Abstract
A model for fuel performance of annular uranium-plutonium mixed oxide (MOX) fuels in lead-cooled fast reactors is developed. This model has several modules working in fully coupled approach based on COMSOL Multiphysics. These modules describe (1) Fission gas release, (2) Plutonium redistribution, (3) Oxygen redistribution, (4)Heat transfer, (5) Gap width evolution. The modeling results were benchmarked with existing codes and experiment data, the results were in satisfactory agreement. The parameters analysis was carried out in this work. Consistent with the solid MOX fuel, the O/M ratio (or deviation from stoichiometry of oxygen) has a great effect on temperature evolution, fission gas migration and release behavior and plutonium redistribution. The effect of linear power on fuel performance are also analyzed.
