| Nuclide | MAT | Numerical Data | Comments | Figures*) | Sig. table |
| 96-Cm-240 | 9625 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 96-Cm-241 | 9628 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 96-Cm-242 | 9631 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 96-Cm-243 | 9634 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 96-Cm-244 | 9637 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 96-Cm-245 | 9640 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 96-Cm-246 | 9643 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 96-Cm-247 | 9646 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 96-Cm-248 | 9649 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 96-Cm-249 | 9652 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 96-Cm-250 | 9655 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
|
*) 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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