Gamma-ray Shielding Parameters Research Articles

Structural, elastic and gamma-ray attenuation properties of potassium borate glasses doped with BaO, Bi2O3, or Pb3O4: A comparative assessment

This study investigates the effect of substituting boron oxide (B2O3) with heavy metal oxides (HEMOs) on the structural, mechanical, and gamma-ray shielding properties of potassium borate (KB) glass systems. The glass compositions analyzed include 80B2O3–20K2O and 65B2O3–20K2O-15HEMO (where, HEMO = BaO, Bi2O3, or Pb3O4). All samples were prepared using the melt-quenching method, and their amorphous nature was confirmed through X-ray diffraction (XRD). Fourier-transform infrared spectroscopy (FTIR) had revealed BO3, BO4, and BiO6 groups beside the B–O–B linkages. The density increased with the addition of HEMOs, following the order: Pb3O4 (KB4) > Bi2O3 (KB3) > BaO (KB2) > and pure KB (KB1). This trend was also observed in the molar volume (Vₘ) and oxygen molar volume (Vₒ), while the oxygen packing density (Pρ) decreased. Mechanical properties assessed using the Makishima-Mackenzie model indicated that KB3 exhibited the highest elastic modulus (Yₘ) and Poisson's ratio (μ). The microhardness (Hₘ) followed the sequence KB2 > KB3 > KB4 > KB1, attributed to the higher bonding energy in KB2. Gamma-ray shielding parameters, including mass attenuation coefficients (MAC), were calculated using Phy-X and XCOM software for photon energies between 0.2835 MeV and 1.333 MeV. KB4 (Pb3O4) showed superior shielding performance with the highest linear attenuation coefficient (LAC) and the lowest half-value layer (HVL) and mean free path (MFP). Despite KB4's high density, KB3 (Bi2O3) is suggested as a more suitable candidate for radiation shielding applications due to its balanced combination of mechanical strength and γ-ray attenuation efficiency.

Production and evaluation of the polyester composites containing pyrite and niobium diboride for radiation protection

The presented study focused on investigating the radiation shielding properties of polyester/pyrite/niobium diboride (FeSNbB) composites. Various gamma-ray shielding parameters were evaluated with help of a HPGe detector system. Theoretical and simulation results are further evaluated by WinXCOM, GEANT4 and FLUKA codes, and the obtained results are compared with experimental values in the energy region 59.5 keV–1332.5 keV. The prepared samples are additionally evaluated using kerma relative to air values and Exposure build-up factors. Then, for the evaluation of neutron radiation shielding, effective removal cross sections for fast neutrons were determined for FeSNbB composites. Electron attenuation efficiency (AE%) for the produced composites was assessed across the energy spectrum of 4 MeV–18 MeV, utilizing experimental data from a Linac machine and theoretical predictions from Eclipse TPS. The results were found to be compatible with each other. FeSNbB50 has the best shielding properties among the studied composites.

Investigation of structural, optical characteristics of Gd3+ doped phosphate glass for radiation shielding applications

Gadolinium doped phosphate glass was created with a composition of 70 P2O5 + 5Al2O3 + 5 Ba2CO3 + 9 KF2 + 5 MnO2 + 5 SnO+1 Gd2O3 by using the melt-quenching process. The prepared glass sample’s amorphous nature was confirmed by the X-ray diffraction analysis. FT-IR examination confirms the presence of phosphate functional groups. Glass’s optical band gap was found to be 3.5 eV using Tauc’s plot method. The photoluminescence analysis indicates that the emission band at around 311 nm. The Commission International de I’Eclairage (CIE) was employed. It was identified that the computed chromaticity coordinate values (x = 0.3164 and y = 0.3371) were situated in the summer sunlight zone, close to the white light region. The attenuation capabilities of the gadolinium-doped phosphate glass sample were validated by the gamma ray shielding parameters. The mass attenuation coefficient and Mean free path of the prepared glass were fund to be 4.41 × 105 cm2/g at 0.015 MeV and 12.4 cm at 15 MeV respectively. In terms of infiltration deepness up to 40 MFP, the energy-related energy buildup factor (EBF) and energy absorption buildup factor (EABF) of glasses were calculated using the five (a, b, c, d, and Xk) parameters of the G-P fitting scheme. All of the results show that the synthetic glass can be used as shielding materials against gamma radiation.

