Depletion Calculations for PWR Assemblies including Burnable Absorbers with Lattice Code PARA

Most of the lattice physics codes, used for routine core design calculations, are based on the spatial flat-flux assumption representation to solve the neutron transport equation. Consequently for regions (like fuel or control rods) with strong flux gradient, a fine computational mesh becomes required for better accuracy of the predictions. In the case of a PWR assembly, ..