JENDL-4.0


Nuclide MAT Numerical Data Comments Figures*) Sig. table
88-Ra-223 8825 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
88-Ra-224 8828 original , 0K , 300K comment Fig1 Fig2 Fig3 table
[update 1] (2013/07/10) original , 0K , 300K comment
88-Ra-225 8831 original , 0K , 300K comment Fig1 Fig2 Fig3 table
[update 1] (2013/07/10) original , 0K , 300K comment
88-Ra-226 8834 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table


*) 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
 
↑ : Same as the previous version above because cross sections were not changed.