JENDL-5


Nuclide MAT Numerical Data*1 Comments Figures*2) Sig. table
90-Th-227 9025 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
90-Th-228 9028 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
90-Th-229 9031 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
90-Th-230 9034 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
90-Th-231 9037 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
90-Th-232 9040 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
90-Th-233 9043 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 Fig4 table
90-Th-234 9046 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