Gamma, Fast Neutron, Proton, and Alpha Shielding Properties of Borate Glasses: A Closer Look on Lead (II) Oxide and Bismuth (III) Oxide Reinforcement

: The purpose of this research was to investigate the shielding characteristics of high-amount heavy metal oxide and Eu 3+ -activated borate glasses based on 10La 2 O 3 –50HMO–(40–x) B 2 O 3 –xEu 2 O 3 (x = 0, 0.5, 1, 2, and HMO = PbO, Bi 2 O 3 ). Critical gamma radiation attenuation characteristics, particularly mass attenuation coefﬁcients of investigated heavy metal oxide glass samples, were determined using Monte Carlo simulations and the Phy-x/PSD software. Following that, we looked at the half-value layer, mean free path, effective atomic number, and build-up factors across a broad energy range (0.015–15 MeV). According to the study’s results, the addition of Eu 2 O 3 enhanced the mass attenuation coefﬁcient and effective atomic number, while reducing the half-value layer, mean free path, and accumulation factors. In terms of gamma radiation attenuation, the LBi50BEu glass system surpassed the LPb50BEu glass system in terms of overall shielding properties against nuclear radiation. Additionally, the heavy metal oxide glass’ efﬁcacy as a neutron shield was determined using fast neutron removal cross-sections ( Σ R ). LBi50BEu2 glass was shown to be more effective in preventing the penetration of charged particle radiation.


Introduction
With today's extensive use of radiation sources and radioactive materials, it is extremely essential to use radiation sources cautiously and safely. Against gamma radiation, the most utilized shielding materials are lead (Pb) and lead-equivalent compounds. However, Pb's negative impacts on human health and the environment pose a serious concern. Subsequently, it has some disadvantageous material properties, such as optical non-transparency, low durability, high cost, and material durability in terms of shielding applications [1]. Another material used to attenuate gamma radiation is concrete. Its most serious shortcomings, however, are that it is exceedingly heavy, pricey, opaque, and cracks when overused [2]. In recent years, researchers have been attempting to investigate the features of eco-friendly, very dense, and chemically homogeneous materials that could be utilized as a replacement for concrete and lead. Corrosion-resistant, biocompatible radiation shielding systems must be created that can be modelled into narrow, compact forms with outstanding structural integrity and endurance. Glass has been proven to be an efficient shielding material due to its transparency to visible light, ease of production, and ease of property change through composition and preparation techniques. Glasses are one of a kind in that they can handle a wide variety of elements. They can act as a shield against hazardous ionizing radiation because of this characteristic. Impurities in the form of metals were incorporated into regular glass to transform it into a radiation shield glass. This doping, especially with heavy metal oxides (Ba, Bi, Pb), enhances the glass' attenuation properties, making it ideal for shielding applications. Glass formers are oxides that serve as the structural backbone of the glass network and are needed for optimal operation. As potential substitutes, borate glasses and lead-free compounds with adequate chemical resistance, transparency, and radiation protection are being investigated [3]. Borate-based glasses have a higher melting point and resistance to temperature changes than other types of glasses. Because of their high solubility of rare earth ions, ease of mass production, and low cost, bore-based glasses are the greatest choice for developing new optical devices. Borate-based glass systems have good broad-band properties and demonstrate significant increases in luminescence intensity. Doping transition metal and rare earth ions into borate glasses improves optical transmittances, electric conductivities, thermal, and even magnetic characteristics [4][5][6]. Pb-based glasses are particularly fascinating due to their strong electrical conductivity, stability, and wide glass-forming range. Strong UV transmittances, low melting and glass transition temperatures, and great thermal stability are all advantages of Pb-based glasses [7,8]. According to a study conducted by Tekin et al. [9], phosphate-based glasses are ideal for the fabrication of optical fibres and shielding material for radiation detection, among many other applications. Agar et al. [10] conducted another significant study which revealed that doping glasses with erbium (Er) leads to an increase in the mass attenuation coefficient and a decrease in build-up factors and half-value layer. Subsequently, glasses doped with Er possess significant radiation-shielding properties. The goal of this novel study is to determine the nuclear-radiation-shielding properties of glass samples from the 10La2O3-50HMO-(40-x) B 2 O 3 -xEu 2 O 3 (x = 0, 0.5, 1 and 2 mol percent and HMO = PbO, Bi 2 O 3 ) system in a wide range of energies between 0.015 and 15 MeV using the MCNPX (version 2.7.0) general-purpose Monte Carlo code [11] and Phy-X/PSD [12] software. It also aims to establish the materials' mechanical qualities, as well as their suitability as shielding materials. The results of this study will be useful in the field of glass literature, notably in the field of radiation shielding. Researchers will gain a better understanding of the utility of HMO-doped glasses as nuclear-radiation-shielding materials as a result of the findings of this study.

