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This paper investigates the optical properties and radiation shielding performance of borosilicate glasses containing chromium trioxide (CrO3) and strontium titanium oxide (SrTiO3). The optical characteristics, including refractive index, absorption coefficient, and transmission behaviour, were thoroughly analysed to gain insights into the transparency and light-carrying capabilities of the glasses. Additionally, the radiation shielding parameters were obtained by utilizing both FLUKA simulation and the XCOM program. The obtained radiation shielding data were then compared and discussed to assess the effectiveness of the glass compositions as shielding materials against ionizing radiation. The results provide a comprehensive understanding of the optical properties and radiation shielding capabilities of the studied glasses, contributing to the development of novel and efficient materials for radiation protection in various applications, including nuclear medicine, industrial radiography, and space exploration. The findings presented in this study offer valuable information for the design and optimization of borosilicate glasses containing CrO3 and SrTiO3 for effective radiation shielding in neutron-rich environments. [ABSTRACT FROM AUTHOR]

This paper investigates the optical properties and radiation shielding performance of borosilicate glasses containing chromium trioxide (CrO3) and strontium titanium oxide (SrTiO3). The optical characteristics, including refractive index, absorption coefficient, and transmission behaviour, were thoroughly analysed to gain insights into the transparency and light-carrying capabilities of the glasses. Additionally, the radiation shielding parameters were obtained by utilizing both FLUKA simulation and the XCOM program. The obtained radiation shielding data were then compared and discussed to assess the effectiveness of the glass compositions as shielding materials against ionizing radiation. The results provide a comprehensive understanding of the optical properties and radiation shielding capabilities of the studied glasses, contributing to the development of novel and efficient materials for radiation protection in various applications, including nuclear medicine, industrial radiography, and space exploration. The findings presented in this study offer valuable information for the design and optimization of borosilicate glasses containing CrO3 and SrTiO3 for effective radiation shielding in neutron-rich environments. [ABSTRACT FROM AUTHOR]

This study experimentally presents the synthesis and characterisation of a new transparent Eu-doped tellurite matrix glassy composite with the view of predicting its UV and radiation sensing applications. This glassy composite, described by 50TeO 2 –15Na 2 O – 15ZnO – (20-x)PbO – xEu 2 O 3 for x = 0 (TPEu-0), 1 (TPEu-1), 2 (TPEu-2), and 3 (TPEu-3) mol%, was prepared by the well-known melting-and- quenching technique. The glassy nature of the prepared samples was verified by the X-ray diffraction (XED) technique, and the density of the glasses was measured by the Archimedes method. The glasses' optical features were determined from optical transmission and absorption spectra. In addition, the gamma radiation sensing and shielding prowess of the TPEu-X samples was determined from Monte Carlo simulation data using FLUKA code and direct calculations from the NISTXCOM database. The response of the glasses under UV-excitation was also analysed. The melting point and density of the glasses increased as the glasses was enriched with Eu 2 O 3. The density of TPEu-X increased from 5.51 to 5.58 while the melting point grew from 750 °C to 1100 °C Eu 2 O 3 concentration grew from 0 to 3 mol%. The increase in the concentration of Eu 2 O 3 activated crystallization in the glass system. TPEu-1 has the highest optical bandgap energy (3.0 eV) and the lowest refractive index (2.39) among the TPEu-X glasses. The Eu 2 O 3 content of the glasses affected their responses and appearance under UV light. Generally, the glass with the lowest Eu 2 O 3 content possessed the least capacity to shield gamma radiation. The prepared TPEu-3 glass displayed the ability to displace many conventional and non-traditional shields in design of efficient radiation protection systems. [ABSTRACT FROM AUTHOR]

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]

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]