His technical field is the nuclear reactor thermal-hydraulics in reactor coolant system/containment and their coupling and the analyses of severe accident phenomena. In relation with that, he is expert on the use of best estimate thermal hydraulic system code (RELAP5 and TRACE) and severe accident code (ASTEC and MELCOR). Currently he is investigating the severe accident phenomenology in PWR and BWR reactor type and the aerosol behavior in the containment of Sodium-Cooled Fast Neutron Reactor by using severe accident codes. He has experience in the assessment of thermal hydraulic system codes, in particular RELAP5 and TRACE, and the assessment of severe accident code, in particular MELCOR and ASTEC-CPA. He is expert on the analyses of the scaling issues.