JENDL-5


Nuclide MAT Numerical Data*1 Comments Figures*2) Sig. table
72-Hf-170 7213 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-171 7216 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-172 7219 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-173 7222 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-174 7225 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-175 7228 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-176 7231 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-177 7234 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-178 7237 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-178m1 7238 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-179 7240 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-179m1 7241 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-180 7243 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-180m1 7244 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-181 7246 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
72-Hf-182 7249 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