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The density, boron–boron separation, and molar volume of 4Al2O3–12Na2O-(18-x)SiO2-(64-x) B2O3-(2+2x)Bi2O3 (where x = 2, 4, 6 and 8 mol%) are increasing with the addition of Bi2O3. The addition of Bi2O3 results in an open network structure. The elastic moduli decrease from 34.711 to 29.875 GPa for Young modulus (E); 20.395 to 15.843 GPa for bulk modulus (B); from 15.257 to 13.494 GPa for shear modulus (G) and 40.738 to 33.836 GPa for longitudinal (L) respectively with increased Bi2O3 concentration. FTIR spectrainvestigation found BO3, BO4, SiO4, and BiO6 structural units to be present. The glasses' highest mass attenuation coefficient (MAC) is at 0.0395 MeV, the lowest energy value. It gradually decreases as energy increases. There is a decrease in the linear attenuation coefficient (LAC) values with energy. Sample Bi18 has the highest MAC and LAC values due to its high concentration of Bi2O3. Across the entire energy range, sample Bi18 has the highest effective atomic number, and the lowest half value layer and mean free path values across all energy values. The transmission factor (TF) values for Bi6 indicate that the required thickness for blocking 90% of the radiation must be greater than the thickness necessaryfor the attenuation of 50%. Bi18 has the lowest TF compared to other glass samples. The radiation protection efficiency values for Bi18 are highest, confirming their full protection ability. Bi18's is the best choice for radiation shielding.

In various medical, industrial, and nuclear facilities, it is very necessary to have enough shielding against the radiation released by regularly employed isotopes. In this work, we concentrate on nuclear security as well as the radiation shielding against gamma attenuation capabilities of the borate glasses, including Te and Cu. These glasses have the chemical form of (100-x)[30B2O3–70TeO2]-xCuO, where x = 0, 0.005, 0.01, 0.015, 0.02 wt%. The systems were represented by five distinct samples, labelled as BTCu-20, BTCu-15, BTCu-10, BTCu-5, and BTCu-0, where the number refers to the percentage of CuO in the mixture and the remainder is made up of TeO2 and B2O3. Through the use of FLUKA simulations, the basic characteristics associated with gamma shieldings, such as attenuation and transmission factors, were examined for the particular energy range of 238–1408 MeV emitted from 133Ba, 137Cs, 60Co, 152Eu, and 232Th. The effect of the systematic replacement of CuO by B2O3 and TeO2 on the shielding qualities was explored in depth for gamma radiation. In addition, comparison research was carried out between the currently available borate glasses and the traditional shielding materials. According to the findings of the current investigation, the GHVL was found to be its lowest at 238 keV with values of 0.87, 0.92, 0.98, 1.04, and 1.10 (cm) for BTCu-0, BTCu-5, BTCu-10, BTCu-15, and BTCu-20 glasses, respectively. This points to the possibility that the BTCu-0 sample might be used in radiation shielding applications, which would result in increased nuclear safety.

In the radiation protection application, the metal-polymer composites have been developed for their radiation shielding properties. In this research, the elastomer composites doped by 10 μm and100nm size of lead, bismuth and tungsten particles as filler with 30 and 60 wt percentages were prepared. To survey the shielding properties of the polymer composites using gamma-ray emitted from 152Eu and 137Cs sources, the gamma flux was measured by using NaI(Tl) detector, then the linear attenuation coefficient was calculated. Also, the Monte Carlo simulation (MCs) method was used. The results showed a direct relationship between the linear attenuation coefficients of the absorbent and filler ratio. Also, the decrease in the particle size of the shielding material in each weight percentage improved the radiation shielding features. When the dimension of the particles was in the order of nano-size, more attenuation was achieved. At low energies used for medical diagnostic X-ray applications due to the predominance of the photoelectric effect, bismuth and lead were suitable selection as filler.

This paper examines gamma-ray shielding properties of SBC-Bx glass system with the chemical composition of 40SiO2–10B2O3–xBaO–(45-x)CaO– yZnO– zMgO (where x = 0, 10, 20, 30, and 35 mol% and y = z = 6 mol%). Mass attenuation coefficient (μ/ρ) which is an essential parameter to study gamma-ray shielding properties was obtained in the photon energy range of 0.015–15 MeV using PHITS Monte Carlo code for the proposed glasses. The obtained results were compared with those calculated by WinXCOM program. Both the values of PHITS code and WinXCOM program were observed in very good agreement. The μ/ρ values were then used to derive mean free path (MFP), electron density (Neff), effective atomic number (Zeff), and half value layer (HVL) for all the glasses involved. Additionally, G-P method was employed to estimate exposure buildup factor (EBF) for each glass in the energy range of 0.015–15 MeV up to penetration depths of 40 mfp. The results reveal that gamma-ray shielding effectiveness of the SBC-Bx glasses evolves with increasing BaO content in the glass sample. Such that SBC-B35 glass has superior shielding capacity against gamma-rays among the studied glasses. Gamma-ray shielding properties of SBC-B35 glass were compared with different conventional shielding materials, commercial glasses, and newly developed HMO glasse. Therefore, the investigated glasses have potential uses in gamma shielding applications.

Although radioprotection is globally regulated for high radiation exposure, formal guidelines concerning natural radiation exposure that causes stochastic radiation effects have not been established. The commonly used absorbers lead, tungsten and bismuth are not appropriate for the radioprotection of the public. The primary barrier against natural radiation is the structural components of buildings, where humans spend approximately 80 % of their lifetime. Natural stones are secondary materials, which are applied to walls and floors as coating. This study focuses on the radiation shielding properties of natural stones. Herein, the samples of marble, granite and sedimentary rock traded in Turkey were examined to determine whether they can serve as passive or alternative radioprotection materials. Notable gamma absorption rates were obtained when an intense gamma source with an energy of 662 keV was used. The calculated mass attenuation coefficients were comparable with those of copper and aluminium. The mean mass attenuation coefficient was 0.082 cm 2 /g for marbles and granites and 0.080 cm 2 /g for sedimentary rocks. Considering the stochastic effects, the use of the natural stones as construction materials is anticipated to significantly reduce the natural radiation level in inhabitable regions. Furthermore, natural stones can be used in clinics as secondary radiation shields against low-energy gamma and x-rays., Competing Interests: Declaration of competing interest There is no Conflict of Interest for the manuscript named “Investigation On Radiation Attenuation Properties Of Natural Stone Samples Traded In Turkey”. No financial supply by any foundations were used., (Copyright © 2024 Elsevier B.V. All rights reserved.)