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Analysis of Radiation Shielding and Density Prediction Models for Boro-Tellurite Glass Systems

Written By

Praveen Kumar R., Susheela K. Lenkennavar, Kiran N. and Kiran D.S.

Submitted: 29 December 2024 Reviewed: 07 January 2025 Published: 29 April 2025

DOI: 10.5772/intechopen.1008957

Glass Science - Innovations and Applications IntechOpen
Glass Science - Innovations and Applications Edited by Helena Vasconcelos

From the Edited Volume

Glass Science - Innovations and Applications [Working Title]

Prof. Helena Cristina Vasconcelos

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Abstract

In this investigation, we applied the Phy-X/Photon Shielding and Dosimetry (PSD) programs to determine the mass attenuation coefficient (MAC) for various glass compositions of TeO2 + B2O3 + MgO + Li2O + La2O3. The study encapsulates the simulation outcomes concerning the radiation shielding performance of boro-tellurite glasses, underlining their remarkable attributes. It consolidates vital shielding parameters such as the mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), effective atomic numbers (Zeff), half-value layers (HVL), mean free path (MFP), and exposure buildup factors (EBF). The analysis of these parameters demonstrates that the glass material possesses notable shielding properties, characterized by low HVL, tenth-value layer (TVL), and MFP values. Density values play a critical role in the theoretical assessment of radiation properties in the Phy-X/PSD software, with density calculated using a theoretical model.

Keywords

  • boro-tellurite glasses
  • shielding materials
  • mass attenuation coefficient
  • radiation
  • Phy-X/PSD

1. Introduction

In the realm of industrial glass production, the density of glass stands out as a key property, necessary for the calculation of various other attributes such as Young’s modulus, elastic properties, thermal conductivity, and refractive index. From an academic viewpoint, density is intricately linked to molar volume and ionic packing ratio, making it crucial for the analysis of material structures, whether they are inorganic, polymeric, or metallic [1].

In the domains of nuclear physics, engineering, and medicine, radiation shielding materials are of significant importance. Glass has emerged as a favored option among researchers conducting studies on radiation shielding. To explore the radiation characteristics of various glass types, a combination of theoretical, experimental, and computational techniques is utilized, focusing on energy levels between 0.00891 MeV and 15 MeV.

Transparent glasses can be used in radiation shielding materials as a dual function [2].

Radiation leakage poses significant risks to living organisms [3]. As the use of radiation in everyday human activities continues to expand, the demand for effective radiation shielding is growing steadily. Consequently, researchers are focused on developing new materials capable of shielding against high-energy electromagnetic radiation, such as X-rays and gamma rays, which are utilized in various fields, including radiology [4], elemental analysis [5, 6], food irradiation [7], industrial applications, and medical practices [8].

Lead (Pb) is a widely recognized element utilized in radiation shielding applications. However, its limitations, including a low melting point of 327.5°C, inadequate mechanical strength, and toxicity, necessitate the development of alternative protective materials that are lead-free. Therefore, it is crucial to create new shielding materials that possess high density, excellent mechanical strength, resistance to chemical abrasion, high transparency, elevated melting temperatures, and cost-effectiveness.

An analysis of research conducted between 2008 and 2023 reveals a significant surge in interest regarding photon attenuation parameters over the last three decades. This trend underscores the critical role of research in radiation shielding. Most of these studies focus on calculating radiation attenuation parameters, including the linear attenuation coefficient (LAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Zeff), effective electron number (Neff), effective conductivity (Ceff), and buildup factors, to identify optimal shielding materials for specific or continuous energy ranges [9].

The trend of utilizing glass as a radiation shielding material is increasingly supported by a substantial amount of research dedicated to exploring the shielding capabilities of various glass systems [10]. In particular, boro-tellurite glasses are of great interest for their radiation absorption properties, stemming from their unique attributes. Their optical transparency is crucial for applications in medical and industrial radiography, as well as in X-ray security screening, where it is important to monitor the entire process. Additionally, the chemical makeup and density of boro-tellurite glasses indicate their potential effectiveness in radiation attenuation. High-density materials are known to shield against photons and charged particles effectively, while boron-rich materials are adept at neutron shielding. Therefore, boro-tellurite glasses are anticipated to provide broad-spectrum radiation protection [11].

The effectiveness of a radiation shield is influenced by various factors, such as the energy and type of radiation, the thickness and composition of the shielding material, and the distance from the radiation source to the shielding material, among others [12].

