Development of the SCK CEN reference datasets for spent fuel safeguards research and development
A set of reference spent fuel libraries has been organized in datasets containing the material composition and radiation emission (i.e. neutrons and gamma-rays) of spent fuel. The data was obtained with computer simulations using the ORIGEN-ARP code, which is part of the SCALE 6.1 package.Both fuel...
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| Format: | Article |
| Language: | English |
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Elsevier
2020-06-01
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| Series: | Data in Brief |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S2352340920303565 |
| _version_ | 1828774734956855296 |
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| author | Riccardo Rossa Alessandro Borella |
| author_facet | Riccardo Rossa Alessandro Borella |
| author_sort | Riccardo Rossa |
| collection | DOAJ |
| description | A set of reference spent fuel libraries has been organized in datasets containing the material composition and radiation emission (i.e. neutrons and gamma-rays) of spent fuel. The data was obtained with computer simulations using the ORIGEN-ARP code, which is part of the SCALE 6.1 package.Both fuel assembly geometries for Pressurized Water Reactors (PWR 17 × 17) and Boiling Water Reactors (BWR 8 × 8) are included in the datasets, and for each geometry both uranium oxide (UO2) and mixed oxide (MOX) fuel materials are considered. The datasets contain the information for spent fuel with a broad range of initial enrichment (UO2 fuel) or initial Pu content (MOX fuel), discharge burnup, and cooling time.For each simulation the neutron spectra, divided into contributions from (α,n) reactions, spontaneous fission, and total neutron emission, as well as total gamma-ray spectra are included. The neutron emission from selected isotopes is also reported, divided in contributions from (α,n) reactions and spontaneous fissions.The datasets are publicly available and are in a format that facilitates the further data extraction and processing for applications in the safeguards research & development related to spent fuel measurement and verification. |
| first_indexed | 2024-12-11T15:26:28Z |
| format | Article |
| id | doaj.art-154da7c4682342e99cfd8beace8d59ec |
| institution | Directory Open Access Journal |
| issn | 2352-3409 |
| language | English |
| last_indexed | 2024-12-11T15:26:28Z |
| publishDate | 2020-06-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Data in Brief |
| spelling | doaj.art-154da7c4682342e99cfd8beace8d59ec2022-12-22T01:00:11ZengElsevierData in Brief2352-34092020-06-0130105462Development of the SCK CEN reference datasets for spent fuel safeguards research and developmentRiccardo Rossa0Alessandro Borella1Corresponding author.; Environment, Health and Safety Institute, SCK CEN Belgian Nuclear Research Centre, 2400 Mol, BelgiumEnvironment, Health and Safety Institute, SCK CEN Belgian Nuclear Research Centre, 2400 Mol, BelgiumA set of reference spent fuel libraries has been organized in datasets containing the material composition and radiation emission (i.e. neutrons and gamma-rays) of spent fuel. The data was obtained with computer simulations using the ORIGEN-ARP code, which is part of the SCALE 6.1 package.Both fuel assembly geometries for Pressurized Water Reactors (PWR 17 × 17) and Boiling Water Reactors (BWR 8 × 8) are included in the datasets, and for each geometry both uranium oxide (UO2) and mixed oxide (MOX) fuel materials are considered. The datasets contain the information for spent fuel with a broad range of initial enrichment (UO2 fuel) or initial Pu content (MOX fuel), discharge burnup, and cooling time.For each simulation the neutron spectra, divided into contributions from (α,n) reactions, spontaneous fission, and total neutron emission, as well as total gamma-ray spectra are included. The neutron emission from selected isotopes is also reported, divided in contributions from (α,n) reactions and spontaneous fissions.The datasets are publicly available and are in a format that facilitates the further data extraction and processing for applications in the safeguards research & development related to spent fuel measurement and verification.http://www.sciencedirect.com/science/article/pii/S2352340920303565Spent fuelNuclear safeguardsORIGEN-ARPNeutron emissionGamma-ray emission |
| spellingShingle | Riccardo Rossa Alessandro Borella Development of the SCK CEN reference datasets for spent fuel safeguards research and development Data in Brief Spent fuel Nuclear safeguards ORIGEN-ARP Neutron emission Gamma-ray emission |
| title | Development of the SCK CEN reference datasets for spent fuel safeguards research and development |
| title_full | Development of the SCK CEN reference datasets for spent fuel safeguards research and development |
| title_fullStr | Development of the SCK CEN reference datasets for spent fuel safeguards research and development |
| title_full_unstemmed | Development of the SCK CEN reference datasets for spent fuel safeguards research and development |
| title_short | Development of the SCK CEN reference datasets for spent fuel safeguards research and development |
| title_sort | development of the sck cen reference datasets for spent fuel safeguards research and development |
| topic | Spent fuel Nuclear safeguards ORIGEN-ARP Neutron emission Gamma-ray emission |
| url | http://www.sciencedirect.com/science/article/pii/S2352340920303565 |
| work_keys_str_mv | AT riccardorossa developmentofthesckcenreferencedatasetsforspentfuelsafeguardsresearchanddevelopment AT alessandroborella developmentofthesckcenreferencedatasetsforspentfuelsafeguardsresearchanddevelopment |