Neutron nuclear data on 96,98,99,100,101,102,103,104,105,106 Ru have been evaluated for the next version of JENDL general-purpose file in the energy region from 10 −5 eV to 20 MeV. The thermal capture cross sections of 96,102 Ru were modified so as to reproduce the latest measured data. The statistical model was applied to calculate the cross sections above the resolved resonance region. In the calculations, coupled-channel optical-model parameters were used for neutrons. Preequilibrium and direct-reaction processes were taken into account in addition to the compound process. The present evaluation is consistent with available experimental data. The evaluated data are compiled into an ENDF-formatted data file.