Studied Radiation Shielding Parameters
Equation (1) describes the photon flux attenuation in narrow photon beam. As indicated in Equation (1), a connection exists between the radiation intensity (I) and the absorbent glass material's thickness (t), as well as the radiation intensity (I o ) prior to contacting the substance [14]: In Equation (1), µ is the linear attenuation coefficient. The term of mass attenuation coefficient (µ m ) is a measure of how likely incident photons are to interact with matter per unit density. The formula shown in Equation (2) is used to compute it: where (µ m ) is the mass attenuation coefficient, (w i ) is the weight fraction of the ith constituent element, (µ) is the linear attenuation coefficient, and (ρ) is the density. The mean free path (MFP) is the mean distance travelled by a photon inside a shielding material prior to encountering an interaction. It is calculated using the following Equation (3): The half-value layer (HVL) is the absorber thickness required to reduce the radiation intensity to half of its starting value, as determined by Equation (4): In composite materials, the term "effective atomic number" (Z eff ) cannot be stated as a single number; instead, it varies depending on the material and specific characteristics of the interacting radiation, and it provides information about the material. The direct method was used to compute the Z eff values of the samples in this investigation: In Equation (5), f i is fraction by mole, A i is atomic weight, and Z j is atomic number of ith constituent element. When developing gamma radiation shielding, build-up factor (BUF) considerations are crucial. The energy absorption build-up factor (EABF) is a measure of the amount of time a material is exposed to air after it has been penetrated by a particle. The exposure build-up factor (EBF) is a measurement of the amount of exposure in air after it has passed through the shielding material. BUFs are often computed using the geometric progression (G-P) fitting technique, which is described in detail below. To begin, the equivalent atomic number (Z eq ) of a particular energy is determined by comparing its (µ m ) Compton/(µ m ) total ratio to the element's convenient ratio. In this study, the Z eq values for the glasses were determined using the interpolation technique. The EBF and EABF values for a single-layered gamma-ray-shielding enclosure (GSE), with an OT of up to 100 mfp and an energy range of 0.015 to 15 MeV, are calculated using the following Equations (6)- (8).
In the above equations: E: Incoming photon energy; X: Penetration depth in millimetres per second; B: Accumulation factor at 1 millimetre per second; K: Photon-dose multiplication factor. The projected range is a critical parameter for analysing the shielding and interaction of nuclear radiation with different objects at different protons and alpha kinetic energies. The predicted range provides an explanation for the mean value of the depth at which alpha and proton particles begin to slow down and come to rest. The stopping power of a vehicle is defined as the quantity of energy lost over a certain distance. The mass stop power of a system is the amount of energy lost per unit of density. For the computation of ion deposition data in ion irradiation materials, the Stopping and Range of Ions in Materials (SRIM) equation was utilized, and Monte Carlo simulations were utilized for the computation of data using the SRIM equation. According to the findings of this study, attenuation characteristics of the glass produced were tested against charged particles, such as alpha and proton, with the results measured in terms of alpha/proton mass stopping power and alpha/proton projected range [15]. The last term to discuss is "effective neutron removal" (R), which refers to the process of removing neutrons from the material in a timely way. Following the definition of the cross-defined (or un-scattered) cross-section definition, the total amount of nuclear energy generated in a fission event from the first (or fast) neutron is equal to the average anticipated quantity of nuclear energy generated in a fission event. Calculating the R values of a material may be accomplished using the following Equation (9): In Equation (9), Σ R/ρ is mass removal cross-section (cm 2 /g), and w i is partial density (g/cm 3 ) of the ith element [16].

