| Nuclide | MAT | Numerical Data*1 | Comments | Figures*2) | Sig. table |
| 58-Ce-134 | 5819 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 58-Ce-135 | 5822 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 58-Ce-136 | 5825 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 58-Ce-137m1 | 5829 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 58-Ce-138 | 5831 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 58-Ce-139 | 5834 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 58-Ce-140 | 5837 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 58-Ce-141 | 5840 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 58-Ce-142 | 5843 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 58-Ce-143 | 5846 | original, 0K, 300K u20 | comment | Fig1 Fig2 Fig3 | table |
| 58-Ce-144 | 5849 | 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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