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Dataset of observables for UOX and MOX spent fuel extracted from Serpent2 fuel depletion calculations for PWRs

dc.contributor.authorCasas Molina, Víctor J.
dc.contributor.authorHernandez-Solis, Augusto
dc.contributor.authorRomojaro Otero, Pablo
dc.contributor.authorMerino-Rodríguez, Ivan
dc.contributor.authorAguilera-Gómez, Nerea
dc.date.accessioned2025-03-12T13:12:44Z
dc.date.available2025-03-12T13:12:44Z
dc.date.issued2023
dc.identifier.urihttp://repositorio.ucm.cl/handle/ucm/5832
dc.description.abstractThis database contains the isotopic mass density and the contribution to activity, decay heat, photon emission, spontaneous fission rate, (α,n) emission rates and radiotoxicity of 150 nuclides that are present in nuclear fuel irradiated in PWRs. These nuclides are of paramount importance for nuclear waste characterization and fuel cycle analysis. These values were obtained by depletion calculations based on a 3D pin-cell geometry model and performed with the Monte Carlo reactor physics burnup calculation code Serpent2, with state-of-the-art nuclear data libraries and relevant methods. The calculations cover a wide range of burnup levels for conventional PWRs and take into account both UOX and MOX fuel. A broad span for initial enrichment for UOX (from 1.5% to 6.0%), and for both the initial plutonium content (from 4.0% to 12.0% and the plutonium isotopic composition of MOX has been considered. This database has been made publicly available due to its relevance in the fields of waste and fuel characterization, nuclear safeguards and radiation protection, and it will allow other potential users to avoid the time-consuming calculations required to obtain the aforementioned data. Additionally, it constitutes an interesting dataset for model training in machine learning applications related to nuclear science and engineering.es_CL
dc.language.isoenes_CL
dc.rightsAtribución-NoComercial-SinDerivadas 3.0 Chile*
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/3.0/cl/*
dc.sourceData in Brief, 49, 109412es_CL
dc.subjectSpent nuclear fueles_CL
dc.subjectUOXes_CL
dc.subjectMOXes_CL
dc.subjectNuclide inventoryes_CL
dc.subjectDecay heates_CL
dc.subjectNeutron and gamma emissiones_CL
dc.subjectNuclear safeguardses_CL
dc.subjectRadiotoxicityes_CL
dc.subjectSerpent2es_CL
dc.subjectFuel depletion calculationses_CL
dc.titleDataset of observables for UOX and MOX spent fuel extracted from Serpent2 fuel depletion calculations for PWRses_CL
dc.typeArticlees_CL
dc.ucm.indexacionScopuses_CL
dc.ucm.urisciencedirect.ucm.elogim.com/science/article/pii/S2352340923005140?via%3Dihubes_CL
dc.ucm.doidoi.org/10.1016/j.dib.2023.109412es_CL


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Atribución-NoComercial-SinDerivadas 3.0 Chile
Excepto si se señala otra cosa, la licencia de la publicación se describe como Atribución-NoComercial-SinDerivadas 3.0 Chile