The subsequent equation serves to calculate the radiation amount that penetrates a material [13]. Here, I refers to the intensity of the radiation following its passage through the material, Io is the initial radiation intensity, μ represents the linear attenuation coefficient of the material, and x denotes the thickness of the material.

I=I0eμxE1

In this investigation, I employed a density model to calculate density and carried out a theoretical study of radiation shielding parameters using the Phy-X/PSD software.

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2. Gamma radiation attenuation properties of boro-tellurite glasses

2.1 Key attributes of materials suitable for gamma radiation protection

Gamma rays represent a type of electromagnetic radiation that possesses high energy, is uncharged, and has no rest mass. These rays are released from the nucleus of an excited atom during the process of nuclear decay, as the atom moves from a higher energy state to a more stable, lower energy state [14].

The attenuation coefficient is a measure that indicates the ease with which electromagnetic radiation can pass through a material. Typically, this coefficient is represented in units of area per mass (cm2/g). By utilizing both the attenuation coefficient and the density of the material, one can estimate the transmission of gamma radiation through a specified thickness of shielding material or determine the necessary thickness of shielding to achieve a specific level of attenuation. It is important to note that gamma attenuation coefficients are inversely related to gamma energy and directly proportional to the atomic number of the elements that make up the shielding material.

Despite being electrically neutral, gamma rays have the ability to ionize atoms directly via the photoelectric effect and the Compton effect [15].

Gamma rays propagate at the speed of light and can travel considerable distances in the air before their energy is depleted [16]. This enables them to easily penetrate various forms of matter, including the human body. As they lose speed, they can damage living cells by imparting energy to neighboring cells. The nature of gamma radiation presents significant dangers to those who work with it. On a positive note, it has important applications in the realm of nuclear medicine.

2.2 The effectiveness of boro-tellurite glasses in shielding against gamma, X-ray, and neutron radiation

TeO2 stands out as a highly promising foundation for innovative attenuating transparent blended materials due to its relatively low melting point (800–850°C), extensive optical transmission range (0.4–5 μm), and exceptional resistance to corrosion and water. Additionally, it boasts a high density, thermal stability, dielectric constant, and effective atomic number (Zeff), all while maintaining strong chemical stability and mechanical strength [17].

The potential of heavy metal oxide borate glasses as transparent shielding materials is under consideration for applications in radiological engineering, glass windows, and nuclear reactors. A thorough investigation into the radiation shielding effectiveness of these glasses is necessary, focusing on their ability to protect against X-rays, gamma rays, and energetic heavy charged particles such as protons, heavy ions, and fast neutrons [18].

TeO2 serves as a conditional glass former and does not vitrify under normal quenching conditions unless a secondary component is added. As a result, the introduction of secondary components, including heavy metal oxides, alkali, or halogens, enhances its ability to form glass [19].

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3. Theoretical background

3.1 Phys-X/SPD software

A comprehensive online tool for Photon Shielding and Dosimetry (PSD) has been developed and is available at https://phy-x.net/PSD. This software is designed to calculate key parameters related to shielding and dosimetry, such as linear and mass attenuation coefficients (LAC, MAC), half and tenth value layers (HVL, TVL), mean free path (MFP), effective atomic number and electron density (Zeff, Neff), effective conductivity (Ceff), and energy absorption and exposure buildup factors (EABF, EBF). It can provide data on shielding parameters within the energy range of 1 keV to 15 MeV. There is significant interest in the study of X-ray and gamma-ray interactions with various media. This information is essential for numerous engineering and medical applications, particularly in the fields of radiation protection and dosimetry. Parameters such as the Mass Attenuation Coefficient (MAC), Half-Value Layer (HVL), Mean Free Path (MFP), effective atomic number (Zeff), and effective charge (Ceff) are critical for assessing the radiation shielding capabilities of materials. Accurate calculations of these parameters are necessary for the effective characterization of shielding materials in both shielding and dosimetry applications. Additionally, when developing any shielding material, it is imperative to calculate its radiation shielding parameters through both experimental and theoretical methods [20].

Heavy metal oxide (HMO) glasses have emerged as a substitute for concrete in radiation shielding applications. Tellurite glasses, a specific type of HMO glass, exhibit remarkable properties, such as the ability to alter their composition with different elements and components. Their high content of polarizable ions and transition metal ions further enhances their nonlinear optical performance, making them more effective than other glass varieties [21].

