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This study explores the physical, elastic, and radiation shielding properties of SrO–B 2 O 3 -based bioactive glass systems. The interest in BAG has grown significantly in recent years due to their applications in biomedicine, including bone transplants, wound care, and dental treatments. Borate-based glass matrices have emerged as a promising alternative to silicate-based BAG, exhibiting faster conversion to hydroxyapatite (HA) in physiological fluids and promoting cell proliferation for bone healing. The procedure known as melt quenching is used to prepare the glasses. The effects of varying SrO content on the glass properties were evaluated to understand their potential applications in the field of radiation shielding. Experimental results were compared with theoretical models, including the Makishima, Mackenzie, and Rocherulle models, to determine the most appropriate model for analyzing the elastic properties. The Rocherulle model was found to be in better agreement with experimental results. It was observed that the elastic modulus increased with increasing SrO content, suggesting improved mechanical strength due to higher cross-link density in the glass network. Furthermore, the glasses exhibited low Poisson's ratio values, indicating increased resistance to deformation under stress. The Phy-X program was used to determine the mass attenuation coefficient (G MAC), which is the fundamental parameter for evaluating the interaction of radiation with shielding materials. The G MAC results increase as the amount of SrO is increased from 0 to 6 wt%. In addition, the findings demonstrated that the effective atomic number (Z eff) of the produced glasses rise when the amount of SrO is increased from 0 to 6 wt%. The comprehensive analysis of physical, elastic, and radiation shielding properties provides valuable insights into the optimization of glass systems for specific applications in industries that require mechanical strength and radiation protection. • Gamma-ray properties for glass samples have been studied using Monte Carlo method. • Mechanical properties for xPbO–RNa 2 B 4 O 7 –(100-R-x)[CaO–Al 2 O 3 –SiO 2 ] have been measured. • 50PbO–50Na 2 B 4 O 7 –(100-R-x)[CaO–Al 2 O 3 –SiO 2 ] glass sample is the superior gamma-ray shielding. [ABSTRACT FROM AUTHOR]

Novel Glass system with a formula of xBaO.(30− x).Na 2 O.70B 2 O 3 (0 ≤x ≤ 30 mol%) have been prepared and examined. The BNaBa x -glass structure was used to estimate the influence of BaO addition on the density and molar volume. There is a linear increase in density with increasing BaO concentration. The molar volume varies oppositely. Furthermore, the impact of barium oxide on the gamma and neutron radiation shielding capacities of xBaO.(30− x).Na 2 O–70B 2 O 3 glasses have been investigated for radiation shielding applications. The μm: coefficient of mass attenuation for BNaBa-0, BNaBa-5, BNaBa-10, BNaBa-15, BNaBa-20, BNaBa-25, and BNaBa-30 glass samples were simulated using the Monte Carlo simulation FLUKA algorithm, in photon energy ranged 0.015MeV–15MeV, the resulting μ m simulated results were compared with the Phy-X/PSD platform. The T 1/2 : half-value layer, λ: mean free path, Z eff : effective atomic number, EBF: exposure, and EABF: energy absorption buildup factors of the BNaBa x -glass samples have been estimated. The results presented that a BNaBa-30-glass with a 30-mol.% concentration of BaO has the best gamma and neutron shielding capabilities than the other investigated BNaBa x -glass samples. • Gamma and neutron shielding properties of BaO–Na 2 O–B 2 O 3 have been studied. • The results were simulated at 0.015–15 MeV and compared with Phy-X/PSD values. • The BNaBa-30 has the best effectiveness shielding against gamma photons. • The results are useful in radiation protection of applications. [ABSTRACT FROM AUTHOR]

• The melt quench technique was used to fabricate the (25- x)Li2O-75B2O3-xWO3 (x = 1, 3, 5 and 7.5 mol%). • CANBERRA photo multiplier tube base model 80 includes a detector (3 × 3 in.) NaI(Tl) crystal and the multichannel analyzer was used. • Geometric progression (G–P) fitting method has been used to calculate EBF and EABF. • TBL4 glass sample shows the highest μ m , Z eff and Young moduli values and lowest HVL, MFP, EBF, EABF, S fae and R dd values. • TBL4 glass sample could be potentially utilized as an efficient and desirable kind of glass material as gamma shield. The melt quench technique was used to fabricate the (25- x)Li 2 O-75B 2 O 3 - x WO 3 (x = 1, 3, 5 and 7.5 mol%). The mass attenuation coefficients (μ m) of the studied glasses were obtained by using the Gamma (γ) rays spectrometer (CANBERRA photo multiplier tube base model 802) which includes a detector (3 × 3 in.) NaI(Tl) crystal and the multichannel analyzer. The measured values have been compared with XCOM program at selected photon energies. Geometric progression (G–P) fitting method has been used to calculate the exposure build-up factor (EBF) and energy absorption build-up factor (EABF) in the energy range of 0.015–15 MeV. Moreover, EBF and EABF values have been applied to compute the specific fraction of absorbed energy (S fae) and relative dose distribution (R dd). The pulse-echo technique has been used to measure the elastic moduli for glass samples. The TBL4 glass sample shows the highest μ m , effective atomic number (Z eff) and Young moduli values and lowest half value layer (HVL), mean free path (MFP), EBF, EABF, S fae and R dd values. The results of this investigations revealed that the fabricated TBL4 glass sample could be potentially utilized as an efficient and desirable kind of glass material as gamma shield to reduce the deleterious effects of radiation. [ABSTRACT FROM AUTHOR]

