Fast Neutron and Gamma-Ray Attenuation Properties of Some HMO Tellurite-Tungstate-Antimonate Glasses: Impact of Sm 3+ Ions

: Characteristics of tellurite-tungstate-antimonate glasses containing heavy metal oxide were investigated in detail using two methods: the MCNPX Monte Carlo code and the Phy-X/PSD platform. The inﬂuence of Sm 2 O 3 , translocating with TeO 2 at ratios of 0.2, 0.5, 0.8, 1, and 1.5 mol% on radiation shielding properties of glasses, was set forth with ﬁve glass structures determined according to the (75-x)TeO 2 -15Sb 2 O 3 -10WO 3 -xSm 2 O 3 glass composition. Densities of the glasses were prepared by doping a low ratio of Sm 2 O 3 that varied between 5.834 and 5.898 g/cm 3 . Sample densities, which have an important role in determining radiation shielding character, increased depending on the increase in Sm 2 O 3 concentration. Effective removal cross-section ( ∑ R) values against fast neutrons, as well as linear and mass attenuation coefﬁcients, half-value layer, mean free path, variation of effective atomic number against photon energy, exposure, and energy built-up factors, were simulated with the help of these two methods. As a result of these estimates, it can be concluded that values obtained using both methods are consistent with each other. From the obtained values, it can be concluded that the SM1.5 sample containing 1.5 mol% would have the most efﬁcient role in radiation shielding. An increase of Sm 2 O 3 resulted in a signiﬁcant increase in linear and mass attenuation coefﬁcients and effective removal cross-section values belonging to fast neutrons and, in addition, resulted in a decrease in the half value layer. Doping HMO glasses with Sm 2 O 3 was observed to contribute directly to the development of radiation shielding properties of the glass.


Introduction
Among the many kinds of glasses, heavy metal oxide (HMO) glasses have garnered considerable attention recently due to their low-phonon properties [1,2]. Heavy metal oxide glasses comprise more than 50% mol percent of a HM cation.
On the other hand, TeO 2 , Sb 2 O 3 , Bi 2 O 3 , and PbO are all known representatives of the HMO glass family. These glasses are superior photonic matrices due to their wider transparency interval spanning the visible to the mid-infrared range, improved non-linear optical features, the high solubility of rare-earth ions, and lower phonon energies than phosphate borate glasses and silicate glasses. Besides their outstanding thermal, mechanical, and chemical resistance, heavy metal oxide glasses have exceptional optical and electrical properties, including a high refractive index and dielectric constant. Therefore, heavy metal oxide glasses are good prospects for a variety of optoelectronic applications, including fiber optics, lasers, and sensors. However, material density (g/cm 3 ) is a basic necessity of potential substances for gamma radiation shielding applications. On the other hand, tellurium dioxide (TeO 2 ) is incapable of forming a glassy network under normal quenching conditions without the aid of a secondary material component known as a network modifier. Due to this characteristic, TeO 2 is a conditional glass former [3,4]. A study of the literature revealed that HMO glasses had been examined for their gamma ray attenuation characteristics, which are a result of their high material density. Celikbilek Ersundu et al., conducted several investigations on manufactured HMO glasses with nominal compositions of K 2 O-WO 3 -TeO 2 and ZnO-MoO 3 -TeO 2 [5,6]. As per their results, K30W60T10 and Z10M10T80 glasses were found to be the most efficient shielding glasses due to their increased resistance to ionizing gamma rays. Our research established that these two glass samples are comparable as they had the highest TeO 2 ratio in their structure.
Additionally, a review of the literature showed that a substantial amount of research had been conducted on HMO-Reinforced glasses. Al-Hadeethi and Sayyed, for example, used the Geant4 simulation code to analyze particular HMO doped borosilicate glasses [7]. Their results indicated that the addition of three dopants, namely Bi 2 O 3 , BaO, and TiO 2 , caused a reduction in the HVL, thus improving the attenuation performance of the investigated HMO glasses. D'Souza et al. examined the impact of Bi 2 O 3 on the structural, optical, mechanical, radiation shielding, and luminescence properties of borosilicate glasses containing HMO in another research [8]. Their findings showed that although the gamma-ray shielding capacity increased with successive applications of Bi 2 O 3 , the neutron attenuation capacity decreased. Our previous studies have led us to further studies on HMO glasses that integrate more extensive concepts. In this study, some of the promising and highly dense Sm 2 O 3 reinforced HMO glasses [9] have been selected from the literature. Accordingly, some of the significant contributions of Sm 2 O 3 additive to the fast neutron and gamma-ray attenuation characteristics of HMO glasses were studied using mathematical and simulation approaches. The results of radiation shielding properties are determined using MCNPX Monte Carlo code and Phy-X/PSD and then discussed considering the Sm 2 O 3 additive in each glass sample. We hypothesized that TeO 2 /Sm 2 O 3 substitution could change the gamma-ray and fast neutron properties of the HMO glasses. Therefore, each finding of the investigation will be addressed to the given scientific hypothesis. Considering the importance of HMO glasses in the literature and their shielding applications in various radiation facilities, the current study's findings may offer some promising and valuable insights into the existing HMO glass and radiation shielding literature.