The investigation of the shielding effectiveness of tellurite glasses has gained significant importance for assessing their future applications in radiation protection. A key characteristic of TeO2 is its ability to be influenced by glass formers, as it does not vitrify under standard quenching conditions without the incorporation of secondary components. Consequently, the addition of heavy metal oxides, alkali, or halogens can enhance its glass-forming capacity by serving as secondary constituents [22].

When examining gamma-ray attenuation, the intensity of an incident photon beam (I0) is reduced as it travels through a medium, in accordance with the Lambert-Beer law.

I=Ioeμt

Here, I is the intensity of the transmitted photons, while I0 reflects the intensity of the incident photons. The linear attenuation coefficient (μ) and the thickness of the medium (t) are both measured in centimeters. Utilizing the (μ/ρ) parameter is recommended, as it is independent of the medium’s density. The calculation for μ/ρ can be found in the equation below.

μρ=1ρ.tlnI0IE2

In addition, HVL is a practical and quick parameter for selecting the necessary material for γ-ray shielding, which diminishes the radiation intensity to 50% of its starting level [23].

HVL=ln2μE3

The packing density parameter is calculated using (Eq.(4)), which is essential for assessing the density of glass systems.

Vi=43π.NA.X.rM3+Y.ro3E4

We applied the density model to determine the density of the glass system [1].

i.e.

ρ=0.53.MiXiViXiE5

After calculating the density with (Eq.(5)), we identified the need for a modification to improve its accuracy. Consequently, we have developed a new equation, referred to as (Eq.(6)), which is designed to reduce errors.

Modified equation is

ρ=0.53.MiXiViXi+0.35andρ=0.53.MiXiViXi+0.75E6

To achieve the desired results, one must add 0.35 for binary and tertiary glass systems, while quaternary systems and those with more components necessitate an addition of 0.75.

ρ=0.53.MiXiViXi+0.35..for binary and tertiary
ρ=0.53.MiXiViXi+0.75.For quaternary,senary,etc.

Density values have been computed using (Eq.(6)). and are displayed in Table 1, where theoretical calculations are compared with experimental results.

Glass matrixCoordination numberExperimental density value (g/cm3)Theoretical density (g/cm3) Calculated using (Eq.(7))
70TeO2-10Bi2O3-20ZnO66.166.38
10PbO-30WO3-60TeO266.436.49
40BaO-20MoO3-40P2O563.763.60
10CaF2-48B2O3-20TeO2-22CaO63.322.85
30PbO-10ZnO-50TeO2-10B2O366.226.07
46B2O3 + 20TeO2+ 19CaO + 10Li2O + 5ZrO263.113.11
20TeO2-10Na2O-60B2O3-7CaO-3ZrO263.953.02
20TeO2-25B2O3-10GeO2-35MgO-10La2O364.0783.65
50TeO2-10BaO-30Li2O-10GeO264.344.30
80TeO2-5ZnO-5Li2O3-10Bi2O366.156.01
70TeO2-15ZnO-15PbO66.256.6

Table 1.

Density (g/cm3) values of various glasses. Theoretical calculations of density values were made and compared with values that have already been determined through experiments.

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4. Radiation shielding properties calculated using Phy-X/PSD software

As shown in Figure 1, the Phy-X/PSD software allows for the calculation of various parameters, and.

Figure 1.

Radiation shielding parameters, Phy-X/PSD software allows for the calculation of these parameters.

I have determined the significant parameters outlined below.

4.1 Mass attenuation coefficients

The interaction probability of gamma rays with a glass sample is characterized by the mass attenuation coefficient (μ/ρ), with ρ representing the density of the glass. This coefficient is essential for determining various shielding parameters, including the effective atomic number (Zeff), Half Value Layer (HVL), Mean Free Path (MFP), and several other related factors.

The evaluation of gamma-ray shielding properties in materials like glasses relies heavily on the mass attenuation coefficient (μ/ρ), which can be theoretically calculated using the mixture rule. The Phy-X/PSD software is a valuable resource for obtaining μ/ρ for our glass samples. This technique has been frequently used to characterize the gamma-ray shielding effectiveness of different materials [24, 25].

4.2 Linear attenuation coefficient (LAC)

The linear attenuation coefficient, commonly referred to as LAC or μ, quantifies the extent to which radiation can penetrate a material. Unlike the mass attenuation coefficient (MAC). This coefficient is widely utilized to assess the effectiveness of a material in providing radiation shielding [26].

The linear attenuation coefficient is a key factor in the shielding and protection of materials from radiation. It has been observed that materials with higher density possess higher linear attenuation coefficients. Therefore, to enhance a material’s capability for radiation protection, increasing its density is recommended.

