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In the present research paper, we present the gamma shielding characterization and the optical properties of a tellurite glass system chemically defined as 64TeO 2 –15Na 2 O–5BaO-xBi 2 O 3 -(15-x)WO 3 –1Yb 2 O 3. The study also focused on the evolution of gamma attenuation and optical parameters as the chemical definition of the glass system changed. The optical constants estimated and analyzed include the molar refractivity (R m) , molar polarizability (α m o l ), reflectance loss, optical transmission, metallization criterion, static dielectric constant, and optical dielectric constant. The values of the mass attenuation coefficient (μ ρ) other basic shielding quantities were also calculated and analyzed in order to reveal the relative shielding effectiveness of the glasses and their potential for radiation safety applications. For TNY-W/Bi1, TNY-W/Bi2, and TNY-W/Bi3, having Bi 2 O 3 molar concentrations of 0, 5, and 10 mol%, respectively, the density was 5.42 g/cm3, 5.56 g/cm3, and 5.67 g/cm3, while the molar volume had values of 29.119 cm3/mol, 30.491 cm3/mol, and 31.964 cm3/mol, respectively. The R m and α m o l increased from 17.72 to 19.68 cm3/mole and 7.03 × 10−24 cm3 to 7.81 × 10−24 cm3, respectively. All other estimated optical parameters vary according to glass composition and the refractive index. The values of μ ρ fluctuated between 0.0344 and 56.4869 cm2/g for TNY-W/Bi1, 0.0351 and 59.3506 cm2/g for TNY-W/Bi2, and 0.0368 and 61.8444 cm2/g for TNY-W/Bi3. For a glass thickness of 10 mm and at 15 keV, the absorbed dose rates in TNY-W/Bi1, TNY-W/Bi2, and TNY-W/Bi3 were 50 μR/h, 52 μR/h, and 53 μR/h, respectively. The increase in Bi 2 O 3 content improved the photon and energy absorption capacities of the TNY-W/BiX glasses. The replacement of WO 3 with Bi 2 O 3 in the glass system increased photon buildup factors in the glasses as well. The present glasses showed better photon absorption capacities than light and heavy concrete, standard shielding glasses, alloys, and rock samples. • Gamma attenuation of TeO 2 /Bi2O 3 /WO 3 glass system is reported. • Radiation shielding performance is estimated. • Monte Carlo simulations are employed. • A good agreement between the theory and the simulation. • TNY-W/Bi3 system has a potential use in nuclear and medical applications. [ABSTRACT FROM AUTHOR]

Composite materials such as metal glasses or alloys combine the useful properties and compensate for the shortcomings of the constituent materials. Therefore, a composite material has improved attributes relative to its individual constituents and therefore, more functionalities. This makes alloys very attractive for radiation shielding in many extreme radiation environments. In this report, different gamma-photon interaction parameters of four SnX alloys (where, X = As, Bi, P, and Sb) were evaluated and analyzed at 0.2, 0.662, and 1.25 MeV. The mass attenuation coefficients (μ ⁄ ρ) of the materials were calculated using the XCOM. Furthermore, other parameters such as the effective atomic number (Z e f f ), electron density (N e f f ), mass energy absorption, the specific gamma constant, absorbed gamma dose rate, and buildup factors were also estimated. The values of μ ρ decreased with energy from 0.2844 cm2/g to 0.0518 cm2/g for SnP, 0.2664 cm2/g to 0.0510 cm2/g for SnAs, 0.3321 cm2/g to 0.0509 cm2/g for SnSb, and 0.7771 cm2/g to 0.0664 cm2/g for SnBi. Also, (Z e f f) S n X and (N e f f) S n X decreased with photon energy within the ranges of 33.01–41.25 and 2.66–3.32 1023 electrons/g for SnP; 41.68–44.30 and 2.59–2.76 1023 electrons/g for SnAs; 56.50–56.51 and 2.329–2.53 1023 electrons/g for SnSb; and 68.26–75.43 and 2.51–2.77 1023 electrons/g for SnBi, respectively. The exposure buildup factor of SnP, SnAs, SnSb, and SnBi at a depth of 40 mfp for 1,25 MeV photons were 27, 30, 17, and 16, respectively. Based on the computed quantities, it is clear that SnBi interact more with photons compared to the other three SnX materials. Moreover, the SnX materials can perform better than some commercial and well-known glass shields, especially at low photon energies. Being Pb-free, the SnX shields are preferable to commercial glass shields containing Pb for radiation protection purposes. • Gamma attenuation of SnX (X = As, Bi, P, and Sb) monolayers. • Radiation shielding performance is studied. • Monte Carlo simulations are employed. • SnX shields are preferable to commercial glass shields. • SnBi monolayer has a potential use in nuclear and medical applications. [ABSTRACT FROM AUTHOR]