Materials and Methods
A group of heavy metal oxide glasses based on the nominal composition of (75-x)TeO 2 -15Sb 2 O 3 -10WO 3 -xSm 2 O 3 (where; x = 0.2, 0.5, 0.8, 1, and 1.5 mol%) have been selected from the literature [9], where the authors have performed a characterization study on those glasses in terms of their luminescence properties. Their research findings encouraged us to broaden the scope of the characterization by including certain critical glass characteristics, namely nuclear radiation shielding capabilities. The compositions of the studied glass samples can be listed as follows.
Accordingly, we used two different tools to determine the critical gamma-ray shielding properties along with some mathematical applications for determining the effective removal cross section (∑R) values for fast neutrons. The linear attenuation coefficients of the glasses were derived using the general-purpose Monte Carlo software MCNPX (v.2.7.0) [10] and the online computation platform Phy-X/PSD [11]. The purpose of this dual tool method was to assess the consistency of the findings obtained from Monte Carlo simulations.

Technical Information of MCNPX Simulations
MCNPX is a general-purpose Monte Carlo code that can be used in different types of radiation transport simulations in nuclear, medical, and particle physics studies. This code enables the user to provide the simulation's necessary characteristics, including geometrical details, material properties, and the radiation source's energy and type, such as narrow beam, point isotropic, and so on. Our study defined a general gamma-ray transmission setup, which can provide basic information, such as the intensity of attenuated gamma-ray in terms of determining the linear attenuation coefficients. We developed a fundamental gamma-ray transmission setup in our research that may give fundamental information, such as the intensity of the attenuated gamma-ray when calculating the linear attenuation coefficients. Accordingly, an INPUT file was created considering cell card, surface card, and source information [10]. In the cell card, we identified the cells that were utilized and their densities and borders. Geometrical features of the boundaries have been specified in the surface card using the x, y, and z axis positions. Figure 1 depicts the modelled simulation setup along with its 3-D and 2-D views obtained from MCNPX visual editor. As it is seen from Figure 1, we set the locations of the used equipment considering their roles for gamma-ray transmission simulation. For instance, a gamma-ray attenuator has been placed between the source of point-isotropic radiation and the detecting field (F4 Tally Mesh). Additionally, two large Lead (Pb) blocks have been designed to absorb scattering gamma-rays, which may increase detection consistency. We would like to emphasize that simulations were performed on each glass sample using photon energy ranging from 0.015 MeV to 15 MeV. Finally, it is worth noting that each glass sample received a total of 10 8 particle tracks (Number of History) with various photon energies. After running all simulations, the MCNPX output exhibited a relative error rate of less than 1%. MCNPX simulations were performed in Lenovo TM ThinkStation620, which has a Ryzen™ Threadripper™ Pro 3995WX (2.7 GHz, 64 Cores, 256 MB Cache) processor. Next, a Phy-X/PSD platform was used to determine the attenuation coefficients. The main difference between the MCNPX and Phy-X/PSD is their format. On the one hand, MCNPX is a Monte Carlo algorithm that needs user definitions for almost every element of the system, including material design, simulation environment, physics list used, and variance reduction methods. On the other hand, Phy-X/PSD is a platform that delivers results immediately as a consequence of mathematical computations performed against a predefined database. Additional information may be acquired from the original article, which is available elsewhere [11].