The ability of new Co 3 O 4 -doped bismuth borate glasses to block radiation was investigated in this study. The glasses had compositions of 55B 2 O 3 –35Bi 2 O 3 -(10-x)Na 2 O-xCo 3 O 4 (where x = 0, 0.75, 1.5, 2.25, and 3 wt%). The optical properties of the prepared bismuth borate glass doped with Co 3 O 4 ions have been studied. The UV demonstrates that as the Co 3 O 4 substitution ratio was increased, the samples' absorbance increased noticeably. The optical band gap energies decreased with increasing Co 3 O 4 concentration in the case of direct transition and in-direct transition. In addition to the Urbach energy E U values of the prepared glass samples was decreased as the concentration of Co 3 O 4 ions increased. Using the Phy-X/PSD program, an investigation was conducted on the gamma-radiation shielding capabilities of new BBNCo glasses. The G LAC (linear attenuation coefficient) readings for BBNCo increased from a previous value of 0. 7575 cm2/g to a new value of 0. 8589 cm2/g when the energy was 356 keV. In addition, computations have been made to determine the removal cross-sections of fast neutrons and the neutron half value layer (N HVL). The addition of Co 3 O 4 seems to increase the efficiency of bismuth borate glass in deflecting gamma and neutron radiation, as shown by the findings. • Co 3 O 4 -doped bismuth borate glasses shield radiation effectively. • Co 3 O 4 concentration impacts optical properties of the glass. • Higher Co 3 O 4 levels increase glass's UV absorption. • Gamma and neutron shielding enhanced by Co 3 O 4 addition. • Co 3 O 4 doping improves performance and durability of glasses. [ABSTRACT FROM AUTHOR]

Glass samples with the chemical formula x CKD—(100 − x) (5Na 2 O–65 B 2 O 3 –9 Bi 2 O 3 –21PbO), (0 ⩽ x ⩽ 32 mol%) were prepared. The density and the ultrasonic estimations of the investigated glasses were analyzed at room temperature before and after the impact of two dosages of gamma irradiation to study the effect of both CKD and gamma radiation. It was found that the density, and the ultrasonic parameters are sensitive to the variety of the content of CKD and the effect of γ-radiation. Replacement of oxides with higher atomic weights such as Bi 2 O 3 and PbO by CKD decreases the density. Analysis of the behavior of the ultrasonic parameters demonstrates that creation of CaO 6 and SiO 4 on one hand and an alternate transformation between BO 4 and BO 3 structural units, on the other hand, affect the increase of the ultrasonic velocities and the elastic moduli. Moreover, the density and the ultrasonic parameters decrease somewhat with the increase of the doses of γ-irradiation. The variations of the previous physical parameters can be referred to the creation of radiation imperfections, which occupied the voids inside the glass structure. [ABSTRACT FROM AUTHOR]

The low cost and high efficient radiation shielding materials are necessary to protect the human being from the exceedingly used harmful nuclear radiations. The cement kiln dust (CKD) is the largest waste stream from cement plants that harm the environment. In this study, new glasses containing moderate contents of CKD for radiation shielding had been synthesized by the melt quenching technique. The synthesized glasses had the chemical formula (25−x)PbO–32CKD–40B 2 O 3 –3BaO– xBi 2 O 3 (0 ≤ x ≤ 25 mol%). NaI (Tl) scintillation detector and pulse-echo techniques were used to investigate the radiation shielding and the mechanical features of the investigated samples. The mass attenuation coefficient (μ m), half-value layer (HVL), tenth value layer (TVL), mean free path (mfp), radiation protection efficiency (RPE), effective atomic number (Z eff) and effective electron density (N el) parameters for glass samples have been determined experimentally. The G-P fitting method was used to calculate the exposure (EBF) and energy absorption buildup factor (EABF) for the prepared glass samples in the photon energy range of 0.015–15 MeV up to 40 mfp. The specific absorbed fraction of the energy (SAFE), the relative dose distribution (RDD) and the neutron shielding parameters have been computed. Moreover, the elastic moduli of the investigated glasses were determined by considering the measured values of the ultrasonic velocities at 5 MHz and the density. The investigated glasses are considered as a promising candidate for radiation application. • Effect of moderate contenets of CKD. • Adding Bi 2 O 3 and BaO cause to increase the radiation shielding parameters. • Adding Bi2O3 causes to increase the density and the elastic moduli. • The results showed good agreement between experimental and theoretical values. [ABSTRACT FROM AUTHOR]