On the use of green concrete composite as a nuclear radiation shielding material

Highlights: • Sustainable Green concrete samples were prepared by partial replacing cement with industrial waste by-product fly ash. • Measurement of physical and mechanical properties of prepared concrete samples. • Experimental measurement of Gamma-ray shielding properties using narrow beam transmission geometry. • Calculation of attenuation parameters using WinXCOM software and FLUKA Monte-Carlo simulation code. • Fast neutron removal cross-section (FNRC) values were calculated for the prepared concrete samples. In the present study, the samples of sustainable green concrete composites reinforced with hematite were prepared by partially replacing Ordinary Portland Cement (OPC) with flyash. The mechanical and gamma radiation shielding parameters have been measured experimentally for these prepared concrete composites. The experimental measurements were performed by using narrow beam transmission geometry (total scatter acceptance angle (θ_sc) = 1.78°) with NaI(Tl) spectroscopy in the gamma photon energy range of 59.54 keV–1332 keV. These experimentally measured values of linear attenuation coefficient are further used to calculate the values of half value layer, mass attenuation coefficient, effective atomic number, electron density, exposure build up factor, Klein-Nishina electronic, electron transfer and Compton mass attenuation coefficients. The fast neutron removal cross sections (∑_R cm⁻¹) were calculated for the concrete samples under investigations. The experimental values of mass attenuation coefficient have been compared with the results of theoretical values obtained by using winXCOM computer software and FLUKA simulations code. Excellent agreements have been observed between experimental, theoretical and simulation results.