Studied Nuclear Radiation Shielding Parameters
Several additional gamma radiation attenuation parameters were calculated after finding the linear attenuation coefficients (µ ). To begin, we used Equation (1) to calculate the mass attenuation coefficients (µ m) of the SM glasses [12].
where µ is the linear attenuation coefficient, and is the glass density. Following that, the SM glasses' half value layer (T1/2) values were calculated. T1/2 is a key factor in determining the need for very stringent radiation protective measures [13]. This quantity provides remarkable information about the thickness of a shielding material at which the intensity of a gamma ray received on it is effectively halved. Additionally, key gamma ray shielding characteristics, such as mean free path (λ) [14], effective atomic numbers (Zeff) [15] against gamma-ray attenuation, exposure, and energy absorption build-up factors (EBF and EABF) [16][17][18][19][20], were measured throughout the gamma-radiation energy range of 0.015-15 MeV. On the other side, we aimed to evaluate the SM glasses' attenuation properties against fast neutrons, which can be beneficial for special utilizations in neutron used/expected (i.e., photodisintegration) radiation facilities. As a result, we calculated the effective removal cross-sections of SM glasses against fast neutrons (∑R) [21,22]. Detailed information on the parameters under investigation may be found in the literature and elsewhere [23][24][25].

Results and Discussion
In this study, five different Sm2O3-reinforced heavy metal oxide glasses based on the nominal composition of (75-x)TeO2-15Sb2O3-10WO3-xSm2O3 (where; x = 0.2, 0.5, 0.8, 1, and 1.5 mol%) have been investigated in terms of their gamma-ray and neutron shielding properties. First, we calculated the linear attenuation coefficients by using MCNPX code. Following the given details above, linear attenuation coefficients for each glass sample were determined at different energies that varied from 0.015 MeV to 15 MeV. Next, the same glass compositions (see Table 1) along with their densities were defined in the Phy-X/PSD platform. Overall, the obtained results agreed well with each other.

Studied Nuclear Radiation Shielding Parameters
Several additional gamma radiation attenuation parameters were calculated after finding the linear attenuation coefficients (µ). To begin, we used Equation (1) to calculate the mass attenuation coefficients (µ m ) of the SM glasses [12].
where µ is the linear attenuation coefficient, and ρ is the glass density. Following that, the SM glasses' half value layer (T 1/2 ) values were calculated. T 1/2 is a key factor in determining the need for very stringent radiation protective measures [13]. This quantity provides remarkable information about the thickness of a shielding material at which the intensity of a gamma ray received on it is effectively halved. Additionally, key gamma ray shielding characteristics, such as mean free path (λ) [14], effective atomic numbers (Z eff ) [15] against gamma-ray attenuation, exposure, and energy absorption build-up factors (EBF and EABF) [16][17][18][19][20], were measured throughout the gamma-radiation energy range of 0.015-15 MeV. On the other side, we aimed to evaluate the SM glasses' attenuation properties against fast neutrons, which can be beneficial for special utilizations in neutron used/expected (i.e., photodisintegration) radiation facilities. As a result, we calculated the effective removal cross-sections of SM glasses against fast neutrons (∑R) [21,22]. Detailed information on the parameters under investigation may be found in the literature and elsewhere [23][24][25].

Results and Discussion
In this study, five different Sm 2 O 3 -reinforced heavy metal oxide glasses based on the nominal composition of (75-x)TeO 2 -15Sb 2 O 3 -10WO 3 -xSm 2 O 3 (where; x = 0.2, 0.5, 0.8, 1, and 1.5 mol%) have been investigated in terms of their gamma-ray and neutron shielding properties. First, we calculated the linear attenuation coefficients by using MCNPX code. Following the given details above, linear attenuation coefficients for each glass sample were determined at different energies that varied from 0.015 MeV to 15 MeV. Next, the same glass compositions (see Table 1) along with their densities were defined in the Phy-X/PSD platform. Overall, the obtained results agreed well with each other.   Figure 2, there is a strong correlation between the two results. However, we discovered some minor inconsistencies as well. Due to the fact that the MCNPX and Phy-X/PSD formats are diametrically opposed, it is quite reasonable to anticipate some discrepancies in the results. MCNPX is a user-friendly program that needs certain fundamental processes, such as material design and source specification.    Figure 2, there is a strong correlation between the two results. However, we discovered some minor inconsistencies as well. Due to the fact that the MCNPX and Phy-X/PSD formats are diametrically opposed, it is quite reasonable to anticipate some discrepancies in the results. MCNPX is a user-friendly program that needs certain fundamental processes, such as material design and source specification. On the other hand, there is a direct correlation between a computer's performance and its relative error. Additionally, there are many sub-titles that may affect the consistency of the Monte Carlo simulation results. However, Phy-X/PSD is a web-based platform that enables users to get different shielding characteristics based on just the material description and energy range. It is worth noting that the total relative variation between the findings ranged from 1.2% to 2.9%. After checking the consistency of the tools, we On the other hand, there is a direct correlation between a computer's performance and its relative error. Additionally, there are many sub-titles that may affect the consistency of the Monte Carlo simulation results. However, Phy-X/PSD is a web-based platform that enables users to get different shielding characteristics based on just the material description and energy range. It is worth noting that the total relative variation between the findings ranged from 1.2% to 2.9%. After checking the consistency of the tools, we proceed to the following parameters. Meanwhile, our results indicate that the SM1.5 sample exhibits the highest linear attenuation coefficients throughout the whole energy range. This may be explained partly by the glass densities, as well as the chemical compositions listed in Table 1. Figure 3 illustrates the difference in glass densities. As can be observed, density levels significantly increased from SM0.2 to SM1.5. As seen in Table 1, increasing the Sm 2 O 3 reinforcements also improved the glass density. Our findings indicated that adding Sm 2 O 3 to HMO glasses enhanced their density and, therefore, their linear attenuation coefficients.
