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Report No.

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

Michel-Sendis, F.*; Gauld, I.*; Martinez, J. S.*; Alejano, C.*; Bossant, M.*; Boulanger, D.*; Cabellos, O.*; Chrapciak, V.*; Conde, J.*; Fast, I.*; Gren, M.*; Govers, K.*; Gysemans, M.*; Hannstein, V.*; Havl$r{u}$j, F.*; Hennebach, M.*; Hordosy, G.*; Ilas, G.*; Kilger, R.*; Mills, R.*; Mountford, D.*; Ortego, P.*; Radulescu, G.*; Rahimi, M.*; Ranta-Aho, A.*; Rantam$"a$ki, K.*; Ruprecht, B.*; Soppera, N.*; Stuke, M.*; Suyama, Kenya; Tittelbach, S.*; Tore, C.*; Van Winckel, S.*; Vasiliev, A.*; Watanabe, Tomoaki ; Yamamoto, Toru*; Yamamoto, Toshihisa*

SFCOMPO-2.0 is the new release of the NEA database of experimentally measured assays, i.e. isotopic concentrations from destructive radiochemical analyses of spent nuclear fuel samples, complemented with design information of 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, which are necessary for the modelling and simulation of the isotopic evolution of the fuel during irradiation. SFCOMPO-2.0 has been developed and is maintained by the OECD Nuclear Energy Agency (NEA) under the guidance of the Expert Group on Assay Data of Spent Nuclear Fuel (EGADSNF) of the NEA Working Party on Nuclear Criticality Safety (WPNCS). In this paper, the new database is described. Applications of SFCOMPO-2.0 for computer code validation, integral nuclear data benchmarking, and uncertainty analysis in nuclear waste package analysis are briefly illustrated.



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Category:Nuclear Science & Technology



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