Skip to main content
SHARE
Research Highlight

Uncertainty Quantification in (α,n) Neutron Source Calculations in an Oxide Matrix

ORNL Image
  • Background and Motivation
    • Nuclear data describing α-particle interactions on light nuclei are essential for calculating (α,n) neutron emissions
    • Currently, in codes like SOURCES4C, there is no uncertainty data to estimate neutron source intensities or emission spectra​​
  • Methodology
    • The ORNL SAMMY code was used to evaluate 17,18O(α,n) cross sections in order to generate the uncertainty in the neutron generation rates for uranium oxide fuel types
  • ​Significance and Impact
    • Generation of (α,n) covariance data is demonstrated for the first time and used for uncertainty analyses in applications crucial for safeguards and non-proliferation