4.3 Half-value layer (HVL)

The half-value layer, known as HVL, is a widely recognized parameter for evaluating the shielding properties of materials. It serves as an indicator of how well a material can attenuate radiation, specifically representing the thickness that reduces the radiation intensity to half of its initial measurement [26].

The HVL of a sample may differ according to the radiation source, given that photons exhibit varying degrees of penetration. This measurement is significant because it reveals the thickness of the material needed to lower the radiation intensity to acceptable safety standards [26].

It is generally acknowledged that the half-value layer (HVL) serves as a measure of a material’s ability to shield against radiation. In our current research, we evaluate the HVL values for all synthesized glasses using their attenuation coefficients within the photon energy spectrum of 0.008 MeV to 15 MeV, as depicted in Figure 2.

Figure 2.

Illustrates the relationship between the linear attenuation coefficients of various materials and their respective densities.

20TeO2+40B2O3+10MgO+20Li2O+10La2O3,30TeO2+37.5B2O3+20MgO+11.5Li2O+1La2O3,35TeO2+37.5B2O3+23MgO+8.5Li2O+1La2O3,40TeO2+35B2O3+20MgO+3.5Li2O+1.5La2O3

In Table 2, the half-value layers (HVL) of the present glasses 20TeO2 + 40B2O3 + 10MgO + 20Li2O + 10La2O3, 30TeO2 + 37.5B2O3 + 20MgO + 11.5Li2O + 1La2O3, 35TeO2 + 37.5B2O3 + 23MgO + 8.5Li2O + 1La2O3, 40TeO2 + 35B2O3 + 20MgO + 3.5Li2O + 1.5La2O3 at certain energy levels are shown, along with a comparison to regular concrete [27].

Energy (MeV)Ordinary concreteTBMLL20TBMLL30TBMLL35TBMLL40
0.11.7470.1950.2310.2140.186
0.53.4182.4452.4062.3202.188
15.2483.7413.5943.4813.315
510.4117.1016.9866.7036.269
1013.1527.3757.4537.0796.497
1514.1997.0717.2516.8496.225

Table 2.

Half value layer (in cm) for TeO2 + B2O3 + MgO + Li2O + La2O3 glasses and ordinary concrete. The half value layer (HVL) measurements of various boro-tellurite glass compositions have been compared to those of ordinary concrete.

4.4 Mean free path (MFP)

The concept of mean free path, or MFP, provides a way to express the average distance a particle must cover in a medium before it engages in an interaction or collision with the material. This factor is determined by the nature of the radiation and the behavior of particles in relation to the material. In the context of radiation shielding, the mean free path (MFP) indicates the distance that photons must traverse before they are absorbed or scattered by the material [26].

When the MFP is shorter, it signifies that gamma rays interact more frequently with matter, which implies that a smaller distance between consecutive interactions results in improved gamma-ray shielding capabilities [28].

4.5 Tenth value layer (TVL)

Another important parameter that is often considered alongside the HVL is the TVL, known as the tenth value layer. The TVL sets a more demanding requirement than the HVL, defining the thickness of material necessary to lower the radiation intensity to 10% of its starting value.

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5. Results and discussions

In our study of the chosen TeO2 + B2O3 + MgO + Li2O + La2O3 glass system, we examined its radiation attenuation capabilities by assessing various shielding factors ranging from 0.008 to 15 MeV. The calculations for these factors were performed using Phy-X software.

The relationship between the mass attenuation coefficient (μ/ρ) and photon energy for the TeO2 + B2O3 + MgO + Li2O + La2O3 glass system is presented in Figure 3, covering the energy spectrum from 0.00891 MeV to 15 MeV. As photon energy increased to 1.5 MeV, the (μ/ρ) values showed a pronounced decrease. This drop in μ/ρ for the glasses in the low energy spectrum can be attributed to the photoelectric absorption cross-section, which is associated with E3.5. Additionally, within the intermediate energy range of 1.5–4 MeV, Compton scattering emerges as the primary interaction mechanism for gamma rays. This interaction exhibits a minimal dependence on the atomic number (Z), which results in comparable μ/ρ values across all glass materials in this energy range. In the high energy range (E > 4 MeV). As the pair production mechanism becomes more dominant, we observed a slight increase in the (μ/ρ) values with rising photon energy toward the end of the energy spectrum.

Figure 3.