Appl. Sci. 2021, 11, x FOR PEER REVIEW 6 of 18 proceed to the following parameters. Meanwhile, our results indicate that the SM1.5 sample exhibits the highest linear attenuation coefficients throughout the whole energy range. This may be explained partly by the glass densities, as well as the chemical compositions listed in Table 1. Figure 3 illustrates the difference in glass densities. As can be observed, density levels significantly increased from SM0.2 to SM1.5. As seen in Table 1, increasing the Sm2O3 reinforcements also improved the glass density. Our findings indicated that adding Sm2O3 to HMO glasses enhanced their density and, therefore, their linear attenuation coefficients. At this moment, Figure 4 depicts the changes in µ values as photon energy (MeV) function. From 0.015 MeV to 0.03 MeV, a sharp decrease was seen. Following that, a sharp peak near Te's k-absorption edge was found. This demonstrates that Te is present in all glass samples. We would like to emphasize that the results of the glass samples were near to each other due to the low molar variations in the Sm2O3 additive. Nevertheless, adding the Sm2O3 additive had a synergistic impact on the linear attenuation coefficients of SM glasses. Our findings clearly showed that the SM1.5 sample has the maximum µ values at all energies. On the other hand, the term mass attenuation coefficient (µ m) refers to the density-independent attenuation coefficient, which contains critical information about the material's shielding performance as a function of its elemental structure. At this moment, Figure 4 depicts the changes in µ values as photon energy (MeV) function. From 0.015 MeV to 0.03 MeV, a sharp decrease was seen. Following that, a sharp peak near Te's k-absorption edge was found. This demonstrates that Te is present in all glass samples. We would like to emphasize that the results of the glass samples were near to each other due to the low molar variations in the Sm 2 O 3 additive. Nevertheless, adding the Sm 2 O 3 additive had a synergistic impact on the linear attenuation coefficients of SM glasses. Our findings clearly showed that the SM1.5 sample has the maximum µ values at all energies. On the other hand, the term mass attenuation coefficient (µ m ) refers to the density-independent attenuation coefficient, which contains critical information about the material's shielding performance as a function of its elemental structure. Figure 5 illustrates the variation of µ m values in the low-energy region. Similar to the discovery of µ values, the SM1.5 sample was reported with maximum amounts. This is explained by the fact that replaced TeO 2           Meanwhile, Figure 5 clearly demonstrated the Te k-absorption peak, indicating that the overwhelming majority of the nominal glass composition was TeO 2 . In addition, we demonstrated the variation of µ m values as a function of photon energy from 0.015 MeV to 15 MeV. The dominance of main photon-matter interactions, such as photoelectric effect, Compton scattering, and pair production, can be observed in Figure 6.
