1. Phenomenological investigation of sodium boiling in a SFR core during a postulated ULOF transient with CATHARE2 system code: a stabilized boiling case;Alpy;J. Nucl. Sci. Technol.,2016
2. Qualification of scientific computing tools used in the nuclear safety case, 1st barrier, guide 28;ASN,2017
3. Bajard, S., Degezelle, T., Li, S., Conti, A., 2022. Influence of the fuel pellet-clad gap heat exchange coefficient on a loss of flow without scram transient simulated with CATHARE3 in a Sodium Fast Reactor. In: NURETH-19. Brussels, Belgium.
4. A Multiphysics Coupling Scheme between OpenMC and OpenFOAM for High-Fidelity, Flexible Multi-Physics Analysis of Nuclear Reactors;Bullerwell,2020
5. Bullerwell, L., Shriwise, P., Romano, P., Rahaman, R., Hou, J., 2021. Development of an OpenFOAM Interface For ENRICO. In: International Conference on Mathematics and Computation Applied To Nuclear Science and Engineering.