JENDL-5


Nuclide MAT Numerical Data*1 Comments Figures*2) Sig. table
96-Cm-240 9625 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
96-Cm-241 9628 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
96-Cm-242 9631 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
96-Cm-243 9634 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
96-Cm-244 9637 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
96-Cm-245 9640 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
96-Cm-246 9643 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
96-Cm-247 9646 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
96-Cm-248 9649 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
96-Cm-249 9652 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
96-Cm-250 9655 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