Meanwhile, Figure 5 clearly demonstrated the Te k-absorption peak, indicating that the overwhelming majority of the nominal glass composition was TeO2. In addition, we demonstrated the variation of µ m values as a function of photon energy from 0.015 MeV to 15 MeV. The dominance of main photon-matter interactions, such as photoelectric effect, Compton scattering, and pair production, can be observed in Figure 6. According to findings, SM1.5 has the maximum µ m values among the studied SM glass samples. In this study, half value layers (T1/2) of SM glasses were also determined between 0.015 MeV and 15 MeV. The term T1/2 is crucial for determining the thickness of a shielding material needed to reduce the initial gamma-ray intensity to half Figure 7. It is worth noting that the T1/2 term has an inverse relationship with the µ value, which implies that material with higher µ values may also offer lower T1/2 values. Additionally, a material with the lowest T1/2 values may be regarded as a clear indicator of gamma-ray superiority among the studied material group. Our results indicated that the SM1.5 sample with the highest Sm2O3 additive has the lowest T1/2 values at all energy levels. For example, T1/2 values were reported as 2.00553 cm, 2.00262 cm, 1.99835 cm, 1.99359 cm, and 1.98160 cm for SM0.2, SM0.5, SM0.8, SM1.0, and SM1.5 samples at 1 MeV, respectively. At this moment, it can be noted that 1.3% mole Sm2O3 (i.e., from 0.2% to 1.5%) decreased the T1/2 value from 2.00553 cm to 1.98160 cm. According to findings, SM1.5 has the maximum µ m values among the studied SM glass samples. In this study, half value layers (T 1/2 ) of SM glasses were also determined between 0.015 MeV and 15 MeV. The term T 1/2 is crucial for determining the thickness of a shielding material needed to reduce the initial gamma-ray intensity to half Figure 7. It is worth noting that the T 1/2 term has an inverse relationship with the µ value, which implies that material with higher µ values may also offer lower T 1/2 values. Additionally, a material with the lowest T 1/2 values may be regarded as a clear indicator of gamma-ray superiority among the studied material group. Our results indicated that the SM1.5 sample with the highest Sm 2 O 3 additive has the lowest T 1/2 values at all energy levels. For example, T 1/2 values were reported as 2.00553 cm, 2.00262 cm, 1.99835 cm, 1.99359 cm, and 1.98160 cm for SM0.2, SM0.5, SM0.8, SM1.0, and SM1.5 samples at 1 MeV, respectively. At this moment, it can be noted that 1.3% mol Sm 2 O 3 (i.e., from 0.2% to 1.5%) decreased the T 1/2 value from 2.00553 cm to 1.98160 cm.
As with pure elements, the atomic numbers of compounds, alloys, and composite materials cannot be represented by a single number in the various energy zones. This number is referred to as the effective atomic number (Z eff ) for compounds, alloys, and mixtures, and it changes according to the photon energy [26]. Figure 8 depicts the variation of Z eff as a function of incident photon energy at all energies. The results indicated that the sample with the highest Zeff value is SM1.5, with the most Sm 2 O 3 in the structure. However, no sharp differences were reported due to the structural similarities between the samples. It should be noted that the minimum difference for Z eff values was reported as 0.07 at 0.04 MeV, whereas the maximum difference was 0. As with pure elements, the atomic numbers of compounds, alloys, and composite materials cannot be represented by a single number in the various energy zones. This number is referred to as the effective atomic number (Zeff) for compounds, alloys, and mixtures, and it changes according to the photon energy [26]. Figure 8 depicts the variation of Zeff as a function of incident photon energy at all energies. The results indicated that the sample with the highest Zeff value is SM1.5, with the most Sm2O3 in the structure. However, no sharp differences were reported due to the structural similarities between the samples. It should be noted that the minimum difference for Zeff values was reported as 0.07 at 0.04 MeV, whereas the maximum difference was 0.36 at 0.06 MeV. The buildup factor is a correction factor used in shielding computations to accou for the effect of scattered radiation and any secondary particles in the medium. If o intends to compensate for secondary radiation accumulation, one must add a buildup f The buildup factor is a correction factor used in shielding computations to account for the effect of scattered radiation and any secondary particles in the medium. If one intends to compensate for secondary radiation accumulation, one must add a buildup factor. The accumulation factor is thus a multiplicative factor that incorporates the contribution of the scattered photons into the reaction to the uncollided photons. Thus, the accumulation factor may be calculated as the ratio of the entire dosage to the uncollided dose-response [27]. Meanwhile, the term of buildup factor can be classified as to exposure buildup factor (EBF) and energy absorption buildup factor (EABF) [28]. In parallel to the given description, the lower buildup factor values can be considered a superiority pattern against gamma-rays since the uncollided photon amount in the successful shields would be low. Figures 9 and 10 depicts the variations of EBF and EABF values as a function of energy at various mean free paths (i.e., from 0.5 to 40). The highest values were seen in both EBF and EABF in the mid-energy range, where Compton scattering is the main interaction between the gamma-ray and the material (see Tables S1-S5). In other words, this area has a high amount of uncollided photons. As a result, relatively higher values for the buildup factor are required to correct the transmission calculations. Our results indicate that SM1.5 has the lowest accumulation factors in both EBF and EABF. Thus, incoming gamma-rays may interact with the SM1.5 sample more often than with other samples.
