Analysis of thorium and transuranium utilization in a small modular reactor

This study presents neutronic analyses of a small modular reactor utilizing transuranium and thorium. Two different fuel cases are considered in the as extracted from PWR-MOX spent (a form mixture minor actinide Pu isotopes) (Case A) 4.5 % enriched UO2 with ThO 2(the separate rods) B). The total power containing 69 assemblies is 450 MW thermal. In both cases, time-dependent critical burnup calculations carried out by using MCNPX 2.7 code until their effective neutron multiplication factors decrease to 0.99. bring that can operate for quite long time without refueling new richness 1.05 be obtained well 2 energy production.