Monte Carlo Simulations (MCNPX Version 2.7.0)
The mass attenuation coefficients of the LPbX and LBiX glasses were efficiently estimated using the general-purpose Monte Carlo algorithm MCNPX (version 2.7.0). To begin, input data for MCNPX were created utilizing the basic components as follows: Figure 1a depicts the 3D view of the modelled setup obtained from MCNPX Visual Editor VE VisedX22S. Within a lead (Pb) shield block, a point isotropic gamma-ray source was placed. The glass specimens were then modelled using their elemental compositions (in percent weight) and material densities (in grams per cubic centimetre). The cylindrical form of the glass specimen had a radius of 5 cm and was made of clear glass. As a consequence of this evolution, the borders of cell cards were filled with the material qualities that were required for their construction (i.e., elemental mass fraction and material density). In Figure 1b MCNPX simulation setup for determining the gamma-ray transmission capabilities of lenses, such as LPbX and LBiX (obtained from MCNPX Visual Editor VE VisedX22S). The modelled point isotropic source may alternatively be viewed as an extension of the overall gamma-ray transmission arrangement in Figure 1a, as can be seen in Figure 1b. Listed in Table 1 are the elemental mass fractions of the LPbX and LBiX glasses that were under investigation. MCNPX INPUT file, which was used to define the elemental composition of glass specimens, had a Mn variable, which should be noted. The term of Mn is an integral part of material definition of nth material, along with constituent elements, their atomic numbers, and their elemental mass fractions (wt.%). Using the results of the initial cell description procedure, we were able to determine the importance of photon and electron interactions (IMP: p, e) in the cell. LPbX and LBiX glasses were connected to the opposite side of the detector field (F4 Tally Mesh) for the purpose of counting the attenuated gamma rays that were produced. This kind of tally mesh is helpful for estimating the average photon flux in a point or cell, as well as for other applications. A total of 10 8 particles at different photon energies were collected for each glass sample after each run was repeated (i.e., from 0.015 MeV to 15 MeV). When running all simulations, the MCNPX model exhibited a relative error rate less than 1 percent (%).
(in percent weight) and material densities (in grams per cubic centimetre). The cylindrical form of the glass specimen had a radius of 5 cm and was made of clear glass. As a consequence of this evolution, the borders of cell cards were filled with the material qualities that were required for their construction (i.e., elemental mass fraction and material density). In Figure 1b, one can see a 2D perspective and the dimensions of the proposed MCNPX simulation setup for determining the gamma-ray transmission capabilities of lenses, such as LPbX and LBiX (obtained from MCNPX Visual Editor VE VisedX22S). The modelled point isotropic source may alternatively be viewed as an extension of the overall gamma-ray transmission arrangement in Figure 1a, as can be seen in Figure 1b. Listed in Table 1 are the elemental mass fractions of the LPbX and LBiX glasses that were under investigation. MCNPX INPUT file, which was used to define the elemental composition of glass specimens, had a Mn variable, which should be noted. The term of Mn is an integral part of material definition of n th material, along with constituent elements, their atomic numbers, and their elemental mass fractions (wt.%). Using the results of the initial cell description procedure, we were able to determine the importance of photon and electron interactions (IMP: p, e) in the cell. LPbX and LBiX glasses were connected to the opposite side of the detector field (F4 Tally Mesh) for the purpose of counting the attenuated gamma rays that were produced. This kind of tally mesh is helpful for estimating the average photon flux in a point or cell, as well as for other applications. A total of 10 8 particles at different photon energies were collected for each glass sample after each run was repeated (i.e., from 0.015 MeV to 15 MeV). When running all simulations, the MCNPX model exhibited a relative error rate less than 1 percent (%).

