JENDL-5


Nuclide MAT Numerical Data*1 Comments Figures*2) Sig. table
73-Ta-177 7316 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
73-Ta-179 7322 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
73-Ta-180 7325 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
73-Ta-180m1 7326 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
73-Ta-181 7328 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
73-Ta-182 7331 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
73-Ta-183 7334 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 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