The table below lists the production cross-sections of residual nuclei stored in the JENDL-4.0 High Energy File (JENDL-4.0/HE). They are generated by the product of MF=3, MT=5 (reaction cross-section) and MF=6, MT=5 (relative production of residual nucleus). In JENDL-4.0/HE, MT=5 is not used to describe the neutron-induced cross-sections below 20 MeV. Therefore, neutron-induced data in the energy range are not included here. As for these data, please refer to the original ones in JENDL-4.0/HE or JENDL-4.0 where cross-sections for each reaction channel are given. Besides, the lower limit of incident energies of proton-induced data is typically 1 MeV. At the incident energies where data points are not given explicitly in the table, the cross sections can be obtained by linear-linear interpolation which is defined in the original file.