Evaluation of Some Heavyweight Minerals as Sustainable Neutron and Gamma-Ray Attenuating Materials: Comprehensive Theoretical and Simulation Investigations

AbstractThis study comprehensively evaluates the radiation attenuation efficiencies of hematite and barite, commonly used materials in radiation shielding, using theoretical and simulation investigations. The MCNP-5 code was used to obtain the linear attenuation coefficient (LAC) within the energy range of 0.015–15 MeV, with validation by the XCOM program. Based on these LAC values, various gamma-ray shielding parameters were determined: mass attenuation coefficient, half-value layer, radiation protection capacity, mean free path, transmission factor, and equivalent thickness to lead (ETPb). Additionally, effective atomic number (Zeff) and electron density (Neff) were calculated, including both single-energy and energy-dependent forms for photon absorption and interaction. Furthermore, MCNP-5 simulations and NGCal program calculations were used to assess thermal neutron attenuation, while the NXcom program determined fast neutron behavior. This analysis revealed superior γ-ray shielding for barite compared to hematite. Similarly, the NXcom program indicated better fast neutron shielding for barite. However, interestingly, simulations validated a 210% higher effectiveness in thermal neutron attenuation for hematite. Finally, comparing the studied materials with other shielding materials demonstrated promising potential as environmentally friendly alternatives for effective shielding against various radiation types.

Gamma-ray interaction studies of concrete with waste glass fillers.

In the present work, the efficacy of waste glass as fillers in concrete for gamma-ray shielding has been studied. Glass fillers of 0, 15, 30, 45, and 60% concentrations have been incorporated into the concrete mixture. The attenuation measurements were performed using gamma spectrometer with NaI(Tl) detector at 511, 662, 1173, and 1332keV gamma energies. Gamma-ray shielding parameters, such as the mass attenuation coefficient (μ/ρ), are determined for all filler concentrations. The mass attenuation coefficient of the prepared samples was found to be varied from 0.081 to 0.088, 0.071 to 0.088, 0.05 to 0.058, and 0.05 to 0.055 (cm2 per g) for 511, 662, 1173, and 1332keV gamma energies, respectively. It was observed that experimentally determined (μ/ρ) values were in very good agreement with theoretical values calculated from EDAX data. Furthermore, it was observed that (μ/ρ) showed an increasing trend with an increase in filler concentration, which is attributed to the increase in the shielding property of the material. Therefore, the glass-concrete composite can be accustomed to reduce the intensity of gamma radiation.

Investigation the Gamma Ray Shielding Parameters for Portland Cement Doped with Several Metal Oxides

In this research, gamma ray photons emitted from radioactive sources (Cs-137, Ra-226) with energies (186, 242, 295, 352, 609, 662, 1120, 1765) keV, respectively, to study some parameters, Such as the linear attenuation coefficient ( , mass attenuation coefficient ( for shield made of composite materials consisting of cement as the base material reinforced with different materials (magnesium oxide MgO , tungsten oxide WO3) nanoparticles with different reinforcement ratios (10, 30, 50) % and thickness (0.5) cm to protect against radiation. For this purpose, a sodium iodide detector activated with thallium with dimensions ( was used with an integrated measuring system, to determine the suitability of these shields for use in the field of gamma ray protection. The results showed that the values ​​of these parameters are affected by changing the reinforcement ratios and the gamma ray energy. It was found that when increasing the reinforcement ratio of the shield led to an increase in the linear and mass attenuation coefficient, and in contrast, a decrease in the values ​​of each occurs when the gamma ray energy of the used radioactive source is increased, especially at a concentration of 50 % and at energy (1765) Kev.

