Abstract
Gamma-ray shielding properties of eight different metallic glasses based on CuxZr100-x: x = 35 (Cu35Zr65) − 70 (Cu70Zr30) were determined using Monte Carlo simulations and Phy-X/PSD software. A typical gamma-ray transmission setup has been modeled in MCNPX Monte Carlo code. The general trend of the linear attenuation coefficients (μ) was reported as (μ)Cu35Zr65 < (μ)Cu40Zr60 < (μ)Cu45Zr55 < (μ)Cu50Zr50 < (μ)Cu55Zr45 < (μ)Cu60Zr40 < (μ)Cu65Zr35 < (μ)Cu70Zr30. In terms of half value layer (HVL) values, the Cu35Zr65 sample has the highest value (2.984 cm) and the Cu70Zr30 sample has the lowest value (2.769 cm) at 8 MeV photon energy. The mean free path (MFP) values were 4.305 and 3.995 cm for Cu35Zr65 and Cu70Zr30 samples, respectively. Generally, MFP and HVL values of the studied glasses were reported as (MFP,HVL)Cu35Zr65 > (MFP,HVL)Cu40Zr60 > (MFP,HVL)Cu45Zr55 > (MFP,HVL)Cu50Zr50 > (MFP,HVL)Cu55Zr45 > (MFP,HVL)Cu60Zr40 > (MFP,HVL)Cu65Zr35 > (MFP,HVL)Cu70Zr30 for all photon energy range. The Cu70Zr30 sample showed maximum values of both the effective conductivity (C eff) and effective electron density (N eff). In addition, the Cu70Zr30 sample has minimum exposure and energy absorption buildup factor (EBF and EABF) values at all studied gamma-ray energies. The results revealed that the Cu70Zr30 sample has superior attenuation properties among all studied samples.
1 Introduction
Bulk metallic glasses (BMGs), also known as amorphous metals, have been studied since they were first produced in the 1960s. Since then, different types of research on their physical and structural characteristics, as well as production changes, have been conducted. In comparison to traditional metals, where atoms are arranged in a repeated pattern of crystals or grains of various sizes and shapes, BMGs have a random and disordered atomic structure. BMG’s competitive physical characteristics such as strength, durability, hardness, elasticity, corrosion and wear resistance are enhanced by this amorphous structure, which is free of grain defects [1]. After a breakthrough at the end of the 1980s and the beginning of the 1990s, BMGs drew the attention of the materials science community. Using various casting and water-cooling processes, the high glass-forming ability (GFA) of some alloys permitted the creation of BMGs up to about 80 mm in size. New BMG forming alloys based on Zr, La, Ti, Ni, Pd, Mg, Al, Fe, and Cu have been developed during the past 15 years. Due to their low critical cooling rates of 102–100 K/s, these multicomponent alloys may be cast in a glassy state (in mm or cm) using a copper mold. BMGs enable researchers to study the peculiar features of metallic glasses. GFA is associated with a highly reduced glass transition temperature T rg (the ratio of the glass transition temperature T g to the liquid temperature T l), a favorable negative enthalpy of mixing of the constituents, and small enthalpy variations between the undercooled liquid and competing crystalline phases. On the other hand, BMGs have sparked interest due to the lack of a crystalline lattice and defects such as dislocations. These materials show a peculiar deformation mechanism, resulting in high strength, extreme stiffness, robust wear resistance, and large elastic deformation [2,3,4,5]. Structural applications of BMGs are severely constrained by their poor ductility and macroscopic strain-softening properties at ambient temperature, particularly under tensile loads. To address this brittleness, BMG composites with a crystalline phase spread across a range of length scales inside the glassy matrix have been created using a variety of glass-forming techniques. With properly adjusted formulations and microstructures, the durability and ductility of some BMG composites can be greatly enhanced even under strain [6,7]. BMGs could recently be made for some specific compositions in the binary Cu–Zr system. CuZr-based BMGs have been extensively studied in recent years due to their improved tensile properties and work-hardening performance. Moreover, for binary and ternary Cu-based BMGs, exceptional plasticity was observed. These discoveries rekindled interest in structural and shielding studies of the Cu–Zr system. Cu–Zr glass can be made in a wide variety of compositions, as previous research has shown. In addition to these studies, the radiation shielding properties of BMGs can be investigated by taking into account their broad range of uses and potential applications [5,6,7]. The efficacy of atomic shielding systems for gamma rays and high-energy X-rays is well understood to be dependent on the atomic number and density of the shielding material. For high-energy X-rays and gamma-rays, a denser shielding substance with a higher atomic number is preferable. The major drawback of lead-based radiation shielding structures is their toxicity and lack of structural integrity. Other typical shielding materials, such as concrete, have drawbacks, such as cracking over time, and the presence of water in concrete reduces the material’s density and structural strength. Additionally, concrete is naturally opaque, making visibility difficult in radiation facilities, where the observation of the patient or source is critical. As a consequence, new radiation shielding systems developed must be corrosion-resistant, biocompatible, and capable of being shaped into slim, compact designs with excellent structural integrity and endurance. Due to their unique features, BMGs have been suggested for use as radiation shields. BMGs have extremely high densities and high atomic numbers that make them effective in blocking high-energy radiation like gamma and X-rays [7,8]. The radiation attenuation parameters of heavy metallic glasses researched in the literature encouraged us to conduct a study on the subject and to perform a detailed examination of several glass types. The primary objective of this investigation was to observe changes in gamma-ray shielding properties as a function of the amount of heavy metal oxide added to the glass samples and to determine at what additive ratios these changes reached their greatest correspondingly. Accordingly, gamma-ray shielding properties of very high-density CuxZr100x metallic glasses (x = 35–70) were determined using Phy-X/PSD software [9] and MCNPX [10] (version 2.7.0) in a wide range of energies between 0.015 and 15 MeV.
