Published December 2017 | Version v1
Journal article

SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data

  • 1. OECD Nuclear Energy Agency, Boulogne-Billancourt (France)
  • 2. Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States)
  • 3. Consejo de Seguridad Nuclear, 28040 Madrid (Spain)
  • 4. NIRAS/ONDRAF, 1210 Bussels (Belgium)
  • 5. VUJE, 918 64 Trnava (Slovakia)
  • 6. ENUSA Industrias Avanzadas, S.A., 28040 Madrid (Spain)
  • 7. Forschungszentrum Juelich GmbH, 52425 Juelich (Germany)
  • 8. Nuclear Research Institute at Rez, Rez (Czech Republic)
  • 9. SCK-CEN Belgian Nuclear Research Centre, 2400 Mol (Belgium)
  • 10. Gesellschaft für Anlagen und Reaktorsicherheit (GRS), 85748 Garching bei München (Germany)
  • 11. AREVA GmbH, 91058 Erlangen (Germany)
  • 12. Centre for Energy Research Hungarian Academy of Sciences, Budapest (Hungary)
  • 13. UK National Nuclear Laboratory, Seascale, Cumbria CA20 1PG (United Kingdom)

Description

Highlights: •SFCOMPO-2.0 is a new NEA database of SNF assay measurements with isotopic concentrations, reactor design and operational parameters information. •SFCOMPO-2.0 contains data for 750 SNF samples coming from 44 reactors of 8 different types, representing over 24000 measurement points. •SFCOMPO-2.0 is publicly available from the NEA. -- Abstract: SFCOMPO-2.0 is the new release of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) database of experimental assay measurements. These measurements are isotopic concentrations from destructive radiochemical analyses of spent nuclear fuel (SNF) samples. The measurements are supplemented with design information for the fuel assembly and fuel rod from which each sample was taken, as well as with relevant information on operating conditions and characteristics of the host reactors. These data are necessary for modeling and simulation of the isotopic evolution of the fuel during irradiation. SFCOMPO-2.0 has been developed and is maintained by the OECD NEA under the guidance of the Expert Group on Assay Data of Spent Nuclear Fuel (EGADSNF), which is part of the NEA Working Party on Nuclear Criticality Safety (WPNCS). Significant efforts aimed at establishing a thorough, reliable, publicly available resource for code validation and safety applications have led to the capture and standardization of experimental data from 750 SNF samples from more than 40 reactors. These efforts have resulted in the creation of the SFCOMPO-2.0 database, which is publicly available from the NEA Data Bank. This paper describes the new database, and applications of SFCOMPO-2.0 for computer code validation, integral nuclear data benchmarking, and uncertainty analysis in nuclear waste package analysis are briefly illustrated.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2017.07.022

Additional details

Identifiers

DOI
10.1016/j.anucene.2017.07.022;
PII
S0306-4549(17)30210-4;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
110
Journal Issue
Complete
Journal Page Range
p. 779-788
ISSN
0306-4549
CODEN
ANENDJ

INIS

Optional Information

Copyright
Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.