Performance of UO2-Graphene Composite Fuel and SiC Cladding during LOCA

The commercial nuclear power industry is interested in advanced fuels and claddings that can produce higher power levels with a higher safety margin and be manufactured at low cost. Although UO2 fuel is chemically stable, its thermal conductivity is low. If the graphene is mixed in UO2 fuel, it is chemically stable and its thermal conductivity will be enhanced. Advantages of the graphene are high thermal conductivity (5,200 W/mK) and low absorption cross section. Zircaloy-4 and Zirlo are cladding materials used in PWR. They have high resistance to the high temperature and high radiation environment, but, zirconium reacts easily water above 1,100 .deg. C and generates hydrogen. The resistance of SiC to the high-temperature and high-radiation environment can be a good reason for applying SiC as a cladding material for light water nuclear reactor. Analysis tests about the radial fuel rod temperature and the peak cladding temperature using MARS-KS (Multi-dimensional Analysis of Reactor Safety-Korean Standard) were simulated in 12 cases