Des, vol.37, pp.71-82, 2010.

A. Karbojian, W. Ma, P. Kudinov, and T. N. Dinh, A scoping study of debris formation, Nucl. Eng. Des, vol.239, pp.1653-1659, 2009.

G. .. Repetto, T. Garcin, S. Eymery, and F. Fichot, Experimental program on debris reflooding (PEARL) -Results on PRELUDE facility, Nucl. Eng. Des, vol.264, pp.176-186, 2013.

N. Chikhi, T. Garcin, F. Foubert, P. March, and F. Fichot, First experimental results of large-scale debris bed reflood tests in the PEARL facility, Proc. NURETH-16, 2015.

J. Starflinger, Recent numerical simulations and experiments on coolability of debris beds during severe accidents of light water reactors, Nucl. Eng. Des, vol.294, pp.153-160, 2015.

E. Takasuo, S. Holmström, T. Kinnunen, and P. H. Pankakoski, The COOLOCE experiments investigating the dryout power in debris beds of heap-like and cylindrical geometries, Nucl. Eng. Des, vol.250, pp.687-700, 2012.

X. Gaus-liu, A. Miassoedov, T. Cron, and T. Wenz, In-vessel melt pool coolability test -Description and results of LIVE experiments, Nuclear Engineering and Design, vol.240, pp.3898-3903, 2010.

V. S. Granovsky, Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retention, Nucl. Eng. Des, vol.278, pp.310-316, 2014.

V. Bouyer, N. Cassiaut-louis, P. Fouquart, and P. Piluso, PLINIUS Prototypic Corium Platform : Major Results and Future Works, Proc. NURETH, 2015.
URL : https://hal.archives-ouvertes.fr/cea-02509269

D. Guénadou and E. Verloo, Presentation of the RESCUE facilities for in Vessel Corium Retention studies: Toolbox for improving the modelling, Proc. Nuclear Energy New, 2012.

G. Zs-l, Modelling of External Cooling for In-Vessel Corium Retention in VVER-440/213 Type Nuclear Power Plants, Proc. 18th International Conference on Nuclear Engineering, 2010.

X. Chen, S. Zhang, J. Lin, and H. Zhang, The Analytical and Experimental Research of In-Vessel Corium Retention in CPR1000, 18th International Conference on Nuclear Engineering, 2010.

X. Cheng, Y. H. Yang, Y. Ouyang, and H. X. Miao, Role of Passive Safety Systems in Chinese Nuclear Power Development, Sci. Technol. Nucl. Install, p.573026, 2009.

C. Journeau, PLINIUS-2: A New Versatile Platform for Severe Accident Assessments, Proc. NUTHOS-10, 2014.

L. Meyer, Melt Dispersion and Direct Containment Heating (DCH) Experiments for Konvoi Reactors, Karlsruhe Institut für Technologie (KIT), vol.7567, 2011.

T. Sevón, HECLA experiments on interaction between metallic melt and hematite-containing concrete, Nucl. Eng. Des, vol.240, pp.3586-3593, 2010.

M. T. Farmer, A Summary of Findings from the Melt Coolability and Concrete Interaction (MCCI) Program, Proceedings ICAPP '07, 2007.

J. J. Foit, Experiments on MCCI with oxide and steel, Annals of Nuclear Energy, vol.74, pp.100-109, 2014.

M. Amizic, E. Guyez, and J. M. Seiler, Experimental Investigation on heat transfer for two-phase flow under natural convection. First CLARA test results, Proceedings of ICONE20, 2012.

Y. B. Petrov, Phase Equilibria during crystallization of melts of the Uranium Oxide-Iron Oxide System in Air, Glass Phys. Chem, vol.35, pp.298-307, 2009.

D. Manara, Melting of stoichiometric and hyperstoichiometric uranium dioxide, J. Nucl. Mater, vol.342, pp.148-163, 2005.