The mass attenuation coefficients (cm2/g) for the TeO2 + B2O3 + MgO + Li2O + La2O3 glass system. Graphical representation of MAC values in relation to photon energy for various glass compositions.

It is important to note that, for the current glass system, the calculated (μ/ρ) values follow this order: 30TeO2 + 37.5B2O3 + 20MgO + 11.5Li2O + 1La2O3 < 35TeO2 + 37.5B2O3 + 23MgO + 8.5Li2O + 1La2O3 < 40TeO2 + 35B2O3 + 20MgO + 3.5Li2O + 1.5La2O3 < 20TeO + 40B2O3 + 10MgO + 20Li2O + 10La2O3. This demonstrates that by altering the glass composition, one can effectively increase or decrease the μ/ρ values, highlighting the significance of selecting appropriate modifiers in the glass system for optimal gamma-ray shielding applications.

The findings indicate that the glass compositions 40TeO2 + 35B2O3 + 20MgO + 3.5Li2O + 1.5La2O3 and 20TeO2 + 40B2O3 + 10MgO + 20Li2O + 10La2O3 possess the maximum μ/ρ values, thereby suggesting their potential for effective gamma radiation shielding.

It is vital to acknowledge that elevated LAC values for certain mediums demonstrate their ability to effectively block incoming photons. This knowledge is key in the preparation of superior shielding glass materials.

In Figure 4, the profile of the LAC for the selected glass systems, which include TeO2 + B2O3 + MgO + Li2O + La2O3 is presented. The data indicates a reduction in the LAC for these glasses as the energy changes between 0.2 MeV and 15 MeV.

Figure 4.

The linear attenuation coefficients (cm2/g) for the TeO2 + B2O3 + MgO + Li2O + La2O3 glass system. The variation of LAC values with photon energy for various compositions has been illustrated graphically.

LAC results demonstrated that TBMLL40 achieved the highest attenuation when compared to the other prepared glass samples. This is primarily because TBMLL40 contains the largest amount of TeO2 contributing to its overall high density of ρ = 3.51 g/cm3. Furthermore, TBMLL20, with a density of 3.09 g/cm3, demonstrates the least amount of attenuation. Figure 2 illustrates the relationship between LAC and densities. This suggests that an increase in sample density correlates with higher MAC and LAC values, thereby enhancing the ability to attenuate photons in the chosen energy range. Consistent with expectations, the highest LAC observed for all samples tested occurs at 8.91 keV, with values of 391.448, 325.182, 353.279, and 409.847 cm−1. At 15 keV, the corresponding values are 98.139, 80.795, 87.788, and 101.981 cm−1.

It is generally acknowledged that the half-value layer (HVL) serves as a measure of a material’s ability to shield against radiation. In our current research, we evaluate the HVL values for all synthesized glasses using their attenuation coefficients within the photon energy spectrum of 0.00891 MeV to 15 MeV, as depicted in Figure 5. As illustrated in Figure 5, the data indicates that at lower photon energy, the half-value layer (HVL) across all compositions is quite minimal, measuring between 0.002 cm and 0.050 cm. The HVL values for the examined glasses remain nearly constant for photon energy levels below 0.1 MeV, followed by a significant increase in HVL values beyond this threshold. The highest HVL values were observed starting at 3 MeV, ranging from 5.513 cm to 6.238 cm.

Figure 5.

The half-value layer (cm) for the TeO2 + B2O3 + MgO + Li2O + La2O3 glass system. Graphical representation of HVL values in relation to photon energy for various glass compositions.

It should be emphasized that the glass made from 40TeO2 + 35B2O3 + 20MgO + 3.5Li2O + 1.5La2O3 has the lowest HVL values across all photon energies when compared to other glass compositions, owing to its higher density of 3.51 g/cm3. The half-value layer (HVL) measurements for TBLL20, TBLL30, TBLL35, and TBLL40 are as follows: at 0.2 MeV photon energy, the values are 0.868, 0.951, 0.897, and 0.807 cm. At 0.662 MeV, the values change to 2.941, 2.856, 2.760, and 2.617 cm. Lastly, at 2.0 MeV, the HVL values are 5.331, 5.114, 4.952, and 4.713 cm.

A shorter Mean Free Path (MFP) signifies a greater number of interactions between gamma rays and matter, which implies that a reduced distance between consecutive interactions enhances the shielding effectiveness against gamma rays. Figure 6 illustrates that the glass composition of 40TeO2 + 35B2O3 + 20MgO + 3.5Li2O + 1.5La2O3 demonstrates reduced MFP values in comparison to the other glasses analyzed in this study.

