Integral nuclear data validation using experimental spent nuclear fuel compositions

Journal Article · 19 July 2017 · Nuclear Engineering and Technology

DOI: https://doi.org/10.1016/j.net.2017.07.002 · OSTI ID:1400163

Gauld, Ian C.  ^[1]; Williams, Mark L. ^[1]; Michel-Sendis, Franco ^[2]; Martinez, Jesus S. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2. OECD Nuclear Energy Agency, Boulogne-Billancourt (France)

Measurements of the isotopic contents of spent nuclear fuel provide experimental data that are a prerequisite for validating computer codes and nuclear data for many spent fuel applications. Under the auspices of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) and guidance of the Expert Group on Assay Data of Spent Nuclear Fuel of the NEA Working Party on Nuclear Criticality Safety, a new database of expanded spent fuel isotopic compositions has been compiled. The database, Spent Fuel Compositions (SFCOMPO) 2.0, includes measured data for more than 750 fuel samples acquired from 44 different reactors and representing eight different reactor technologies. Measurements for more than 90 isotopes are included. This new database provides data essential for establishing the reliability of code systems for inventory predictions, but it also has broader potential application to nuclear data evaluation. Furthermore, the database, together with adjoint based sensitivity and uncertainty tools for transmutation systems developed to quantify the importance of nuclear data on nuclide concentrations, are described.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 1400163
• Journal Information: Nuclear Engineering and Technology, Vol. 49, Issue 6; ISSN 1738-5733
• Publisher: Korean Nuclear SocietyCopyright Statement
• Country of Publication: United States
• Language: English