Investigation of natural radionuclides and radiation shielding potential of some commonly used building materials in Northwestern Nigeria

This study assessed the gamma-ray shielding potential of clay, sand, gypsum and kaolin commonly used as a building material in Northwestern, Nigeria. The radiological status of the samples was first evaluated by determining the activity concentrations of 238U, 232Th and 40K using NaI (Tl) detector after which elemental composition and mass density were determined using Neutron Activation Analytical Technique. After which the mass attenuation coefficients (MAC), linear attenuation coefficients (LAC), half value layer (HVL), tenth value layer (TVL), and effective atomic number (Zeff) were determined experimentally and theoretically using standard point sources of 137Cs and 60Co photon peaks (0.662 and 1.332, 1.173) MeV and Py-MLBUF software. The activity concentrations were found to range from 51 to 59 Bq kg−1 with a mean value of 59 Bq kg−1 for 238U, 24 to 27 Bq kg−1 with a mean value of 29 Bq kg−1 for 232Th, and 219 to 247 Bq kg−1 with a mean value of 247 Bq kg−1 for 40K which were about within the world recommended values of 33, 45 and 420 Bq kg−1 respectively. The results of the elemental compositions show that Si, Al, K, Fe, and Ba in clay and sand samples have concentrations in the range of 36.83–78.48%, 1.92–26.05%, 6.33–21.96%, 2.39–19.09%, and 0.09–1.44%, respectively, while in kaolin and gypsum, results revealed that Si, Al, K, Fe, and Ca range between 0.34 and 65.52%, 1.14–35.82%, 0.00–12.12%, 0.00–5.77%, and 0.00–96.6%, respectively. However, the concentrations of other elements such as Mg, Ti, Mn, Zn, Na, and Ba varied significantly with the samples. The results showed that clay has an average density of 1.96 g/cm3, sand has 2.32 g/cm3, kaolin has 2.63 g/cm3, and gypsum has the highest density with a value of 2.66 g/cm3 compared to other samples. During the measurements, a thallium-activated sodium-iodide NaI (TI) detector was used. A narrow beam transmission geometry condition was adopted for the measurements to ensure minimal scattered radiation. Absorption and attenuation of gamma beams as a function of sample thickness against gamma energy generally exhibit an increasing gamma ray behaviour as the sample thickness increases from 1 to 3 cm. The results showed that the gypsum, kaolin, sand, and clay were capable of attenuating 63.5%, 61.5%, 58.4%, and 44.2 of gamma-ray photons of energy 0.662 MeV at 3 cm thickness %, respectively, and 40.6%, 32.9%, 30.6%, and 27.3% of gamma energy 1.332 MeV at 3 cm thickness, respectively. The results showed that MAC, LAC, and Zeff of all the samples decreased with an increase in photon energy, while those of HVL and TVL increased. The experimental results for all the gamma-ray shielding parameters were found to be in good agreement with the theoretical values obtained using Py-MLBUF. The results have shown that all the samples have similar photon attenuation behaviours; however, gypsum has the best shielding potential than kaolin and this is attributed due to its highest density value.

Sm3+ doping-adjusted mechanical, dielectric, and radiation shielding properties of cobalt copper nanoferrites

The scarcity of research on the shielding properties of spinel ferrites underscores the necessity for more rigorous investigations. Consequently, this study introduces a facile synthesis method for Co, Cu, and Sm spinel nanoferrites (referred to as CCS nanoferrites) using the citrate combustion technique. The investigation focuses on their mechanical, dielectric, and gamma-ray shielding parameters. Gamma-ray shielding features are obtained theoretically via the Phy-X database. The particle size, nature, and distribution of the present CCS nanoferrites were analyzed using HR-TEM microscopy. HR-TEM results reveal both the spherical shapes and the aggregation of nanoparticles. These observations can be attributed to the interplay of high surface energy and magnetic interactions among the components of the CCS nanoferrites. The Co0.5Cu0.5Sm0.15Fe1.85O4 nanoferrite exhibits an optimal dielectric constant value of 4587, with an enhanced ratio of 1618% compared to the pristine CCS0 sample. Additionally, it demonstrates an optimal conductivity of 38.59 μ (Ω·m)−1, with an enhanced ratio of 1105%. Furthermore, the loss is reduced to 2.65, showing an improvement ratio of 54% compared to the pristine nanoferrite at room temperature and 50 Hz. Moreover, the longitudinal modulus, shear modulus, Young's modulus, and bulk modulus of the nanoferrite Co0.5Cu0.5Sm0.15Fe1.85O4 were increased from 1.79 to 4.96 GPa, 0.32–0.93 GPa, 0.88–2.56 GPa, and 1.37–3.73 GPa, respectively, when compared to the pristine sample. The comparative study of half-value layers at 0.662 MeV revealed that CCS nanoferrites exhibit smaller half-value layers than common radiation shielding materials. Additionally, the study highlighted the enhanced radiation shielding performance of the nanoferrites. Concerning the dielectric, mechanical, and ionizing radiation shielding properties of the CCS spinel nanoferrites, the CCS5 (with the highest Sm content) has the optimum ionizing radiation shielding ability with the highest dielectric and mechanical parameters compared to the other samples. The implications of these findings extend to potential applications in biomedicine, radiation protection, and the optimization of electronic devices operating in radiation fields.

