Korkmaz, Mehmet EminYi?it, MustafaA?ar, Osman13.07.20192019-07-2913.07.20192019-07-2920130932-3902https://doi.org/10.3139/124.110358https://hdl.handle.net/20.500.12451/5987In this study, burnup calculations have been performed for a sodium cooled Accelerator Driven Thorium Reactor (ADTR) using the Serpent 1.1.16 Monte Carlo code. The ADTR has been designed for burning minor actinides, mixed Th-232 and mixed U-233 fuels. A solid Pb-Bi spallation target in the center of the core is used and sodium as coolant. The system is designed for a heating power of 2 000 MW and for an operation time of 600 days. For burnup calculations the Advanced Matrix Exponential Method CRAM (Chebyshev Rational Approximation Method) and different nuclear data libraries (ENDF7, JEF2.2, JEFF3.1.1) were used. The effective multiplication factor change from 0.93 to 0.97 for different nuclear data libraries during the reactor operation period.eninfo:eu-repo/semantics/closedAccessArticle78319319710.3139/124.110358Q3WOS:000323402800004N/A