Effect of cross-sections data on calculated static neutronic parameters of PWR MOX/UO2 core transient benchmark case using NODAL3 code

This paper describes the effect of cross-section data generated by several codes on calculated neutronic parameters. The Pressurized Water Reactor Mixed Oxide and Uranium (PWR MOX/UO2) Core Transient Benchmark case was chosen because it has been used widely to validate codes. in this study will be SRAC, Serpent, HELIOS NODAL3 code calculate parameters from each cross-section. are effective multiplication factor (keff), control rod worth, critical boron concentration, power distribution under Hot Zero Power (HZP) conditions. Power-Weighted Error (PWE) Error-Weighted (EWE), as a measure relative error fuel assembly power, less than 5 %, indicating that calculation is consistent with DeCART reference. difference radial peaking for all three cross-sections reference reaches 6.284 % (G-3), 8.438 10.998 (C-7), respectively, HELIOS. axial at top bottom reactor core peaked 16.60 13.86 10.20 provided Further improvements needed applying various discontinuity factors improve its performance.