Enhancing radiation shielding transmission factors and mechanical Robustness of borosilicate glasses through Bi2O3 modification: A comprehensive study

The mechanical behavior and gamma radiation attenuation features of borosilicate glasses with chemical compositions 16ZnO–8BaO-5.5SiO2-0.5Sb2O3-(70-x)B2O3/xBi2O3 are extensively investigated. Makishima-Mackenzie principle, Monte Carlo code, and Phy-X/PSD software are utilized in terms of determining these properties. Our results showed that the total packing density (Vt) decreased from 0.634851 to 0.571458, while the total dissociation energy increased from 26.612 (kJ/cm3) to 29.652 (kJ/cm3) for S1-glass (with 10 mol% of Bi2O3) and S5-glass (with 30 mol% Bi2O3). All elastic moduli are enhanced by increasing the Bi2O3 additive in the investigated glasses. Poisson's ratio was decreased from 0.281226 for S1-glass to 0.256957 for S5-glass. In terms of gamma-ray shielding parameters; linear (μ) and mass attenuation (μm) coefficients for the rich glass sample with B2O3 (S5) possess the highest values among all investigated (S1–S5) samples. The glass sample S5 is reported with the lowest values of tenth (TVL) and half (HVL) value layers among all studied glasses. In addition, the exposure (EBF) and energy absorption (EABF) bulidup factors were decreased with increasing the amount of Bi2O3 reinforcement for mean free path values from 0.5 to 40 mfp. The lowest possible levels of attenuation (minimum transmission) were measured at a thickness of 3 cm for all of the glass samples.

Synthesis structural optical and mechanical properties of Nb3⁺ doped Zinc Borophosphate glass for radiation shielding application

Abstract The Nb3⁺ doped Zinc Borophosphate glass (30B2O3 +35P2O5+5TiO2+10ZnO+9LiCO3+10 BaCO3+1NbO2) has been synthesized successfully using melt-quenching method. The powder X-ray diffraction (XRD) analysis was used to find the glass nature of Nb3⁺ doped Zinc Borophosphate glass. The functional group of Nb3⁺ doped Zinc Borophosphate glass was recognized using Fourier-transform infrared spectroscopy (FTIR) analyses. Linear optical properties of the Nb3⁺ doped Zinc Borophosphate glass were studied using UV–vis–NIR spectrum in the room temperature. Mechanical behaviour of Nb3⁺ doped Zinc Borophosphate glass was examined through Vicker’s hardness method. The mechanical properties of Nb3⁺ doped Zinc Borophosphate glass was examined with various loads. The emission transitions of Nb3⁺ doped Zinc Borophosphate glass was studied using Photoluminescence analysis. The CIE diagram of the Photoluminescence was examined. Gamma ray shielding parameters such half value layer, mean free path and mass attenuation coefficient of Nb3⁺ doped Zinc Borophosphate glass were studied using Phy-X software.

