, 4TH-Generation Sodium-Cooled Fast Reactors -The Astrid Technological Demonstrator, 2012.
Plateau Facility in Support to Astrid and the SFR Program: An Overview of the First Mock-Up of the Astrid Upper Plenum, MICAS, Proceedings of the16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH16), 2015. ,
Study of the Free Surface Flow in the MICAS Mock-Up in Support of the ASTRID SFR Program, Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11), 2016. ,
Flow Analysis in the Upper Plenum of the MICAS Model in Support of the ASTRID Reactor Program, Proceedings of the17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH17), 2017. ,
The Safety orientations during ASTRID conceptual design phase, Proceeding of FR13, Paper CN-199-267, IAEA CN-199, 2013. ,
Advanced Coupling methodology for Thermal-hydraulic calculations, Proceeding of the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), pp.26-29, 2017. ,
Experimental and Numerical Validation of Flow Pattern in Compact Heat Exchanger, Proceedings of the17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH17), 2017. ,
URL : https://hal.archives-ouvertes.fr/hal-02417762