Table 1
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 |
| Attenuation | 0.02%–2% | Gaussian | Likely |
| 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 |
| Background | 0.2–>10% | Gaussian | Possible |
| Energy unc. | 1%, 1–3 ns | From conversion | Technique-dependent |
| Neutron flux | 0%, >1% | 0.5–Full | Technique-dependent |
| Multiple scattering | 0.2%–1% | Gaussian | 0.5–0.75 |
| Impurities in the sample | Sample-dependent | 0.9–1 | 0.5–0.75 |
| Dead time | >0.1% | Full | 0 |
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