JENDL-5


Nuclide MAT Numerical Data*1 Comments Figures*2) Sig. table
98-Cf-246 9843 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
98-Cf-248 9849 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
98-Cf-249 9852 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
98-Cf-250 9855 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
98-Cf-251 9858 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
98-Cf-252 9861 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
98-Cf-253 9864 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
98-Cf-254 9867 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