Potential use of concretes for gamma-ray shielding

Abstract

In this study, eleven concrete samples produced in a variety of compositions were irradiated by Na-22, Cs-137 and Co-60 radioactive sources and the measurements of transmitted gamma-rays with the energies of 511, 661.6, 1173.2, 1274.5, 1332.5 keV have been carried out by using a gamma-ray scintillation spectrometer includes a NaI(Tl) scintillation detector and multichannel analyzer (MCA) card. Results of these measurements were then used to determine linear attenuation coefficient (mu), mass attenuation coefficient (mu(m)), half-value layer (HVL) and tenth-value layer (TVL) to estimate the effectiveness of each sample on radiation shielding. The results are explained in the view of the concrete composition and its impact on the gamma-ray interaction probability at different energies. In addition, mass and linear attenuation coefficients that are the most important parameters for estimation of shielding properties of samples are compared with other previously published data for concrete samples from several regions.