[en] The distribution of secondary γ-ray doses generated from the interaction of reactor neutrons of definite energy ranges have been measured in ordinary and ilmenite concrete shields of densities 2.3 and 4.6 g/cm³ respectively . A collimated beam of reactor neutrons emitted from one of the horizontal channels of the TRR reactor was used. The γ-dose s were measured using a ⁷LiF Teflon TLD dosimeter. The results showed that the intensity of secondary γ-rays produced in ordinary concrete is more than that produced in ilmenite concrete. The penetration of secondary γ in ordinary concrete is more than the in case of ilmenite concrete. The data also show that at large thicknesses, the effect of build up factor is more pronounced in ordinary concrete than in ilmenite concrete. In addition the results show that thermal neutrons emitted directly from the reactor are the main source of secondary γ-ray at the first layers of the shield. However, neutrons of energies above 0.4 eV give the main contribution in the production of secondary γ-rays for thicknesses greater than 30 cm