Gamma and neutron shielding behavior of spark plasma sintered boron carbide-tungsten based composites

Abstract

In this study gamma and neutron attenuation properties of boron carbide-tungsten (B4C-W) based composites were investigated. B4C-W based composites were produced by spark plasma sintering (SPS) method. W additions were 5%, 10%. and 15% by volume. Samples with theoretical densities were obtained. Occurance of W2B5 phase with a reaction between B4C and W particles were observed with XRD and SEM investigations. The materials were subjected to gamma and neutron sources. Cs-137 and Co-60 gamma radioisotopes were used as gamma, and Pu-Be Neutron Howitzer was used as neutron source. Linear and mass attenuation coefficients of the composites were carried out for gamma sources by using gamma transmission technique. Furthermore, total macroscopic cross-sections of the samples were determined for Pu-Be neutrons. In conclusion, increasing W ratio in the B4C-W system causes higher gamma attenuation behavior for gamma sources, but the macroscopic cross-sections of the B4C-W composites decrease by increasing W concentration.