JENDL-5


Nuclide MAT Numerical Data*1 Comments Figures*2) Sig. table
63-Eu-145 6307 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-146 6310 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-147 6313 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-148 6316 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-149 6319 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-150 6322 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-150m1 6323 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-151 6325 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-152 6328 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-152m1 6329 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-153 6331 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-154 6334 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-155 6337 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-156 6340 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
63-Eu-157 6343 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