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

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. We supplement the measurements 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. Our paper describes the new database, and applications of SFCOMPO-2.0 for computer code validation, integralmore » nuclear data benchmarking, and uncertainty analysis in nuclear waste package analysis are briefly illustrated.« less
Authors:
 [1] ;  [2] ;  [2] ;  [3] ;  [1] ;  [4] ;  [1] ;  [5] ;  [6] ;  [7] ;  [8] ;  [9] ;  [9] ;  [10] ;  [8] ;  [11] ;  [12] ; ORCiD logo [2] ;  [10] ;  [13] more »;  [14] ;  [15] ;  [2] ;  [16] ;  [17] ;  [18] ;  [19] ;  [1] ;  [10] ;  [20] ;  [21] ;  [15] ;  [22] ;  [23] ;  [24] ;  [25] ;  [25] « less
  1. Organisation for Economic Co-operation and Development (OECD), Boulogne-Billancourt (France)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Nuclear Safety Council, Madrid (Spain)
  4. National Organization for Radioactive Waste and Enriched Fissile Fuel (NIRAS/ONDRAF), Bussels (Belgium)
  5. Vuje, Inc., Trnava (Slovak Republic)
  6. ENUSA Industries, Madrid (Spain)
  7. Julich Research Centre (Germany)
  8. Nuclear Research Inst., Rez (Czech Republic)
  9. Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium)
  10. Society for Plant and Reactor Safety (GRS), Munich (Germany)
  11. AREVA GmbH, Erlangen (Germany)
  12. Centre for Energy Research Hungarian Academy of Sciences, Budapest (Hungary)
  13. UK National Nuclear Lab., Cumbria (United Kingdom)
  14. UK National Nuclear Lab., Sellafield (United Kingdom)
  15. Engineering and Analysis of Shields (SEA), Madrid (Spain)
  16. US Nuclear Regulatory Commission (NRC), Rockville, MD (United States)
  17. Industrial Power Corporation (TVO), Helsinki (Finland)
  18. Radiation and Nuclear Safety Authority (STUK), Helsinki (Finland)
  19. Federal Office for Radiation Protection (BFS), Salzgitter (Germany)
  20. Japan Atomic Energy Agency (JAEA), Ibaraki (Japan)
  21. Scientific Engineering Consultants GmbH (WTI), Julich (Germany)
  22. Joint Research Centre Karlsruhe, Eggenstein-Leopoldshafen (Germany)
  23. Paul Scherrer Inst. (PSI), Villigen (Switzerland)
  24. Japan Atomic Energy Agency (JAEA), Tokai (Japan)
  25. Nuclear Regulation Authority, Tokyo (Japan)
Publication Date:
Grant/Contract Number:
AC05-00OR22725
Type:
Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 110; Journal Issue: C; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Research Org:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 97 MATHEMATICS AND COMPUTING; SFCOMPO; Spent nuclear fuel database; Radiochemical assay data; Experimental isotopic compositions; Nuclear fuel depletion; Nuclear fuel evolution; Code validation; Integral benchmarks
OSTI Identifier:
1376611