| Nuclide | MAT | Numerical Data | Comments | Figures*) | Sig. table |
| 94-Pu-236 | 9428 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-237 | 9431 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-238 | 9434 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| [update 1] (2013/07/10) | original , 0K , 300K | comment | ↑ | ↑ | |
| 94-Pu-239 | 9437 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| [update 1] (2012/09/14) | original , 0K , 300K | comment | ↑ | ↑ | 94-Pu-240 | 9440 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-241 | 9443 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-242 | 9446 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| [update 1] (2013/07/10) | original , 0K , 300K | comment | ↑ | ↑ | |
| 94-Pu-244 | 9452 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-246 | 9458 | 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 ↑ : Same as the previous version above because cross sections were not changed. |
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