Libraries with Expanded Representation of Fission Product Yields for Calculations of the Nuclide Composition of Fuel in a Fast Spectrum

• Published in: Atomic energy (New York, N.Y.) Vol. 117; no. 6; pp. 427 - 433
• Main Authors: Mitenkova, E. F., Novikov, N. V., Solov’eva, E. V.
• Format: Journal Article
• Language: English
• Published: Boston Springer US 01.04.2015; Springer; Springer Nature B.V
• Subjects: Accuracy; Energy; Fission products; Fuels; Hadrons; Heavy Ions; Libraries; Mathematical analysis; Nuclear accidents & safety; Nuclear Chemistry; Nuclear Energy; Nuclear engineering; Nuclear fission; Nuclear fuels; Nuclear Physics; Nuclear reactors; Nuclear safety; Nuclides; Physics; Physics and Astronomy; Plutonium; Radioactive wastes; Spent nuclear fuels; Spent reactor fuels; Statistical analysis; Uranium; Zirconium; Transport Cross Section; Metal Fuel; Spend Fuel; Fission Product; Nuclear Data
• ISSN: 1063-4258; 1573-8205
• DOI: 10.1007/s10512-015-9943-3

The calculation of the spent-fuel composition is the baseline problem of the analysis of the nuclear and radiological safety of objects with spent fuel assemblies. The use of fission product libraries formed on the basis of evaluated nuclear data with an enlarged number of energy points is especially important for high-precision calculations of the nuclide composition of fuel irradiated in a fast spectrum. The results of an analysis of the nuclide composition of mixed oxide and uranium-plutonium-zirconium metal fuel with burnup ~10% h.a. in a fast spectrum, which were obtained in high-precision calculations based on data from different fission product yield libraries, are presented.