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    Lead-free bismuth glass system towards eco-friendly radiation shielding applications
    (Elsevier, 2023) Alzahrani, Jamila S.; Sriwunkum, Chahkrit; Tonguc, Baris Tamer; Alothman, Miysoon A.; Olarinoye, I. O.; Al-Buriahi, M. S.
    In this study, the gamma-ray photon, electron, proton, helium ion, carbon ion, thermal neutron, and fast neutron interaction parameters of the (70-x)(Bi2O3 + ZnO) + x(V2O5 + TeO2) + 20B(2)O(3) + 6.5SiO(2) + 2.5Al(2)O(3) + 1(CeO2 + Sb2O3) glass system were estimated with the aim of assessing their radiation shielding potentials. The mass attenuation coefficients (MACs) of the glasses were estimated for photon energies between 0.015 and 15 MeV using the PHITS simulation code and XCOM software. The stopping powers of charged radiation such as electrons, protons, alpha-particles, and carbon ions were also estimated by Monte Carlo simulation of particle transport using PHITS. The narrow beam transmission simulated using PHITS yielded values of MAC that were not so different from those from XCOM. The MACs of B/V-ZBVSA1 vary from 0.039-90.747 cm(2)/g, while those of B/V-ZBVSA2, B/V-ZBVSA3, and B/V-ZBVSA4 vary from 0.035-69.724, 0.036-73.088, and 0.037-70.597 cm(2)/g, respectively. The HVL of the glasses varied from 0.011-2.56 cm, 0.019-3.69 cm, 0.017-3.31 cm, and 0.017-3.36 cm for B/V-ZBVSA1 - B/V-ZBVSA4, respectively The effective atomic number varied within the limits: 28.36-76.06, 19.67-67.91, 22.14-68.70, and 22.39-68.08 for BV-ZBVSA1 - BV-ZBVSA4, respectively. The stopping powers (S-p) of electrons in BV-ZBVSA1, BV-ZBVSA2, BV-ZBVSA3, and BV-ZBVSA4 were in the range 1.219-8.043 MeVcm(2)/g, 1.295-9.306 MeVcm(2)/g, 1.264-8.859 MeVcm(2)/g, and 1.257-8.793 MeVcm(2)/g correspondingly. Comparatively, the S-p of protons, alpha-radiation, and carbon ions follows the order: BV-ZBVSA2 > BV-ZBVSA3 > BV-ZBVSA4 > BV-ZBVSA1. Also, the value of Sigma(R) for BV-ZBVSA1, BV-ZBVSA2, BV-ZBVSA3, and BV-ZBVSA4 was 0.1171, 0.1126, 0.1133, and 0.1103 cm(-1) accordingly, while the corresponding total cross-section of thermal neutrons was 67.6227, 46.8356, 59.1179, and 56.6994 cm(-1). The present glasses showed superiority in absorbing photons and neutrons compared to some existing shields and previously recommended glasses. The present glassy samples, thus, can be adopted for radiation protection purposes, among others in radiation facilities.
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    X- and gamma rays cross sections and nuclear shielding performance of recycled cathode ray tube doping with high concentrations of Na2CO3
    (Pergamon-Elsevier Science Ltd, 2024) Al-Buriahi, M. S.; Alzahrani, Jamila S.; Basha, Beriham; Tonguc, B. T.; Alrowaili, Z. A.; Sriwunkum, Chahkrit; Olarinoye, I. O.
    In an attempt to mitigate the increasing number of waste Cathod Ray Tube (CRT) glass in the environment, provide a safe, cheaper, and environmentally attractive recycling route for the glasses, and provide an alternative material for gamma radiation absorption applications, this study investigated the influence of adding Na2CO3 on the density, and gamma photon-absorbing prowess of CRT glass. Using the powder metallurgy process, CRT-NCx glasses consisting of CRT glass powder mixed with two distinct weight concentrations (20% (CRT-NC20 and 40% (CRT-NC40)) of Na2CO3 powder were prepared. The mass attenuation coefficients (mu/rho) of the prepared glasses were obtained using FLUKA simulations for 15 keV-15 MeV photons. The density of CRT, CRT-NC20, and CRTNC40 were 3.117 g/cm3, 2.987 g/cm3, and 2.894 g/cm3, respectively. The range of mu/rho for CRT, CRT-NC20, and CRT-NC40 corresponded to 0.0326-45.5236 cm2/g, 0.030-35.0662 cm2/g, and 0.0278-26.9813 cm2/g, respectively. The half-value layer and mean free path was found to vary within the range 0.005-6.822 cm and 0.007-9.842 cm for CRT; 0.007-7.748 cm and 0.010-11.178 cm for CRT-NC20; and 0.009-8.633 cm and 0.013-12.455 cm for CRT-NC40. The minimum and maximum values of mu en rho were 0.0216 and 37.7566 cm2/g for CRT, 0.0202 and 29.1167 cm2/g for CRT-NC20, and 0.01921 and 22.4430 cm2/g for CRT-NC40. CRT-rich glass showed higher radiation absorbed doses for the same beam energy and glass thickness. Na2CO3-rich glasses had lower buildup factors BFs, hence preferable in broad beam transmission scenarios. The investigated CRT-NCx glasses are more attractive for radiation protection functions in contrast to some well-known radiation shielding materials considering their lower mean free paths. The present glass system provides and alternative and effective gamma radiation shield, and also proffers a way of upcycling waste CRT glasses.