Engineering Commons^™

Theoretical Approach For Error Estimation Of Temperature And Thermal Conductivity In Uranium Dioxide Fuel, Adam John Gerth

All Graduate Plan B and other Reports, Spring 1920 to Spring 2023

The knowledge of in-reactor thermophysical properties of nuclear fuel rods, which are usually composed of uranium dioxide (UO2) ceramics, is important for the safe design and operation of nuclear power plants. A two thermocouple method can be utilized to determine the thermal conductivity within the fuel rods by measuring rod centerline temperature and cladding temperature. Using this technique, Halden Reactor Project (HRP) has developed a correlation for thermal conductivity of UO2 as a function of temperature and burnup. This correlation for thermal conductivity was extracted from experimental data based on a constant thermal conductivity assumption of the fuel rod. However, …