Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN)
Author in the following contributions
- Modeling and Simulation of Source Term for Sodium-Cooled Fast Reactor under Hypothetical Severe Accident: Sodium Fire and Radionuclide Transport in Containment
- Progress in system thermohydraulic code HYDRA-IBRAE/LM models development for fast reactor simulation
- Codes of new generation – sustainable platform for numerical modeling of installations in the Proryv project
- Aerosol module for modeling of the fission product behavior in FR cooling circuits and NPP compartments