Electrical and gamma ray shielding properties of phospho-tellurite glasses doped with alkali and transition metal oxides

This article presents investigated results on physical, electrical and gamma radiation shielding properties of glasses of composition, (P2O5)0.25-(TeO2)0.5-x-(Na2O)0.1- (ZnO)0.15-(CoO)x (x= 0.10, 0.15, 0.20, 0.25, 030 and 0.35) were synthesized by melt quenching procedure. After confirming non-crystallinity, density was measured and found it to be decreased with increase of CoO concentration in the range 4.0370 gm/cm3 - 3.5673 gm/cm3. Molar volume, mean distance between TMIs, small polaron radius, oxygen packing density and field strength were estimated. Conductivity was measured in the temperature range 303K -663K. High temperature conductivity is found to be varied as per Mott’s (SPH) model. High temperature activation energy is found to be increased with CoO content. Low temperature conductivity variation has been analyzed using Mott’s (VRH) model. Gamma ray shielding parameters were evaluated using Phy-X/PSD software for the energy range 0.005 MeV-15 MeV. The mass and linear attenuation coefficients were found to decrease with CoO content and photon energy. Half and tenth value layers increased with increase of mole fractions of CoO. All the observed shielding parameters are superior to those reported previously for other glasses. The glass with x=0.10 is best suited for the utility of gamma shielding at low energy.

Exploring a monotonically non-decreasing behavioral function on shielding properties and transmission factors in borosilicate glasses through heavy metal oxide reinforcement

In this study, the gamma-ray attenuation properties and transmission factors of different types of glasses formed in the (B2O3)x[(ZnO)0.60-(SiO2)0.40]1-x system as a function of increasing heavy metal oxide ratio were investigated. For transmission factor and absorption coefficient calculations, the general-purpose Monte Carlo code MCNPX (2.7.0) was used. In addition, the Phy-X/PSD code is used to obtain some important gamma-ray shielding parameters. According to the obtained results, increasing the quantity of heavy metal oxide in the glass composition favorably affected the examined parameters and lowered the transmission factor and buildup factor values. Furthermore, it has been observed that parameters such as the absorption coefficient and the effective atomic number increase as a function of increasing heavy metal oxide contribution into glass configuration. The lowest half value layer values are reported for S1 sample. For example, half value layers are reported as 3.313 cm, 3.449 cm, 3.764 cm, 3.625 cm, 3.515 cm for S1, S2, S3, S4, and S5 sample at 1 MeV photon energy, respectively. According to the transmission factor values, S1 is the sample that allows the least transmission of primary photons and demonstrates the highest resistance. It was observed that the minimal exposure build-up factor and energy absorption buildup factor values for the S1 sample at 10 mean free paths. It can be concluded that the heavy metal oxide additive applied to borosilicate glasses creates a non-decreasing functional behavior effect that is monotonic in gamma-ray attenuation parameters.

Gamma ray shielding properties of synthesized lanthanide borides using EGSnrc code

In this study, we have investigated some hexaborides which are synthesized for the purpose of gamma-ray shielding. These materials were synthesized by the method of magnesiothermic reduction process in the open air, and stoichiometric amounts of M2O3, B2O3, and Mg (20% excess) were mixed where MIII is a three oxidation state lanthanide metal (DyIII, PrIII and YbIII) ion. Chemical and physical characteristics of the manufactured samples were determined by X-ray Diffractometry (XRD), Energy Dispersive X-ray Spectroscopy (EDX) and Scanning Electron Microscopy (SEM) analyzes. Gamma-ray shielding parameters were determined by using EGSnrc Monte Carlo (MC) code in 21.0 keV-1.728 MeV photon energy range. The calculated data were compared with the results calculated by Nist's XCOM database. The obtained results by using EGSnrc and XCOM program have shown successful consistency. It was concluded that the manufactured hexaborides have promising gamma shielding properties compared especially to lead and some shielding materials investigated earlier in the literature.

Designing a Lead-free and high-density glass for radiation facilities: Synthesis, physical, optical, structural, and experimental gamma-ray transmission properties of newly designed barium-borosilicate glass sample

