Data of uncontrolled withdrawal of control rods group accident analysis for VVER-1000 unit

This dataset presents the analysis results of an uncontrolled withdrawal of control rods group under minimum controlled power condition in the Final Safety Analysis Report (FSAR) of a VVER-1000 reactor unit. Three-dimensional neutronics/thermal-hydraulics coupled code was employed in the study. The dataset includes the time-dependent variations of the following result parameters: neutron power, axial relative power distribution in the core hot channel assembly (#31), coolant flow rate in loops, PRZ pressure, PRZ spray flow rate, coolant temperature in hot legs of different loops, steam generator outlet pressure, maximum fuel temperature in axial layers of hot channels, DNBR in axial layers of hot channels, and maximum cladding temperature in axial layers of hot channels. This dataset can be used for related research in the field of accident safety analysis for VVER units.