Figure 6.

The mean free path (cm) for the TeO2 + B2O3 + MgO + Li2O + La2O3 glass system. The variation of MFP values with photon energy for various compositions has been illustrated graphically.

Many of the Universe’s most impressive objects display peak emissivity at photon energies from 0.2 MeV to 100 MeV, including gamma-ray bursts, blazars, and pulsars. This energy band is particularly significant for directly examining the fundamental physical properties of these phenomena. It is also characterized by spectral features related to gamma-ray emissions produced by pion decay [29].

In the low energy range of 0.001–0.5 MeV, the photoelectric effect is the predominant interaction occurring within this spectrum. In the intermediate energy range of 0.5–4 MeV, Compton scattering is clearly the predominant interaction observed. In the high energy range of 4–10 MeV, the phenomenon of pair production can be detected [30].

The ability of glass to attenuate radiation can additionally be evaluated through its tenth value layer (TVL). It is commonly understood that materials with lower TVL values need less thickness to effectively shield against gamma radiation photons. The TVL measurements for the TeO2 + B2O3 + MgO + Li2O + La2O3 glasses are illustrated in Figure 7, indicating trends that mirror those seen in the HVL measurements shown in Figure 5. It is noted that the TVL increases as the incident photon energy becomes higher. In Figure 8, the correlation between the electron density values (Neff) of the studied glass systems and photon energy is presented [31]. This figure clearly demonstrates that the fluctuations in Neff exhibit a trend that is remarkably similar to that of Ceff, as shown in Figure 9.

Figure 7.

Tenth value layer (cm) for the TeO2 + B2O3 + MgO + Li2O + La2O3 glass system. Graphical representation of TVL values in relation to photon energy for various glass compositions.

Figure 8.

Effective electron density (electron/g) for the TeO2 + B2O3 + MgO + Li2O + La2O3 glass system. The variation of Neff values with photon energy in the range of 8.9 keV to 15 MeV for various compositions has been illustrated graphically.

Figure 9.

Effective conductivity (s/m) for the TeO2 + B2O3 + MgO + Li2O + La2O3 glass system. The variation of Ceff values with photon energy in the range of 8.9 keV to 15 MeV for various compositions has been illustrated graphically.

5.1 Chemical durability

The chemical durability of glass can be assessed through two primary mechanisms: leaching and etching. Leaching, or the ion-exchange mechanism, occurs in environments with relatively low pH, such as acidic or aqueous solutions, where H+ or H3O+ ions act as the aggressors. This process involves the exchange of mobile cationic ions present on the glass surface, such as Na+, K+, or Li+ (M+), with the ions from the leaching solution, specifically H+ or H3O+ [32].

The chemical durability of glass is primarily influenced by the composition of the host glass, along with additional factors such as the pH level of the leaching solution (whether neutral, acidic, or alkaline), the surface area of the glass, and the duration of the leaching process. The excellent chemical durability of the synthesized borosilicate glasses is primarily attributed to the robust structure of the borosilicate network. This network is composed of three structural units: trigonal BO3, tetrahedral BO4, and tetragonal TeO2 groups. Notably, the trigonal BO3 groups exhibit a higher solubility compared to the tetrahedral BO4 groups. The densely packed architecture of boro-tellurite is composed of trigonal BO3 and tetragonal TeO2 units, along with tetrahedral BO4 building blocks. This configuration enhances the glass’s resistance to radiation by obstructing the network and preventing the passage of photons through the glassy medium [32].

Given that the glass system has a high refractive index and strong thermal stability, the evaluation of the shielding properties of the prepared glasses reveals commendable performance when compared to standard commercial materials.

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6. Conclusions

The density values obtained through the recently introduced formula show a substantial increase in accuracy. This modified formula effectively decreases the error by roughly ±4%.

Various glass compositions within the TeO2 + B2O3 + MgO + Li2O + La2O3 system were synthesized, and their shielding characteristics were evaluated using Phy-X/PSD software. The assessment focused on parameters such as mass attenuation coefficient, linear attenuation coefficient, half-value layer, mean free path, tenth value layer, effective electron density, and conductivity. Higher mass attenuation coefficients were observed in the glass compositions of 40TeO2 + 35B2O3 + 20MgO + 3.5Li2O + 1.5La2O3 and 20TeO2 + 40B2O3 + 10MgO + 20Li2O + 10La2O3.