Results and Discussions
In this study, a comprehensive investigation on high-amount heavy metal oxide (HMO)-added and Eu 3+ -activated borate glasses based on 10La2O3-50HMO-(40-x)B2O3-xEu2O3 (x = 0, 0.5, 1 and 2 mol% and HMO = PbO, Bi2O3) system was carried out in terms of their individual and comprehensive gamma-ray and charged particle attenuation competencies. In total, eight different glass samples, encoded LPb50B, LPb50Eu0.5, LPb50BEu, LPb50BEu2, LBi50B, LBi50Eu0.5, LBi50Eu1, and LBi50Eu2, were classified considering HMO type in their structure. Material densities and chemical properties of the aforementioned glasses can be obtained from Table 1. It is clearly seen that material densities of PbO-reinforced borate glasses varied from 5.043 g/cm 3 to 5.393 g/cm 3 , whereas material densities of Bi2O3-reinforced borate glasses varied from 5.940 g/cm 3 to 6.812 g/cm 3 . In the glass structure, (40-x)B2O3-xEu2O3 indicates that, in both glass groups, B2O3 has been replaced with Eu2O3 from 0 to 2 mole%. Therefore, one can say that Bi2O3 contribution (as 50% mole) has increased the material density more than PbO contribution in terms of their

Results and Discussions
In this study, a comprehensive investigation on high-amount heavy metal oxide (HMO)-added and Eu 3+ -activated borate glasses based on 10La 2 O 3 -50HMO-(40-x)B 2 O 3 -xEu 2 O 3 (x = 0, 0.5, 1 and 2 mol% and HMO = PbO, Bi 2 O 3 ) system was carried out in terms of their individual and comprehensive gamma-ray and charged particle attenuation competencies. In total, eight different glass samples, encoded LPb50B, LPb50Eu0.5, LPb50BEu, LPb50BEu2, LBi50B, LBi50Eu0.5, LBi50Eu1, and LBi50Eu2, were classified considering HMO type in their structure. Material densities and chemical properties of the aforementioned glasses can be obtained from Table 1. It is clearly seen that material densities of PbO-reinforced borate glasses varied from 5.043 g/cm 3 to 5.393 g/cm 3 , whereas material densities of Bi 2 O 3 -reinforced borate glasses varied from 5.940 g/cm 3 to 6.812 g/cm 3 . In the glass structure, (40-x)B 2 O 3 -xEu 2 O 3 indicates that, in both glass groups, B 2 O 3 has been replaced with Eu 2 O 3 from 0 to 2 mole%. Therefore, one can say that Bi 2 O 3 contribution (as 50% mole) has increased the material density more than PbO contribution in terms of their HMO structures. To begin, we calculated the mass attenuation coefficients (MAC) of the aforementioned glass samples using the MCNPX code, and then compared them to theoretical findings obtained using the Phy-X/PSD program. In Table 2, the findings of both techniques are listed, together with their respective relative variances. Additionally, Figure 2 illustrates the variation in the MAC values of the investi-gated glasses throughout the energy range 0.015-15 MeV. From Table 2, it is seen that the MAC values of LPb50B and LPb50BEu2 glasses vary between 78.429 cm 2 /g-0.045 cm 2 /g and 79.045 cm 2 /g-0.045 cm 2 /g, while the MAC values for LBi50B and LBi50Eu2 glasses are between 89.281 cm 2 /g-0.048 cm 2 /g and 89.442 cm 2 /g-0.048 cm 2 /g. It is noticed from Figure 2 that the MAC values decrease rapidly at 0.015-0.1 MeV photon energies, and increase suddenly before reaching 0.1 MeV. This rapid drop is due to the impact of photoelectric absorption (PEA) in the low energy region and the changing in cross-section of interaction with 1/E 3.5 in that zone. Besides, a sudden increase occurred around 88.00 keV and 90.52 keV, which are the absorption edges of Pb and Bi heavy elements in two glass systems, since the cross-section of PEA is proportional to Z 4−5 . It is regarded that the reduction in MAC values is slower at medium energies where the Compton scattering (CS) process (Z/E) is powerful. It is remarkable that after 1.022 MeV, where pair production (PP) occurs, the MAC values increased slowly with increasing energy. At high energy levels, most photons are annihilated, and MAC values vary depending on Z 2 . Therefore, the MAC values of glasses containing Bi and Pb elements with high Z at high energies increased. With the addition of Eu 2 O 3 (0, 0.5, 1, 2 mol%), the MAC values are obtained at 0.015 MeV as 78.429 cm 2 /g, 78.586 cm 2 /g, 78.742 cm 2 /g, and 79.045 cm 2 /g and 89.281 cm 2 /g, 89.322 cm 2 /g, 89.362 cm 2 /g, and 89.442 cm 2 /g for LPb50B and LBi50B glass systems, respectively. From this, it can be deduced that the insertion of Eu 2 O 3 increases MAC values in both glass systems, and the higher MAC values are obtained in glasses prepared with Bi 2 O 3 . The material thickness of LPb50BEu and LBi50BEu glasses for 0.015-15 MeV photon energies, which halves the incoming radiation intensity, is presented in Figure 3.   