Integral nuclear data validation using experimental spent nuclear fuel compositions
Abstract
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.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- OECD Nuclear Energy Agency, Boulogne-Billancourt (France)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1400163
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Engineering and Technology
- Additional Journal Information:
- Journal Volume: 49; Journal Issue: 6; Journal ID: ISSN 1738-5733
- Publisher:
- Korean Nuclear Society
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Adjoint Depletion; Nuclear Data; SFCOMPO Database; Spent Fuel; Uncertainty Analysis
Citation Formats
Gauld, Ian C., Williams, Mark L., Michel-Sendis, Franco, and Martinez, Jesus S. Integral nuclear data validation using experimental spent nuclear fuel compositions. United States: N. p., 2017.
Web. doi:10.1016/j.net.2017.07.002.
Gauld, Ian C., Williams, Mark L., Michel-Sendis, Franco, & Martinez, Jesus S. Integral nuclear data validation using experimental spent nuclear fuel compositions. United States. https://doi.org/10.1016/j.net.2017.07.002
Gauld, Ian C., Williams, Mark L., Michel-Sendis, Franco, and Martinez, Jesus S. Wed .
"Integral nuclear data validation using experimental spent nuclear fuel compositions". United States. https://doi.org/10.1016/j.net.2017.07.002. https://www.osti.gov/servlets/purl/1400163.
@article{osti_1400163,
title = {Integral nuclear data validation using experimental spent nuclear fuel compositions},
author = {Gauld, Ian C. and Williams, Mark L. and Michel-Sendis, Franco and Martinez, Jesus S.},
abstractNote = {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.},
doi = {10.1016/j.net.2017.07.002},
journal = {Nuclear Engineering and Technology},
number = 6,
volume = 49,
place = {United States},
year = {Wed Jul 19 00:00:00 EDT 2017},
month = {Wed Jul 19 00:00:00 EDT 2017}
}
Web of Science