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

Journal Article · · Annals of Nuclear Energy (Oxford)
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  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)
+ Show Author Affiliations

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, integral nuclear data benchmarking, and uncertainty analysis in nuclear waste package analysis are briefly illustrated.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1376611
Journal Information:
Annals of Nuclear Energy (Oxford), Vol. 110, Issue C; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 42 works
Citation information provided by
Web of Science

References (10)

SCALE 6: Comprehensive Nuclear Safety Analysis Code System journal May 2011
Determination of Bandwidths of PWR-UO 2 Spent Fuel Radionuclide Inventory Based on Real Operational History Data journal August 2016
Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE journal May 2011
IDAT: The International Handbook of Evaluated Reactor Physics Benchmark Experiments Database and Analysis Tool journal November 2014
Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE journal August 2012
A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN journal November 2015
Nuclide Composition Benchmark Data Set for Verifying Burnup Codes on Spent Light Water Reactor Fuels journal February 2002
Proposed re-evaluation of the 154Eu thermal n , γ capture cross-section based on spent fuel benchmarking studies journal January 2017
Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems journal May 2011
Development of Depletion Perturbation Theory for Coupled Neutron/Nuclide Fields journal April 1979

Cited By (2)

Flexible classification with spatial quantile comparison and novel statistical features applied to spent nuclear fuel analysis journal August 2018
Discrimination of weapons-grade plutonium from thermal reactors in nuclear forensics journal September 2019

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Related Subjects

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