Development of a MOX equivalence Python code package for ANICCA

The basis of the MOX (Mixed OXide) energy equivalence principle is keeping in-core fuel management characteristics (cycle length, feed size, etc.) a nuclear reactor unchanged when replacing UOX (Uranium assemblies by MOX. If effect loading pattern neglected, such an obtained tuning Pu content in fuel, while considering specific isotopic vector at time core reload to obtain crossing reactivity curves and end-of-cycle average burnup. It proposed this work extend cycle analysis tool ANICCA (Advanced Nuclear Inventory Cycle Code) with Python code package, which automatically governs supply demand isotopes required equivalence. This package can determine evolution for any given means multidimensional interpolation on directive grid pre-calculated data tables generated WIMS10, covering physically accessible space. A scenario will be assessed representative inventory available spent as demonstration case, defining interim storage building dimensional requirements different reprocessing strategies.