JENDL-5


Nuclide MAT Numerical Data*1 Comments Figures*2) Sig. table
66-Dy-154 6619 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-155 6622 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-156 6625 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-157 6628 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-158 6631 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-159 6634 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-160 6637 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-161 6640 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-162 6643 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-163 6646 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-164 6649 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-165 6652 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
66-Dy-166 6655 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