Technical Area 2 -Severe Accidents, 2013. ,
Identification of Research Areas in response to the Fukushima Accident, SNE-TP Report, 2013. ,
, Global Vision report, Nuclear Gen II and III Association, 2015.
Severe Accident Facilities for European Safety Targets. The SAFEST Project, Proc. ERMSAR, 2015. ,
Conclusions on severe accident research priorities, Ann. Nucl. Ener, vol.74, pp.4-11, 2014. ,
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. ,
Synopsis and outcome of the QUENCH experimental programme, Nucl. Eng. Des, vol.240, pp.1714-1727, 2010. ,
Quenching of high temperature VVER fuel after long term oxidation in hydrogen rich steam, Nucl. Eng. Des, vol.37, pp.71-82, 2010. ,
A scoping study of debris formation, Nucl. Eng. Des, vol.239, pp.1653-1659, 2009. ,
Experimental program on debris reflooding (PEARL) -Results on PRELUDE facility, Nucl. Eng. Des, vol.264, pp.176-186, 2013. ,
First experimental results of large-scale debris bed reflood tests in the PEARL facility, Proc. NURETH-16, 2015. ,
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. ,
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. ,
In-vessel melt pool coolability test -Description and results of LIVE experiments, Nuclear Engineering and Design, vol.240, pp.3898-3903, 2010. ,
Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retention, Nucl. Eng. Des, vol.278, pp.310-316, 2014. ,
PLINIUS Prototypic Corium Platform : Major Results and Future Works, Proc. NURETH, 2015. ,
URL : https://hal.archives-ouvertes.fr/cea-02509269
Presentation of the RESCUE facilities for in Vessel Corium Retention studies: Toolbox for improving the modelling, Proc. Nuclear Energy New, 2012. ,
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. ,
The Analytical and Experimental Research of In-Vessel Corium Retention in CPR1000, 18th International Conference on Nuclear Engineering, 2010. ,
Role of Passive Safety Systems in Chinese Nuclear Power Development, Sci. Technol. Nucl. Install, p.573026, 2009. ,
PLINIUS-2: A New Versatile Platform for Severe Accident Assessments, Proc. NUTHOS-10, 2014. ,
Melt Dispersion and Direct Containment Heating (DCH) Experiments for Konvoi Reactors, Karlsruhe Institut für Technologie (KIT), vol.7567, 2011. ,
HECLA experiments on interaction between metallic melt and hematite-containing concrete, Nucl. Eng. Des, vol.240, pp.3586-3593, 2010. ,
A Summary of Findings from the Melt Coolability and Concrete Interaction (MCCI) Program, Proceedings ICAPP '07, 2007. ,
Experiments on MCCI with oxide and steel, Annals of Nuclear Energy, vol.74, pp.100-109, 2014. ,
Experimental Investigation on heat transfer for two-phase flow under natural convection. First CLARA test results, Proceedings of ICONE20, 2012. ,
Phase Equilibria during crystallization of melts of the Uranium Oxide-Iron Oxide System in Air, Glass Phys. Chem, vol.35, pp.298-307, 2009. ,
Melting of stoichiometric and hyperstoichiometric uranium dioxide, J. Nucl. Mater, vol.342, pp.148-163, 2005. ,