Application of CFD Codes for the Nuclear Reactor Flow Research

Research of the flow inside the reactor pressure vessel based on the outputs from the experimental measurements and key thermohydraulic effect analysis by CFD codes. The research enabled to develop strategies, procedures and methods for safe and effective reactor cooldown under accident conditions. The main aim of the project was to enhance the operating safety of the unit, reduction of the radiation risk during the potential accident, development and upgrading of the system thermohydraulic codes for NPP.