JENDL-4.0


Nuclide MAT Numerical Data Comments Figures*) Sig. table
90-Th-227 9025 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
90-Th-228 9028 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
90-Th-229 9031 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
90-Th-230 9034 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
90-Th-231 9037 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
90-Th-232 9040 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
90-Th-233 9043 original , 0K , 300K comment Fig1 Fig2 Fig3 Fig4 table
90-Th-234 9046 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