| Nuclide | MAT | Numerical Data | Comments | Figures*) | Sig. table |
| 91-Pa-229 | 9125 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 91-Pa-230 | 9128 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 91-Pa-231 | 9131 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 91-Pa-232 | 9134 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 91-Pa-233 | 9137 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
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*) 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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