JENDL-4.0


Nuclide MAT Numerical Data Comments Figures*) Sig. table
92-U -230 9213 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
92-U -231 9216 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
92-U -232 9219 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
92-U -233 9222 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
[update 1] (2012/09/14) original , 0K , 300K comment
92-U -234 9225 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
[update 2] (2013/07/10) original , 0K , 300K comment
92-U -235 9228 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
[update 1] (2012/09/14) original , 0K , 300K comment
92-U -236 9231 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
92-U -237 9234 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
92-U -238 9237 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
[update 1] (2012/09/14) original , 0K , 300K comment


*) 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.