Study on Fissile Material Usage for 50 MWt High Temperature Gas Reactor using (Pu-U)O2 Fuel

Abstract One of the most potential nuclear power plants is High Temperature Gas-cooled Reactor (HTGR). It is a reactor system designed using TRISO (Tristructural-Isotropic) coated fuel and has very high outlet temperature to produce electricity and many co-generation application processes. The present study aims to analyze fissile material usage for 50 MWt prismatic-type HTGR using (Pu-U)O2 fuel. Calculations were performed using neutron diffusion method that applied in SRAC2006 code, and nuclear data based on JENDL 4.0. Selected neutronic parameters are analyzed to study the effect of the number of fissile enrichment and number of Coated Fuel Particle (CFP) to the reactor system. The results of the parametric survey show that for prismatic-type of 50 MWt HTGR, 10% of enrichment and 8950 of number CFP give the best performance in term of fissile material usage during reactor operation.