Assessment of Neutronic Parameters of the Angra 2 NPP Core With Different Fuels Using Serpent 2.1.32 Nuclear Code and Endf/B and Jeff 3.1 Libraries

Abstract

The core of the Angra 2 reactor has been modeled with SERPENT2.1.32 nuclear code using the ENDF/B-VII.1 and JEFF 3.1 cross-section libraries. The objective is to analyze and compare the neutron multiplication factor and check the mass variation of fissile actinides during the burnup, obtained with several libraries for standard UO2 enriched with U-235, mixed oxide fuels (MOX), and reprocessed fuel spiked with thorium (TRU) in a PWR. The parameters were calculated at BOL (Beginning of Life) and during the burnup fuel cycle. The neutron multiplication factor evaluated at BOL and its evolution during the burnup cycle has a consistent result between cross-section libraries used. The difference between the neutronic parameters is expected to increase at the EOC (End of Cycle), mainly due to the distinct nuclear libraries used. The mass variation of fissile actinides also shows good consistency between cross-section libraries.