Half-value layers (T1/2) of the LPb50BEu and LBi50BEu glasses are almost zero in the 0.015-0.1 MeV range. After 0.1 MeV, secondary scattering enhances with the effect of CS, while the T1/2 values increase quickly. Beyond 3 MeV, the T1/2 values reduce with the annihilation of photons in the PP process. The densities of LPb50BEu and LBi50BEu glasses are reduced in the range of 5.39-5.04 g/cm 3 and 6.81-5.94 g/cm 3 with the addition of Eu2O3. Therefore, it is seen that the T1/2 values increase with the insertion of Eu2O3. The maximum T1/2 values for LPb50BEu and LBi50BEu glasses were obtained as 3.60 cm and 2.95 cm, respectively. These results are quite satisfactory for a good shield material for gamma rays. Moreover, the mean free path values (λ) of proposed glasses in comparison with some commercial SCHOTT [17] glasses, RS-253-G18, RS-360, RS-520, and concrete types, barite, ferrite, chromite [18], are given in Figure 4. Half-value layers (T 1/2 ) of the LPb50BEu and LBi50BEu glasses are almost zero in the 0.015-0.1 MeV range. After 0.1 MeV, secondary scattering enhances with the effect of CS, while the T 1/2 values increase quickly. Beyond 3 MeV, the T 1/2 values reduce with the annihilation of photons in the PP process. The densities of LPb50BEu and LBi50BEu glasses are reduced in the range of 5.39-5.04 g/cm 3 and 6.81-5.94 g/cm 3 with the addition of Eu 2 O 3 . Therefore, it is seen that the T 1/2 values increase with the insertion of Eu 2 O 3 . The maximum T 1/2 values for LPb50BEu and LBi50BEu glasses were obtained as 3.60 cm and 2.95 cm, respectively. These results are quite satisfactory for a good shield material for gamma rays. Moreover, the mean free path values (λ) of proposed glasses in comparison with some commercial SCHOTT [17] glasses, RS-253-G18, RS-360, RS-520, and concrete types, barite, ferrite, chromite [18], are given in Figure 4. Therefore, it is seen that the T1/2 values increase with the insertion of Eu2O3. The maximum T1/2 values for LPb50BEu and LBi50BEu glasses were obtained as 3.60 cm and 2.95 cm, respectively. These results are quite satisfactory for a good shield material for gamma rays. Moreover, the mean free path values (λ) of proposed glasses in comparison with some commercial SCHOTT [17] glasses, RS-253-G18, RS-360, RS-520, and concrete types, barite, ferrite, chromite [18], are given in Figure 4.  The λ values of LPb50BEu and LBi50BEu glasses are thinner than other shielding materials. The LBi50BEu2 glass had the smallest λ values, while the RS-213-G18 glass presented the largest MFP values, as seen in Figure 5. In order to express a composite material with a single atomic number, an effective atomic number (Z eff ) is needed, which shows the shielding capacity of the shielding material well [19]. While the addition of Eu 2 O 3 in the high energy region increased the Z eff values of the glasses, the Z eff values declined at medium and low energy levels. It is noted from Figure 6 that the Z eff values of LBi50BEu glasses prepared with Bi 2 O 3 are higher than LPb50BEu glasses. Perfect geometry is not possible in real radiation applications. For this reason, the correction factor B (build-up factor) is needed to account for scattering in the material and in the air in the Lambert-Beer law [20]. Energy absorption and exposure build-up factors (EABF and EBF) for L(Pb/Bi)50BEu glasses were generated using Phy-X/PSD software in photon energies of 0.015-15 MeV for several λ values. of LBi50BEu glasses prepared with Bi2O3 are higher than LPb50BEu glasses. Perfect geometry is not possible in real radiation applications. For this reason, the correction factor B (build-up factor) is needed to account for scattering in the material and in the air in the Lambert-Beer law [20]. Energy absorption and exposure build-up factors (EABF and EBF) for L(Pb/Bi)50BEu glasses were generated using Phy-X/PSD software in photon energies of 0.015-15 MeV for several λ values.    