Simulation of BNPP steady state by PARCS and PMAXS library

Due to the advanced capabilities of the PARCS code in reactor simulation, using this code in Bushehr power plant analysis, at COLD and HZP states is the purpose of the present study. Multi-group cross sections are calculated by lattice code TRITON, CASMO and HELIOS. Since mentioned code are not available,In this paper, a novel method for generating the PMAXS format cross section of the PARCS code using WIMSD-5 lattice code is presented, and examined in a VVER-1000 core. Each fuel assembly of a VVER-1000 core is modeled by WIMSD-5; the group constants consistent with GenPMAXS are extracted and then the PMAXS file is produced. Our generated libraries are verified by modeling VVER-1000 Bushehr Nuclear Power Plant (BNPP) core during Hot Zero Power (HZP) as well as Cold Zero Power (CZP). Comparison of the PARCS results with the Final Safety Analysis Report (FSAR) of the BNPP and its Neutronics Album is presented herein.