| Nuclide | MAT | Numerical Data*1 | Comments | Figures*2) | Sig. table |
| 94-Pu-236 | 9428 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-237 | 9431 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-238 | 9434 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-239 | 9437 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-240 | 9440 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-241 | 9443 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-242 | 9446 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-244 | 9452 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-246 | 9458 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 94-Pu-247 | 9461 | 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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