| Nuclide | MAT | Numerical Data | Comments | Figures*) | Sig. table |
| 99-Es-251 | 9911 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 99-Es-252 | 9912 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 99-Es-253 | 9913 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 99-Es-254 | 9914 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 99-Es-254m | 9915 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 99-Es-255 | 9916 | 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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