Abstarct: The effects induced by irradiation on different materials can be constructive or destructive, and these effects vary depending on the type of radiation, the type of irradiated material, and the dose delivered to the target material. The outstanding characteristics of boron carbide (B4C) and silicon carbide (SiC) have introduced them as suitable materials for investigating irradiation effects in nuclear and non-nuclear sciences. In this research, the effect of gamma rays on SiC and B4C was investigated. The samples were irradiated using a 60Co source at doses ranging from 25 to 150 kGy with increments of 25 kGy, and changes in the structural, morphological, optical, electrical, and dielectric properties of the samples were analyzed. The results showed that the optimal performance range of the powders against gamma irradiation was in the dose range of 70 to 100 kGy. In addition, to investigate the possibility of recovering defects induced by gamma irradiation, irradiated samples at doses of 0, 100, and 150 kGy were subjected to thermal treatment, and the effect of temperature up to 1100 °C on the studied properties was examined. The results of the thermal treatment showed that although gamma irradiation caused more severe structural and microstructural effects in boron carbide compared to silicon carbide, the recovery process of irradiation-induced defects was more effective in silicon carbide, and this material exhibited higher structural stability against thermal treatment. To evaluate the effect of gamma irradiation in engineering applications, aluminum matrix composites were prepared by the ARB method using irradiated boron carbide and silicon carbide powders in micro- and nanoscale sizes at doses of 0, 50, 100, and 150 kGy, and the effect of gamma irradiation on the microstructure and mechanical properties of the resulting composites was investigated. The aim of this research was to investigate and optimize the behavior and properties of boron carbide and silicon carbide in micro- and nanoscale forms under gamma irradiation, to evaluate the role of thermal treatment in recovering induced defects, and to investigate the applicability of these materials in aluminum matrix composites for the development of efficient materials for industrial applications, especially nuclear industries and other related applications.