We report the design, synthesis, optical, structural, and gamma-ray attenuation properties of a newly developed Lead-free and high-density borosilicate glass sample for its potential applications in medical and industrial radiation facilities. A barium-borosilicate glass sample (BSBaZn) was designed and synthesized using nominal composition of 7B2O3-50SiO2-38ZnO-5BaO. The FTIR spectrum of the BSBaZn is revealed four fundamental regions. These regions are 400–620 cm−1, 620–770 cm−1, 800–1210 cm−1, and 1210–1500 cm−1. Transmittance rate in the wavelength range of 350–1100 nm is reported as 80 %. A high-purity Germanium (HPGe) detector along with an energetic 133Ba radioisotope is also utilized for experimental gamma-ray transmission studies. Various fundamental gamma-ray shielding parameters of BSBaZn are determined and accordingly compared with many other glass shields. MCNPX (version 2.7.0) general purpose Monte Carlo code is utilized for gamma-ray transmission factor (TF) values. The results showed that the synthesized BSBaZn sample has promising structural, optical, and physical properties in addition to promising gamma-ray attenuation properties. The high transparency of BSBaZn along with its high-density may be considered as an important selection criterion for its implementation in protection purposes in medical and industrial radiation facilities, where the source and patients monitoring play a significant role.

Synthesis, optical characteristics, and gamma-ray protection competence evaluation of polyvinyl chloride reinforced basalt nanocomposites

In this study, new PVC (polyvinyl chloride) polymers doped with different contents of basalt nanoparticles have been prepared. The PVC was mixed with concentrations (0, 5, 10, 15, 20, and 50 wt%) of basalt nanoparticles utilizing the casting method. The samples coded as PB0.0, PB5.0, PB10.0, PB15.0, PB20.0, and PB50.0. The density of the casted samples increased from 1.38 to 2.18 g/cm3 with increasing basalt nanoparticle concentrations. Scanning electron microscope (SEM) of the prepared samples showed a good dispersion with small basalt concentrations in the while some agglomerations were found with the highest basalt concentrations in the mixture. The values of the direct optical energy gap varied from 3.0 to 3.5 eV, while the refractive index values changed from 2.39 to 2.27. The gamma-ray shielding parameters were evaluated using the Phy-X/PSD software program as well as the MCNP – code. The most critical results showed that the linear-attenuation coefficient (μ) increased from 14.421 to 23.862 cm−1 (at 0.015 MeV), and from 0.030 to 0.048 cm−1 (at 15 MeV) for PB0.0 and PB50.0 samples, respectively. Moreover, the evaluation of other gamma - ray shielding characteristics showed an enhancement with the addition of the basalt nanoparticles. Besides, neutron cross section was also calculated, and results revealed that PB0.0 is 0.086 cm−1 and PB50.0 is 0.104 cm−1. Finally, the obtained results concluded that the γ -ray, and neutron shielding capacities were enhanced with the increase in basalt nanocomposites amount in the fabricated composites.

Impact of BaTiO3 on the structural, optical, and nuclear radiation shielding parameters of poly(methyl methacrylate) nanocomposites as transparent shielding material

Six weight percentages (0, 2, 5, 10, 15, and 20 wt(%)) of barium titanate BaTiO3 were doped as a nanoparticle in poly(methyl methacrylate) PMMA and their optical and nuclear radiation shielding properties were investigated. The XRD patterns, FTIR spectra and SEM images confirmed that the nanocomposite films were successfully prepared. The pure PMMA sample demonstrated a significant degree of transparency, approximately 90%. The inclusion of BaTiO3 resulted in a significant reduction in the optical bandgap while maintaining a moderate transmittance level of approximately 40% at a concentration of 10 wt (%). The direct and indirect band gap energy of PMMA were decreased from 4.81 eV to 4.62 eV–1.64 eV and 1.09 eV, respectively, after doping with 20 wt(%) BaTiO3 nanoparticles. The refractive index of the investigated samples was determined using various approaches and seen to increase after nanofiller addition. Seven energy lines, from Eu-152, Cs-137, Na-22 and Ra-226 radioactive gamma ray sources, were used to deduce the gamma ray shielding parameters of the prepared samples. Also, three neutron energy ranges were used to measure the macroscopic cross-sections for the investigated samples. The results showed good agreement between measured values of mass attenuation coefficients and those calculated by WinXCOM computer program. Furthermore, the optimal weight percentage of BaTiO3 in PMMA for attenuation of all examined gamma ray energies was 10 wt (%), whereas it was 15 wt (%) for the investigated three neutron energy ranges. In other words, a novel flexible, transparent and non-toxic polymer nanocomposite shielding material is presented and the samples containing 10–15 wt(%), demonstrates improved radiation attenuation.

