Radiation shielding properties of spark plasma sintered boron carbide-aluminium composites

In this study gamma and neutron attenuation properties of boron carbide-aluminium (B4C-Al) composites were investigated. B4C-Al composites were produced by spark plasma sintering method. Aluminum percentages in the B4C-Al composites were 0%, 10%, 15%, and 20% by volume. The composite materials were performed against gamma and neutron sources. Cs-137 and Co-60 gamma radioisotopes were used as gamma sources and Pu-Be neutron howitzer was used for neutron source. Theoretical mass attenuation coefficients were determined by using XCOM computer code and compared with the experimental results. It has been seen that the experimental results were close to the theoretical results. Total macroscopic cross-sections of the samples were determined for Pu-Be neutrons. It is concluded that increasing aluminum ratio in the B4C-Al composites causes higher gamma attenuation behavior for Cs-137 and Co-60 gamma sources and the total macroscopic cross-sections of the B4C-Al composites decrease by increasing Al concentration.