期刊
ANNALS OF NUCLEAR ENERGY
卷 197, 期 -, 页码 -出版社
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2023.110248
关键词
SFR; Sensitivity and uncertainty analysis; Anisotropy; Nuclear data; Angular distribution; Legendre scattering coefficient
This paper analyzes the impact of nuclear data uncertainties on the safety of advanced reactors, with a specific focus on angular distribution uncertainties. Through sensitivity and uncertainty analysis, key parameters for MOX3600 are identified, and a comparison of different libraries' uncertainties on the eigenvalue is performed.
Nuclear data uncertainties are considered a main limiting factor in proving safety of advanced reactors. A reasonable amount of available information should be applied to sensitivity and uncertainty analyses for this, and this work considers the influence of usually omitted angular distribution uncertainties. A sensitivity and uncertainty analysis of MOX3600 is conducted using Serpent. The angular distribution influence is assessed by applying covariances of the state-of-the-art libraries. The sensitivity analysis shows that quantifying the influence of higher-order Legendre moment uncertainties on the eigenvalue and void reactivity is of minor importance for MOX3600. The uncertainty analysis shows the P1-coefficients for 238U and 16O introduce uncertainties to the eigenvalue similar to 56Fe and should be accounted for. A library comparison reveals TENDL-2021 and ENDF/B-VIII.0 introduce uncertainties of a few hundred pcm to the eigenvalue, and the data should be reassessed, while the other libraries give an uncertainty of several tens of pcm.
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