Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide
We used MCNP6 computer code to model HTR-10 core reactor.We used two types of fuel; UO2 and (Th+Pu)O2 mixture.We Flea determined the critical height at which the reactor approached criticality in both two cases.The neutronic and burnup parameters were investigated.The results indicated that the core fueled with mixed (Th+Pu)O2, achieved about 24% h