The effective removal cross-section, R (cm 2 /g), refers to the possibility that a fast or fission energy neutron would undergo the first collision, thus excluding it from the group of penetrating, uncollided neutrons. For neutron energies between 2 and 12 MeV, it is believed to be roughly constant. Moreover, the materials with the highest ∑R values can be considered as superior materaials against hazardous neutron particles. In this study, ∑R values of SM glasses were determined, and the results have been demonstrated in Figure 11. Following the gamma-ray attenuation characteristics, a distinguished synergistic impact of increasing Sm 2 O 3 was eventually found. As shown in Figure 11, the SM1.5 sample clearly differs from the SM0.2 sample. Therefore, one can say that Sm 2 O 3 can be considered a useful tool to improve the gamma-ray and fast neutron shielding properties of HMO glasses. The effective removal cross-section, R (cm 2 /g), refers to the possibility that a fast or fission energy neutron would undergo the first collision, thus excluding it from the group of penetrating, uncollided neutrons. For neutron energies between 2 and 12 MeV, it is believed to be roughly constant. Moreover, the materials with the highest ∑R values can be considered as superior materaials against hazardous neutron particles. In this study, ∑R values of SM glasses were determined, and the results have been demonstrated in Figure 11. Following the gamma-ray attenuation characteristics, a distinguished synergistic impact of increasing Sm2O3 was eventually found. As shown in Figure 11, the SM1.5 sample clearly differs from the SM0.2 sample. Therefore, one can say that Sm2O3 can be considered a useful tool to improve the gamma-ray and fast neutron shielding properties of HMO glasses.

Conclusions
In the current study, we have focused on the radiation shielding characteristics of doped oxide glasses Sm2O3 containing a heavy metal oxide. It can be concluded that the inclusion of Sm2O3 in heavy metal oxide glasses can be a useful option for improving the capabilities of radiation shielding and other properties of materials, such as optical, luminescence, structural, and thermal. In terms of luminescence characteristics, Sm2O3, which has occupied a niche in photonics, may be a favorable compound due to its large size and high density. In fact, the doping of Sm2O3 significantly increased the density of the synthesized sample. The results indicated that the SM1.5 sample with the highest Sm2O3 additive has the highest density and lowest T1/2 values at all energy levels. For example, T1/2 values were reported as 2.00553 cm, 2.00262 cm, 1.99835 cm, 1.99359 cm, and 1.98160 cm for SM0.2, SM0.5, SM0.8, SM1.0, and SM1.5 samples at 1 MeV, respectively. At this moment, it can be noted that 1.3% mole Sm2O3 (i.e., from 0.2% to 1.5%) decreased the T1/2 value from 2.00553 cm to 1.98160 cm. Thus, the SM1.5 glass presents as the best sample for blocking gamma radiation in the current investigation.

Conclusions
In the current study, we have focused on the radiation shielding characteristics of doped oxide glasses Sm 2 O 3 containing a heavy metal oxide. It can be concluded that the inclusion of Sm 2 O 3 in heavy metal oxide glasses can be a useful option for improving the capabilities of radiation shielding and other properties of materials, such as optical, luminescence, structural, and thermal. In terms of luminescence characteristics, Sm 2 O 3 , which has occupied a niche in photonics, may be a favorable compound due to its large size and high density. In fact, the doping of Sm 2 O 3 significantly increased the density of the synthesized sample. The results indicated that the SM1.5 sample with the highest Sm 2 O 3 additive has the highest density and lowest T 1/2 values at all energy levels. For example, T 1/2 values were reported as 2.00553 cm, 2.00262 cm, 1.99835 cm, 1.99359 cm, and 1.98160 cm for SM0.2, SM0.5, SM0.8, SM1.0, and SM1.5 samples at 1 MeV, respectively. At this moment, it can be noted that 1.3% mol Sm 2 O 3 (i.e., from 0.2% to 1.5%) decreased the T 1/2 value from 2.00553 cm to 1.98160 cm. Thus, the SM1.5 glass presents as the best sample for blocking gamma radiation in the current investigation.