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

Published: 26 June 2023| Version 5 | DOI: 10.17632/shv89y2zzd.5


This database contains information on the isotopic mass density and its contribution to activity, decay heat, photon emission, spontaneous fission rate, (alpha,n) reaction rate and radiotoxicity of 150 nuclides present in nuclear fuel that has been irradiated in PWRs. 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.  To make this resource widely available, the database has been made publicly accessible. It is particularly useful for waste and fuel characterization, nuclear safeguards, and radiation protection applications. By providing access to the data contained in this database, other potential users can save time and avoid the complexities associated with performing similar calculations. Moreover, this database serves as a valuable dataset for model training in machine learning applications related to nuclear science and engineering.



Studiecentrum voor Kernenergie


Nuclear Engineering, Nuclear Waste Disposal, Nuclear Fuel Cycle, Fission Reactor Fuel, Nuclear Safeguard