Safety analyses of reactor VVER 1000

Department of Electrical Power Engineering, Faculty of Electrical Engineering and Communication, Brno University of Technology (BUT) is participating in research of safety analyses of nuclear power plants, especially nuclear power plants with VVER 1000 reactors. Main task of this research is lattice calculation, homogenized cross section processing for further 3D nodal reactor core simulation and coupled reactor core simulations and thermal-hydraulic calculations. Verification of deterministic methods and obtained results is provided by Monte Carlo simulation. Taking in account several years of experience with calculation tools provided by United States Nuclear Regulatory Commission (U.S. NRC), the complex simulation is performed by simulations tools such as nuclear package SCALE, reactor core simulator PARCS and thermal-hydraulics code TRACE.