| Nuclide | MAT | Numerical Data*1 | Comments | Figures*2) | Sig. table |
| 97-Bk-245 | 9740 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 97-Bk-246 | 9743 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 97-Bk-247 | 9746 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 97-Bk-248 | 9749 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 97-Bk-248m1 | 9750 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 97-Bk-249 | 9752 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 97-Bk-250 | 9755 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
|
*1) u20: Data up to 20 MeV. *2) Fig1, Fig2 and Fig3 are made from pointwise files at 300 K. Fig1 : Total, elastic and inelastic scattering, capture and fission cross sections Fig2 : Same as Fig1 but the cross sections are averaged in 70 energy group intervals Fig3 : Threshold reaction cross sections Fig4 : Number of prompt and delayed neutrons per fission |
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