For the Fe–9 at.% Cr alloy, radiation-induced segregation is simulated in the model based on the first and second Fick’s laws with inverse Kirkendall effect considered. The governing quantitative characteristics of radiation-induced segregation are systematized and calculated. Such characteristics include the following: concentration profiles of Cr atoms and point defects, surface concentration of Cr atoms, the value of surface enrichment (depletion) of Cr atoms, the full width of the concentration profile of Cr atoms at half maximum enrichment (depletion), segregation area of Cr and discriminant of radiation-induced segregation of Cr atoms in a steady state. The effect of the Fe–9 at.% Cr alloy dislocation subsystem on the specified characteristics of radiation-induced segregation is studied due to the absorption of nonequilibrium point defects. The dislocation subsystem is shown to suppress the effects of radiation-induced segregation. The concentration profiles of Cr atoms and point defects at the selected values of dislocation densities in the alloy dislocation subsystem (0, 10$^{12}$ m$^{-2}$, 10$^{14}$ m$^{-2}$, 10$^{16}$ m$^{-2}$) are calculated. For the values of dislocation densities, the dependence of the surface enrichment of Cr atoms on the irradiation dose increased from 10$^{-4}$ dpa to 10$^{2}$ dpa is studied and the dependences of the governing quantitative characteristics of radiation-induced segregation on temperature changed from 250°С to 650°С are analysed.