A list of unc. sources typically encountered in (n,f) fission cs measurements is provided together with a range of unc., their correlations, and comments on possible cross-correlations between unc. of different experimental datasets as a rough estimate if no information is provided for a specific experiment.
|Unc. source||Typical range||Cor(Expi, Expi)||Cor(Expj, Expj) i ≠ j|
|Sample mass||>1%||Full||≠ 0 if same sample used|
|Counting statistics||Sample and measurement time-dependent||Diagonal||0|
|Detector efficiency||0–0.3%, 1%–2%||Full < 10 MeV||Likely, 0.5–1|
|FF angular distribution||≈ 0.1%||Gaussian||Likely, 0.75–1.0|
|Energy unc.||1%, 1–3 ns||From conversion||Technique-dependent|
|Neutron flux||0%, >1%||0.5–Full||Technique-dependent|
|Impurities in the sample||Sample-dependent||0.9–1||0.5–0.75|
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