The analysis revealed that the HVL and MFP values of the examined glasses increase with higher photon energy, with the lowest values observed in the compositions of 40TeO2 + 35B2O3 + 20MgO + 3.5Li2O + 1.5La2O3 and 20TeO2 + 40B2O3 + 10MgO + 20Li2O + 10La2O3. Based on the findings of this study, it can be concluded that these specific glass compositions demonstrate superior shielding effectiveness against gamma radiation compared to others, attributed to their elevated mass attenuation coefficients and reduced HVL and MFP values.

References

  1. 1. Inaba S, Fujino S. Empirical equation for calculating the density of oxide glasses. Journal of the American Ceramic Society. 2010;93(1):217-220
  2. 2. Katubi KM, Alsulami RA, Albarqi MM, Alrowaili ZA, Kebaili I, Singh VP, et al. Radiation shielding efficiency of lead-tungsten-boron glasses with Sb, Al, and Bi against gamma, neutron and charge particles. Applied Radiation and Isotopes. 2024;204:111139-111139
  3. 3. Møller AP, Mousseau TA. Assessing effects of radiation on abundance of mammals and predator–prey interactions in chernobyl using tracks in the snow. Ecological Indicators. 2013;26:112-116
  4. 4. Mettler FA, Huda W, Yoshizumi TT, Mahesh M. Effective doses in radiology and diagnostic nuclear medicine: A catalog. Radiology. 2008;248(1):254-263
  5. 5. Kanngießer B, Malzer W, Reiche I. A new 3D micro X-ray fluorescence analysis set-up – First archaeometric applications. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms [Internet]. 2003;211(2):259-264. Available from: https://www.sciencedirect.com/science/article/pii/S0168583X03013211
  6. 6. Marguí E, Hidalgo M, Queralt I. Multielemental fast analysis of vegetation samples by wavelength dispersive X-ray fluorescence spectrometry: Possibilities and drawbacks. Spectrochimica Acta Part B: Atomic Spectroscopy. 2005;60(9–10):1363-1372
  7. 7. Farkas J. Irradiation for better foods. Trends in Food Science & Technology [Internet]. 2006;17(4):148-152. Available from: https://www.sciencedirect.com/science/article/abs/pii/S0924224405003511
  8. 8. Halliwell E, Couch C, Begum R, Li W, Maqbool M. Increase in linear attenuation coefficient by changing crystal structure of materials for radiation shielding and biomedical devices safety. Colloids and Surfaces A: Physicochemical and Engineering Aspects. 2021;622(March):1-6
  9. 9. Sayyed MI, Mhareb MHA, Kaky KM. Characterization of mechanical and radiation shielding features of borosilicate glasses doped with MoO3. SILICON. 2023;16(5):1955-1965
  10. 10. Kilicoglu O, Mehmetcik H. Science mapping for radiation shielding research. Radiation Physics and Chemistry. 2021;189:109721
  11. 11. Tamam N, Huwayz MA, Alrowaili ZA, Alwadai N, Katubi KM, Alqahtani MS, et al. Radiation attenuation of boro-tellurite glasses for efficient shielding applications. Applied Radiation and Isotopes. 2023;203:111080
  12. 12. Buckner CA, Lafrenie RM, Dénommée JA, Caswell JM, Want DA, Gan GG, et al. We are IntechOpen , the world ’ s leading publisher of open access books built by scientists , for scientists TOP 1%. Intech [Internet]. 2016;11(tourism):13. Available from: https://www.intechopen.com/books/advanced-biometric-technologies/liveness-detection-in-biometrics
  13. 13. Demir N, Kuluozturk ZN, Dal M, Aygün B. Investigation of gammaray shielding parameters of marbles. In: Mann KS, Singh VP, editors. Computational Methods in Nuclear Radiation Shielding and Dosimetry. New York: Nova Science Publishers, Inc.; 2020. pp. 293-312. ISBN 9781536186611
  14. 14. Tsoulfanidis N, Landsberger S. Measurement and Detection of Radiation. 5th ed. Boca Raton: CRC Press; 2021. DOI: 10.1201/9781003009849
  15. 15. McAlister DR. Gamma Ray Attenuation Properties of Common Shielding Materials [White Paper]. Univ Lane Lisle [Internet]; 2018. DOI: 10.1016/j.jnoncrysol.2014.08.003
