Characterizations of Cement and Modern Sustainable Concrete Incorporating Different Waste Additives

This chapter provides a brief introduction to cement and concrete, from their first utilization in constructions and monuments in different civilizations to their development and use in modern times. It discusses the modern forms of these materials, their physical and chemical properties, and their various applications. The chapter also examines the sustainability of concrete mixed with different waste additives, which can impart desirable properties to concrete, as a promising way to reduce environmental hazards resulting from the landfilling of these wastes. In addition to environmental benefits, waste utilization has economic benefits as well

Investigating the Effect of Gamma and Neutron Irradiation on Portland Cement Provided with Waste Silicate Glass

In this study, samples of commercial Portland cement mixed with 30% weight of crushed waste silicate glass were prepared in the shape of well-dried cylinders. Then, their physical and mechanical properties were investigated for two types of samples: samples without exposure and samples with exposure to gamma-ray and neutron irradiation. A notable deterioration of the physical properties of the irradiated samples relative to the non-irradiated ones was recorded. All the spectroscopic analyses were performed for the samples with exposure and without exposure to gamma-ray and neutron irradiation. The XRD emerging peaks of irradiated samples were studied to estimate the presence and stabilities of major peaks indicating the presence of the main compositions of cement with the amorphous nature of glass. FT-IR transmittance spectra were identified and the bonds were located close to those of identical glasses. Moreover, SEM images and EDX analysis were conducted on the two types of composite samples (without exposure and with exposure to gamma and neutron irradiation) to specify the change in the physical appearance and the chemical composition after irradiation. The attenuation parameters were computed theoretically with the assistance of Phy-X/PSD software to evaluate the gamma-ray and neutron shielding properties by defining the composition and the density of the samples. The irradiation was found to have a negative impact on the shielding ability of the prepared samples where there was an over-reduction in the parameters calculated with the probability that the damage may increase with longer exposure to the radiation