When all gamma-shielding parameters are evaluated together, the LBi50BEu glasses show a superior performance compared to LPb50BEu glasses in reducing photons. Besides, the protection capability of L(Pb/Bi)50BEu glasses against uncharged (fast neutrons) and charged particles (alpha and protons) was also evaluated. For this purpose, the macroscopic removal cross-section (ΣR) of glasses for fast neutrons was calculated firstly.     In Figure 9, Σ R values of both groups of glasses are established. In both glass systems, the Σ R values decreased as the density decreased with the addition of Eu 2 O 3 . The Σ R values of LPb50BEu glasses were 0.10106 cm −1 , 0.09999 cm −1 , 0.09478 cm −1 , and 0.09286 cm −1 , respectively, while, for LBi50BEu glasses, they were found to be 0.11484 cm −1 , 0.11428 cm −1 , 0.09745 cm −1 , and 0.09921 cm −1 . It appears that the LBi50BEu glass system is more effective at capturing neutrons than others. It is clear that selected glass systems are also successful at reducing neutrons when compared to water and paraffin (Σ R = 0.101 cm −1 ), which are traditional neutron moderators. As the charged particle moves through the material, it interacts with the atomic electrons in the material and its energy decreases. However, during this time, the stopping power increases because the kinetic energy of the particle is inversely proportional to the stopping power. The change of the mass stopping power (AMSP and PMSP) of L(Pb/Bi)50BEu glasses versus the photon energy for alpha and proton particles is given in Figure 10. While the charged particles move in the glass in the form of a Bragg curve, and the curve increases proportionally with 1/E, there is a sharp decrease in the curve at the end of the path where the particle travels through the matter. Since alpha particles are heavier than protons, they have reached the maximum MSP at higher energies. Since the stopping power of the material is proportional to the square of the atomic number, LBi50BEu glasses with larger Z eff values have higher MSP values. The furthest distance that the charged particles can travel through the material is expressed as the projected range (PR). Figure 11 presents the change of APR and PPR values of L(Pb/Bi)50BEu glasses in response to kinetic energy. Since the addition of Eu 2 O 3 reduces the Z eff values, PR is larger in glasses with 2 mol% Eu 2 O 3 added. Since protons are smaller in mass, they move faster and have a longer range inside the glass (PPR > APR). The PRs of alpha and proton particles are shorter in LBi50BEu glasses.  In Figure 9, ΣR values of both groups of glasses are established. In both glass systems, the ΣR values decreased as the density decreased with the addition of Eu2O3. The ΣR values of LPb50BEu glasses were 0.10106 cm −1 , 0.09999 cm −1 , 0.09478 cm −1 , and 0.09286 cm −1 , respectively, while, for LBi50BEu glasses, they were found to be 0.11484 cm −1 , 0.11428 cm −1 , 0.09745 cm −1 , and 0.09921 cm −1 . It appears that the LBi50BEu glass system is more effective at capturing neutrons than others. It is clear that selected glass systems are also successful at reducing neutrons when compared to water and paraffin (ΣR = 0.101 cm −1 ), which are traditional neutron moderators. As the charged particle moves through the material, it interacts with the atomic electrons in the material and its energy decreases. However, during this time, the stopping power increases because the kinetic energy of the particle is inversely proportional to the stopping power. The change of the mass stopping power (AMSP and PMSP) of L(Pb/Bi)50BEu glasses versus the photon energy for alpha and proton particles is given in Figure 10. While the charged particles move in the glass in the form of a Bragg curve, and the curve increases proportionally with 1/E, there is a sharp decrease in the curve at the end of the path where the particle travels through the matter. Since alpha particles are heavier than protons, they have reached the maximum MSP at higher energies. Since the stopping power of the material is proportional to the square of the atomic number, LBi50BEu glasses with larger Zeff values have higher MSP values. The furthest distance that the charged particles can travel through the material is expressed as the projected range (PR). Figure 11 presents the change of APR and PPR values of L(Pb/Bi)50BEu glasses in response to kinetic energy. Since the addition of Eu2O3 reduces the Zeff values, PR is larger in glasses with 2 mol% Eu2O3 added. Since protons are smaller in mass, they move faster and have a longer range inside the glass (PPR > APR). The PRs of alpha and proton particles are shorter in LBi50BEu glasses.   