Akademik Veri Yönetim Sistemi
Ceramics International, cilt.51, sa.22, ss.36961-36978, 2025 (SCI-Expanded)
This study examines the radiation shielding performance of functionally graded composite materials that are reinforced with ceramic particles. The studied samples were fabricated by adding B4C, TiO2, and a combination of B4C + TiO2 ceramic particles into the AA6082 matrix in various proportions by weight. Then they were evaluated both theoretically and experimentally in terms of their radiation shielding performance. Fast and thermal neutron attenuation coefficients were calculated by using the NGCal software. The gamma radiation shielding performances of the samples were experimentally assessed at photon energies of 0.662 MeV, 1.173 MeV, and 1.332 MeV using 60Co and 137Cs sources. According to the experimental results, the linear attenuation coefficient values of the samples at 0.662 MeV were found to be in the following order: TiO2 > AA6082 > B4C > Hybrid. At higher photon energies (1.173 MeV and 1.332 MeV), the linear attenuation coefficient values ranked as TiO2 > B4C > Hybrid > AA6082 and TiO2 > Hybrid > B4C > AA6082, respectively. The superior gamma shielding performance of TiO2-reinforced functionally graded composites was attributed to their higher density and atomic number. On the other hand, B4C-reinforced composites exhibited excellent thermal neutron attenuation due to the high neutron absorption cross-section of boron. The hybrid composites, incorporating both TiO2 and B4C, demonstrated moderate shielding performance, likely due to challenges in achieving a homogeneous distribution of reinforcement particles. Functionally graded composites containing TiO2 exhibited the lowest values of half-value layer, tenth-value layer, and mean free path among the tested samples, indicating their effectiveness in gamma shielding applications. Incorporating TiO2 and B4C into AA6082 significantly enhanced its attenuation properties against thermal neutrons, fast neutrons, and gamma radiation. These materials hold significant promise for applications in nuclear reactors, medical radiation shielding, and other radiation protection fields. Further optimization of microstructural homogeneity and production parameters is recommended to maximize their shielding efficiency and broaden their applicability.