JENDL-5


Nuclide MAT Numerical Data*1 Comments Figures*2) Sig. table
77-Ir-185 7707 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-186 7710 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-187 7713 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-188 7716 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-189 7719 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-190 7722 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-191 7725 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-192 7728 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-192m2 7730 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-193 7731 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-193m1 7732 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-194 7734 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-194m1 7735 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-195 7737 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-196 7740 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
77-Ir-196m1 7741 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