In this paper, the synthesis and gamma-radiation shielding attributes of xMgO-(30-x)BaO-69.5B 2 O 3 -0.5Fe 2 O 3 glasses are reported. The aim is to ascertain the optimum chemical structure of the glass system for gamma radiation shielding applications and dosimetry. The simple melt and quench method was adopted for the synthesis of the xMgO-(30-x)BaO-69.5B 2 O 3 -0.5Fe 2 O 3 glasses, where for x = 0, 5, 10, 12, and 15 mol% represented MBBFe-0, MBBFe-1, MBBFe-2, MBBFe-3, and MBBFe-4, respectively. The mass attenuation coefficients μ / ρ of the glasses were evaluated using the XCOM and FLUKA simulations for the photon energy range of 15 keV–15 MeV. The differences between the values of μ / ρ evaluated with FLUKA and XCOM were within 0.96%. The mass attenuation coefficients of MBBFe-0, MBBFe-1, MBBFe-2, MBBFe-3, and MBBFe-4 ranged from 0.0288 to 28.6205 cm2/g, 0.0279–25.6462 cm2/g, 0.0268–22.2712 cm2/g, 0.0260–20.4073 cm2/g and 0.0251–18.4086 cm2/g, respectively. The corresponding values of the half-value layer at 15 MeV are 7.06 cm, 7.64 cm, 8.25 cm, 8.70 cm, and 9.53 cm for MBBFe-0, MBBFe-1, MBBFe-2, MBBFe-3, and MBBFe-4, respectively. The specific gamma constant values of MBBFe-X glasses are in the range 11.289–264.417 Rm2/Cihr, 10.871–236.716 Rm2/Cihr, 10.386–205.282 Rm2/Cihr, 9.931–187.921 Rm2/Cihr and 9.444–175.515 Rm2/Cihr for MBBFe-0, MBBFe-1, MBBFe-2, MBBFe-3, and MBBFe-4, respectively. The substitution of BaO with MgO therefore, depreciated the gamma shielding efficacy, photon energy absorption abilities, and interaction per unit mass of the MBBFe-X glasses. This study concludes that MBBFe-0 is the best gamma absorber among the studied glasses and has the potential to be a good gamma-radiation shield with an efficiency that supersedes many traditional and modern shielding materials such as concrete, metal alloys, polymers, rocks, commercial glass shields, and other shielding glasses. • New glassy system are reported for radiation uses. • Gamma shielding performance is studied for the new system. • Monte Carlo simulations are carried out. • A good agreement between the theory and the simulation. • MBBFe-X has a potential use in shielding applications. [ABSTRACT FROM AUTHOR]

The physical, structural, mechanical, and radiation (gamma photon and neutron) shielding properties of CRT screen glass and Bi 2 O 3 mixtures are presented in this study with the aim of adopting them as cheap, transparent, and environmentally safe glass shields for radiation protection purposes. Bi 2 O 3 -doped CRT screen glass samples are prepared by the ball milling and cold press methods and coded as TVS, TVS-Bi10, and TVS-Bi20, representing glass-ceramics containing 0, 10, and 20 wt% of Bi 2 O 3 , respectively. Vickers hardness values are 493, 534, and 564 HV for TVS, TVS-Bi10, and TVS-Bi20, respectively. Also, the values of densities are measured and recorded as 2.61, 2.78, and 3.06 g/cm3 for the TVS, TVS-Bi10, and TVS-Bi20. The values of the mass attenuation coefficients computed using FLUKA simulations and XCOM agree within an error margin of 1%. The values of the estimated photon shielding parameters show that shielding efficiency follows the order TVS < TVS-Bi10 < TVS-Bi20. In addition, the introduction of Bi 2 O 3 has a positive impact to increase the ability of TVS to moderate fast neutrons The total cross-section for thermal neutrons in TVS, TVS-Bi10, and TVS-Bi20 is 1.1294, 1.1198, and 1.1932 cm-1, respectively. The best photon, fast, and thermal neutron absorber is TVS-Bi20 among the TVS-BiX glass-ceramics. The TVS-Bi20 sample can function better than some commercially available glass shields, light and heavy concrete, and other categories of composite materials such as glasses, rocks, and polymers. The TVS-Bi20 is thus recommended as an eco-friendly and efficient radiation shielding material. • Bi 2 O 3 doping powders are synthesised from CRT-screen waste glass. • Radiation shielding properties are studied. • Physical and structure features are investigated. • Nuclear security performance is estimated. • TVS-Bi20 is recommended as an eco-friendly and efficient shielding material. [ABSTRACT FROM AUTHOR]

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 Na 2 CO 3 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 Na 2 CO 3 powder were prepared. The mass attenuation coefficients (μ ρ) of the prepared glasses were obtained using FLUKA simulations for 15 keV–15 MeV photons. The density of CRT, CRT-NC20, and CRT-NC40 were 3.117 g/cm3, 2.987 g/cm3, and 2.894 g/cm3, respectively. The range of μ ρ 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 μ e n ρ 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. Na 2 CO 3 -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. • Radiation protection of recycled CRT/Na 2 CO 3 composites. • Experimental work is carried out. • Monte Carlo simulations are employed. • Na 2 CO 3 -rich glasses had lower buildup factors. • The studied system has a potential use in nuclear and medical applications. [ABSTRACT FROM AUTHOR]