TY - JOUR
T1 - Dataset of observables for UOX and MOX spent fuel extracted from Serpent2 fuel depletion calculations for PWRs
AU - Casas Molina, Victor
AU - Hernandez Solis, Augusto
AU - Romojaro, Pablo
AU - Merino Rodriguez, Ivan
AU - Aguilera Gómez, Nerea
N1 - Score=10
Publisher Copyright:
© 2023 The Authors
PY - 2023/8
Y1 - 2023/8
N2 - This 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.
AB - This 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.
KW - Spent nuclear fuel
KW - UOX
KW - MOX
KW - Nuclide inventory
KW - Decay heat
KW - Neutron and gamma emission
KW - Nuclear safeguards
KW - Serpent2
KW - Radiotoxicity
KW - Fuel depletion calculations
UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/56833144
UR - http://www.scopus.com/inward/record.url?scp=85166657528&partnerID=8YFLogxK
U2 - 10.1016/j.dib.2023.109412
DO - 10.1016/j.dib.2023.109412
M3 - Article
SN - 2352-3409
VL - 49
JO - Data in Brief
JF - Data in Brief
M1 - 109412
ER -