Fuel Performance Modeling for Proposed Th Based Canadian SCWR Fuel

Abstract

The fuel for the Canadian Super Critical Water Reactor (SCWR) is in the design concept phase. The proposed fuel is ceramic pellets made of Th-Pu mixed oxide. Neutronics and thermal hydraulics calculations are being undertaken by the nuclear industry to optimize the fuel assembly within a pressure tube. The SCWR working group has provided conceptual fuel element designs (outer diameter, fuel composition, cladding material, exit burnup etc.) for two distinct fuel geometries within the assembly. A detailed analysis of the fuel element during in reactor conditions can be used to determine cladding material thickness/suitability and optimize the fuel pellet geometry. This work will report on the development of a fuel performance model for the Canadian SCWR fuel using finite element method. This model examines the temperature and deformation of a single fuel pellet and the clad surrounding it. Modeling parameters and the performance of a UO₂ fuel pellet and a Th-Pu oxide pellet will be compared and presented.