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

Kevin Govers, Mireille Gysemans, F. Michel-Sendis, I. Gauld, J.S. Martinez, C. Alejano, M. Bossant, Danièle Boulanger, O. Cabellos, V. Chrapciak, J. Conde, I. Fast, M. Gren, Kevin Govers, Mireille Gysemans, V. Hannstein, F. Havluj, M. Hennebach, G. Hordosy, G. IlasR. Kilger, Robert Mills, D. Mountford, P. Ortego, G. Radulescu, M. Rahimi, A. Ranta-Aho, K. Rantamaki, B. Ruprecht, N. Soppera, M. Stuke, K. Suyama, S. Tittelbach, C. Tore, Stefaan Van Winckel, A. Vasiliev, T. Watanabe, Toru Yamamoto, Toshihisa Yamamoto

    Research outputpeer-review


    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.
    Original languageEnglish
    Pages (from-to)779-788
    Number of pages10
    JournalAnnals of nuclear energy
    StatePublished - 2 Aug 2017

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