Akademik Veri Yönetim Sistemi
Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji, cilt.13, sa.4, ss.1418-1430, 2025 (TRDizin)
Neutronic analyses were performed in a hybrid reactor using 50% TRISO-coated CANDU spent nuclear fuel and 50% Th mixture as fuel and natural Li as coolant. The XSDRNPM/SCALE nuclear code program was used for neutronic analyses. Under these conditions, the hybrid reactor operated for 48 months. TBR and M values were calculated from neutronic analyses. At the beginning of the 48-month operation period, the TBR value was approximately 1.176, while at the end of the operation period, this value was approximately 1.196. The M value was calculated as approximately 1.653 and 1.869 at the beginning and end, respectively. Additionally, the rate of hydrogen production in the hydrogen production facility integrated into the reactor was examined. The vanadium-chloride (V-Cl) thermochemical cycle was preferred as a method for hydrogen production. The approximate hydrogen production rate at the beginning and end of the 48-month operation period of the plant was calculated as 1,659 kg/s and 2,287 kg/s. As a result, it seems that the hybrid reactor and vanadium chloride (V-Cl) thermochemical cycle are preferable for hydrogen production.