Dataset of observables for UOX and MOX spent fuel extracted from Serpent2 fuel depletion calculations for Pressurized Water Reactors

These nuclides are crucial for characterizing nuclear waste and analyzing fuel cycles. The values in the database were obtained through depletion calculations based on a representative 3D cuboid model of a fuel pin-cell, using the Monte Carlo reactor physics burn-up calculation code Serpent2 version 2.2.0, along with state-of-the-art nuclear data libraries and methods.

The calculations cover a wide range of burn-up levels for conventional PWRs (0 to 70 MWd/KgHM), and take into account both UOX and MOX fuel. The range of initial enrichment for UOX and initial plutonium content is also considered, i.e., 1.5% to 6.0% enrichment for UOX and 4% to 12% of initial plutonium + americium content (over the heavy metal). Additionally, different Pu isotopic composition vectors are considered within the range of reactor-grade (RG) plutonium.