| Nuclide | MAT | Numerical Data*1 | Comments | Figures*2) | Sig. table |
| 61-Pm-143 | 6137 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 61-Pm-144 | 6140 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 61-Pm-145 | 6143 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 61-Pm-146 | 6146 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 61-Pm-147 | 6149 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 61-Pm-148 | 6152 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 61-Pm-148m1 | 6153 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 61-Pm-149 | 6155 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 61-Pm-150 | 6158 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 61-Pm-151 | 6161 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | 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 |
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