Investigation of the temperature distribution in fuel rod in a fusion-fission reactor

摘要

In this study, the neutronic and thermal effects of UO_2 fuel in the fuel rod used hybrid reactor have been investigated for various neutron wall loads by full reactor power. The reactor operation time for the different first neutron wall loads is selected as 24 months. Li_(20)Sn_(80) coolant in the fuel zone is used to breed tritium and supply heat transfer out of the blanket. The fission rate for row#1 fuel rods is determined by XSDRNPM/SCALE 5 codes. The effects of different neutron wall loads hybrid reactor on temperature distribution in the fuel rod are comparatively examined as analytically and numerical method. The calculations of temperature distribution are performed for row#1 fuel rods because the maximum heat production occurs in the fuel rows adjacent to the first wall. The maximum temperature in the centerline of the fuel rods has reached the melting point for 8 MW/ m~2 after 24 months. As a result, the calculation results analytical and numerical temperatures distributions in the fuel rod have indicated in a good agreement.