  16. 16. Kaur P, Singh KJ, Thakur S. Evaluation of the gamma radiation shielding parameters of bismuth modified quaternary glass system. AIP Conference Proceedings. 2018;1953:3-6
  17. 17. Imheidat MA, KhHamad M, Naseer KA, Sayyed MI, Dwaikat N, Cornish K, et al. Radiation shielding, mechanical, optical, and structural properties for tellurite glass samples. Optik (Stuttg). 2022;268(August):169774. DOI: 10.1016/j.ijleo.2022.169774
  18. 18. Kurudirek M. Heavy metal borate glasses: Potential use for radiation shielding. Journal of Alloys and Compounds. 2017;727:1227-1236. DOI: 10.1016/j.jallcom.2017.08.237
  19. 19. El-Mallawany RAH, El-Mallawany RAH. Tellurite Glasses Handbook: Physical Properties and Data. 1st ed. Boca Raton: CRC Press; 2001. DOI: 10.1201/9781420042085
  20. 20. Şakar E, Özpolat ÖF, Alım B, Sayyed MI, Kurudirek M. Phy-X/PSD: Development of a user friendly online software for calculation of parameters relevant to radiation shielding and dosimetry. Radiation Physics and Chemistry. 2019:108496. DOI: 10.1016/j.radphyschem.2019.108496
  21. 21. Sayyed MI, El-Mallawany R. Shielding properties of (100-x)TeO2–(x)MoO3 glasses. Materials Chemistry and Physics. 2017;201:50-56. DOI: 10.1016/j.matchemphys.2017.08.035
  22. 22. Noguera O, Merle-Méjean T, Mirgorodsky AP, Thomas P, Champarnaud-Mesjard JC. Dynamics and crystal chemistry of tellurites. II. Composition- and temperature-dependence of the Raman spectra of x(TlO2) + (1-x)TeO2 glasses: Evidence for a phase separation? Journal of Physics and Chemistry of Solids. 2004;65(5):981-993
  23. 23. Barabash A, Barabash D, Pertsev V, Panfilov D. Polymer-composite materials for radiation protection. Advances in Intelligent Systems and Computing. 2019;983:352-360
  24. 24. Singh VP, Medhat ME, Shirmardi SP. Comparative studies on shielding properties of some steel alloys using Geant4, MCNP, WinXCOM and experimental results. Radiation Physics and Chemistry. 2015;106:255-260
  25. 25. Telzhammer V, Ozcan S, Gottschalk MG, Steeb H, Hodes GE, Guest PC, et al. Central and peripheral changes underlying susceptibility and resistance to social defeat stress – A proteomic profiling study. Diagnostics in Neuropsychiatry. 2015;1(1-4):1-7. DOI: 10.1016/j.dineu.2015.08.001
  26. 26. Sayyed MI. The impact of chemical composition, density and thickness on the radiation shielding properties of CaO–Al2O3–SiO2 glasses. Silicon [Internet]. 2023;15(18):7917-7926. DOI: 10.1007/s12633-023-02640-y
  27. 27. Bashter II. Calculation of radiation attenuation coefficients for shielding concretes. Annals of Nuclear Energy. 1997;24(17):1389-1401
  28. 28. Sayyed MI, Ersundu MÇ, Ersundu AE, Lakshminarayana G, Kostka P. Investigation of radiation shielding properties for MeO-PbCl2 -TeO2 (MeO = Bi2O3, MoO3, Sb2O3, WO3, ZnO) glasses. Radiation Physics and Chemistry. 2017;144:419-425
  29. 29. De Angelis A, Tatischeff V, Argan A, Brandt S, Bulgarelli A, Bykov A, et al. Gamma-ray astrophysics in the MeV range. Experimental Astronomy. 2021;51(3):1225-1254
  30. 30. Al-Buriahi MS, Mann KS. Radiation shielding investigations for selected tellurite-based glasses belonging to the TNW system. Materials Research Express. 2019;6(10):105206
  31. 31. Agar O, Sayyed MI, Tekin HO, Kaky KM, Baki SO, Kityk I. An investigation on shielding properties of BaO, MoO3 and P2O5 based glasses using MCNPX code. Results in Physics. 2018;2019(12):629-634
  32. 32. Hussein EMA, Shaban SE, Madbouly AM. Chemical durability and shielding study of borosilicate glass systems from solid municipal waste ash for radiation shielding applications. Optical and Quantum Electronics. 2024;56(4):1-24. DOI: 10.1007/s11082-023-06180-y

Written By

Praveen Kumar R., Susheela K. Lenkennavar, Kiran N. and Kiran D.S.

Submitted: 29 December 2024 Reviewed: 07 January 2025 Published: 29 April 2025