Investigation of Elastic Moduli and Gamma-Ray Shielding Parameters of P2O5-SiO2-BaO Glasses Doped with Varying WO3

Investigation of Elastic Moduli and Gamma-Ray Shielding Parameters of P2O5-SiO2-BaO Glasses Doped with Varying WO3

Effect of Bi2O3 on the physical, structural and gamma ray shielding properties of phosphate glasses inside the ternary P2O5-SrO-Bi2O3 system

Strontium phosphate glasses containing bismuth oxide were prepared using conventional melt-quenching technique. X-ray diffraction and differential scanning calorimetry (DSC) analysis suggests that stable ternary glasses of composition 70 P2O5-(30-x)SrO-xBi2O3 can be obtained for x = 5–25 mol%. This study examines such physical properties as the density, molar volume (Vm), glass transition temperature (Tg), and structural properties in the interest of explaining the effect on these glasses of Bi-Sr substitution. An almost linear increase in the density when the concentration of bismuth increases between x = 5 and x = 10 mol% followed by monotonic decreasing is noted. However, the calculated molar volume (Vm) behaves in exactly the opposite way. DSC curves showed that the glass transition temperature (Tg) decreases by 555 °C down to 490 °C as the concentration of Bi2O3 increases, due to the increase in the number of bridging oxygens. Structural investigations performed using IR spectroscopy revealed that the structure of the phosphate network contains predominately meta-phosphate (Q2) units, with contributions from pyrophosphate (Q1) and orthophosphate (Q0). The infrared spectra also revealed depolymerization of the phosphate chains in the glass system, with increased Bi2O3 concentration and the formation of P–O–Bi bonds. The study of the gamma ray shielding parameters showed that the prepared glasses can be used for shielding radiation applications.

Investigation of gamma shielding parameters of some silica borotellurite glasses with different amount of Bi[formula omitted]O[formula omitted] at energies between 10 and 150 keV

A newly developed computer code GRASP to calculate some gamma ray shielding parameters has been introduced. Mass attenuation coefficients, effective atomic numbers, half-value layers and mean free paths of TeO2-B2O3-SiO2 glasses with different amounts of Bi2O3 have been studied in detail for photon energies between 10 and 150 keV. The mass attenuation coefficients determined with GRASP are in good agreement with the ones calculated with XCOM. GRASP can be used to determine various shielding parameters as an alternative to the existing programs. All the parameters calculated with GRASP suggest that gamma shielding capability of the glasses studied gets better as the amount of Bi2O3 in the glass increases.

Investigation of the Influence of TeO2 on the Elastic and Radiation Shielding Capabilities of Phospho-Tellurite Glasses Doped With Sm2O3

The impact of TeO2 on the elastic and radiation shielding properties of phospho-tellurite glasses doped with varying amounts of Sm2O3 has been studied. The elastic properties, such as packing factor, packing density, Young’s modulus, bulk modulus, shear modulus, and Poisson’s ratio, were determined by using the Makashima-Mackenzie and Rocherulle models. The gamma-ray shielding parameters, such as mass attenuation coefficient, half-value layer, tenth-value layer, effective atomic number, equivalent atomic number, exposure buildup factor, and energy absorption buildup factor, were calculated using Phy-X/PSD software in the energy range from 0.015 to 15 MeV at penetration depths up to 40 mean free paths for selected glasses. The fast neutron removal cross section was also determined using Phy-X/PSD software. The results show that the mass attenuation coefficient decreases with increasing photon energy but is not influenced by the addition of Sm2O3. The exposure buildup factor values and energy absorption buildup factors have lower values in the low- and high-energy regions and higher values in the intermediate energy region. The 1.5 mol % concentration of Sm2O3 in the selected glass shows higher exposure buildup factor and energy absorption buildup factor values in the intermediate energy region. Among the selected glasses, PZBTS1.5 has the highest value of fast neutron removal cross sections. The high density, high effective atomic number, and transparency to visible light of these materials indicate that they can be used as shielding materials in nuclear reactors and nuclear technology.