Finally, it is worth noting that the linear attenuation coefficients determined using Phy-X/PSD and MCNPX (2.7.0) were very consistent. Figure 12 depicts a comparison of obtained linear attenuation coefficients from MCNPX Monte Carlo code and Phy-X/PSD for the LBi50B sample. A relative difference of 2% was reported at 0.02 MeV photon energy. Overall, our findings showed that relative differences were varied from 1.15% to 2.6% at all photon energies. Both outcomes were reported in comparable linear attenuation coefficient values, based on our results. However, minor variations in certain energy areas were discovered. This is closely linked to the tools employed, since MCNPX is a Monte-Carlobased technique for radiation transport that needs user specification at different stages of the process described before. By contrast, Phy-X/PSD is a web-based tool that requires just the material composition, density, and energy quantities. As a result, some differences are almost certainly due to a variety of variables, including the number of dispersed gamma rays entering the detecting field, the narrow beam shape, the cross-section libraries and physics lists, the hardware performance, and the CPU characteristics of the computers used. Finally, it is worth noting that the linear attenuation coefficients determined using Phy-X/PSD and MCNPX (2.7.0) were very consistent. Figure 12 depicts a comparison of obtained linear attenuation coefficients from MCNPX Monte Carlo code and Phy-X/PSD for the LBi50B sample. A relative difference of 2% was reported at 0.02 MeV photon energy. Overall, our findings showed that relative differences were varied from 1.15% to 2.6% at all photon energies. Both outcomes were reported in comparable linear attenuation coefficient values, based on our results. However, minor variations in certain energy areas were discovered. This is closely linked to the tools employed, since MCNPX is a Monte-Carlo-based technique for radiation transport that needs user specification at different stages of the process described before. By contrast, Phy-X/PSD is a web-based tool that requires just the material composition, density, and energy quantities. As a result, some differences are almost certainly due to a variety of variables, including the number of dispersed gamma rays entering the detecting field, the narrow beam shape, the crosssection libraries and physics lists, the hardware performance, and the CPU characteristics of the computers used.

Conclusions
In this study, the nuclear radiation shielding capabilities were thoroughly examined for eight borate glasses of Eu2O3 containing high ratios of PbO/Bi2O3. For this aim, MAC

Conclusions
In this study, the nuclear radiation shielding capabilities were thoroughly examined for eight borate glasses of Eu2O3 containing high ratios of PbO/Bi2O3. For this aim, MAC values of the glasses, encoded LPb50BEu and LBi50BEu, in the 0.015-15 MeV photon energy range were acquired by MCNPX simulation codes and Phy-X/PSD online software. While the MAC values for LPb50BEu2 and LBi50Eu2 glasses produced values of between 79.045 cm 2 /g-0.045 cm 2 /g and 89.442 cm 2 /g-0.048 cm 2 /g, the MAC values of LPb50B and LBi50B glasses change between 78.429 cm 2 /g-0.045 cm 2 /g and 89.281 cm 2 /g-0.048 cm 2 /g. Based on the MAC values, other vital photon-shielding parameters, T 1/2 , λ, Z eff , EABF, and EBF, were also found for LPb50BEu and LBi50BEu glasses. When all parameters were evaluated, it was revealed that the LBi50BEu glass system was more effective than LPb50BEu in shielding gamma radiation. It was seen that the Σ R values of both glass systems were greater than conventional neutron moderators. LBi50BEu2 glass was also found to be superior to LPb50BEu2 glass in stopping charged particle radiation, as in gamma radiation.

Data Availability Statement:
The data presented in this study are available on request from the corresponding author.