| Nuclide | MAT | Numerical Data*1 | Comments | Figures*2) | Sig. table |
| 62-Sm-144 | 6225 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 62-Sm-145 | 6228 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 62-Sm-146 | 6231 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 62-Sm-147 | 6234 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 62-Sm-148 | 6237 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 62-Sm-149 | 6240 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 62-Sm-150 | 6243 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 62-Sm-151 | 6246 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 62-Sm-152 | 6249 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 62-Sm-153 | 6252 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 62-Sm-154 | 6255 | 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 |
|||||
