This work investigated the neutronics behavior and the economics of the HYLIFE-II reactor with ThF4 and UF4, which produces an electrical power of 1 GW from the fusion power of 2.857 GW during the operation period of 30 years. The use of ThF4 and UF4 is realized by a mixture zone consisted of 90% flibe (Li2BeF4) and 10% fuel, instead of 100% flibe coolant. The mixture compositions are selected as 90% flibe + 10% UF4, 90% flibe + 10% ThF4 and 90% flibe + 5% UF4 + 5% ThF4. The capacity factor of the reactor is 0.75. The mixtures, with zone thickness of 65 cm were circulated with periods of 20.22, 19.89 and 20.11 s during the operation period of 30 years, respectively. In addition, for flibe + UF4, power stabilization by means of plutonium separation from the mixture was applied.The use of fuel materials in the HYLIFE-II reactor resulted in high energy production, sufficient tritium breeding, significant fissile fuel breeding and low radiation damage in the first wall. The average values of tritium breeding ratio over 30 years are between 1.08 and 1.12, higher than 1.0 indicating sufficient tritium breeding. Generally, the mixtures with ThF4 show better performance than the mixture with UF4 in terms of more energy production and significant fissile fuel breeding. The neutronic performance of the reactor increases with the operational period. However, the stabilization process performed after operation for 6 years causes all neutronic values to remain nearly constant during the followed operation time. At the 6th year of operation, the power production, which is ≈1540 MW(electric) at startup, reached the electrical power of 2 GW for flibe + UF4. The power production without the separation process reached ≈3500 MW(electric) for the mixtures with ThF4 and ≈3000 MW(electric) for the mixture with UF4. At the end of the operation period, helium production values in the first wall, made of Hastelloy, are calculated as 590 ppm without the stabilization process and 550 ppm with the stabilization process. If the same electrical power of 2 GW(electric) were produced by 100% fusion power, the helium production would be 1190 ppm. This shows a decrease of ≈100% in helium production for the same zone thickness and electrical power production. In addition to this improvement, the COE value of the hybrid HYLIFE-II with the stabilization process also improves between 5% and 11.5%. Thereby, the COE values of the HYLIFE-II of 1934 MW(electric) and the improved HYLIFE-II of 2000 MW(electric) would drop from 4.5 and 4.18 to 3.98 ¢/kW h, respectively. The separated fissile fuel capability of the reactor with the stabilization process is ≈4000 kg/year with the fuel enrichment grade of ≈85% after the initial operation period of 6 years. This production rate of the fissile fuel amount would be sufficient to provide for about 15 light water reactors. In addition, after shutdown of the hybrid HYLIFE reactor, the fissile fuel of 46 tonnes with the fuel enrichment grade of ≈4.88% would be left over.