2 Materials and methods
Eight distinct CuxZr100-x metallic glass systems [2] were comprehensively investigated in this work in terms of their gamma-ray shielding capabilities, effective conductivity, and buildup factors (BUFs). In the reference study, material densities of glass samples were reported as 7.01, 7.17, 7.26, 7.33, 7.47, 7.53, 7.75, and 7.86 g/cm3 for sample codes Cu35Zr65, Cu40Zr60, Cu45Zr55, Cu50Zr50, Cu55Zr45, Cu60Zr40, Cu65Zr35, and Cu70Zr35, respectively (see Table 1). The calculated nuclear radiation shielding parameters will be discussed in this section, along with technical information.
Sample codes, composition, elemental weight fractions, and density
| Code | Composition wt% | Density (g/cm3) | |
|---|---|---|---|
| Cu | Zr | ||
| Cu35Zr65 | 34.77 | 65.23 | 7.01 |
| Cu40Zr60 | 39.88 | 60.12 | 7.17 |
| Cu45Zr55 | 44.94 | 55.06 | 7.26 |
| Cu50Zr50 | 49.86 | 50.14 | 7.33 |
| Cu55Zr45 | 55.14 | 44.86 | 7.47 |
| Cu60Zr40 | 59.92 | 40.08 | 7.53 |
| Cu65Zr35 | 64.92 | 35.08 | 7.75 |
| Cu70Zr30 | 69.93 | 30.07 | 7.86 |
2.1 Nuclear radiation shielding properties
To simplify the mass attenuation coefficient, it is essential to understand the Lambert–Beer law [11,12], which is shown in equation (1):
where I 0 is the original energy of the beam, μ is the linear attenuation coefficient, t is the absorber thickness, and I is the gamma-ray intensity after transit through the absorber.
The mass attenuation coefficient (μ m) is the ratio of the linear attenuation coefficient to the density. It is generally represented in cm2/g [13,14,15,16,17,18] and is computed using the following equation:
where μ is the linear attenuation coefficient and ρ is the density of the sample.
Equation (3) was used to calculate the values of μ m using the Py-MLBUF platform:
where w i is the weight fraction of the ith constituent of the element and ρ is the density of the sample.
The mean free path (MFP) is defined as the average distance a photon can travel between two successive interactions within a material [19], and can be calculated using equation (4):
After traveling 1 MFP through a shielding material in perfect narrow-beam geometry, the power of monoenergetic gamma rays is reduced by about 37%. The optical thickness (OT), a dimensionless quantity, is calculated by multiplying the linear attenuation coefficient by the distance in cm between the point source and the detector. The OT depicts the number of MFP lengths covered by gamma photons as they travel through the shield. The half value layer (HVL) is the thickness of material with a transmitted radiation intensity equal to half that of the incoming radiation, while the tenth value layer (TVL) is the thickness of material with a beam intensity equal to one-tenth of its original value [20]. HVL and TVL may be determined using equations (5) and (6):
Equation (7) relates the effective conductivity C eff (s/m) of a shielding material for attenuation at room temperature (300 K) to the effective number of electrons N eff:
where ρ, e, and m e are the density of shielding materials (g/cm3), the charge on an electron (C), and the electron’s rest mass (kg), respectively. τ depicts the electron’s relaxation time and is calculated using equation (8):
where h is the Planck constant and k is the Boltzmann constant.
The effective atomic number (Z eff) is a critical parameter in radiation sciences. It can be utilized to describe how complex shielding materials strengthen their shielding capabilities. The direct method was used in this study to calculate the effective atomic number by comparing the atomic and electronic cross sections:
where f i , A i , and Z j are the fractions by mole, atomic weight, and the atomic number of the ith constituent element, respectively.
Incoherent scattering is the only way to determine the equivalent atomic number (Z eq) of the shielding material. Z eq values are used to calculate BUFs.
The Z eq values in this work were obtained using the interpolation method, as displayed in equation (10):
where the ratio R is the determining factor for the equivalent atomic number, for particular photon energy,
The atomic numbers Z 1 and Z 2 of the elements correspond to their respective R 1 and R 2 ratios.
The BUF is a multiplier that takes into account the contributions of scattered photons to the corrected response to uncollided photons. In other words, it is the number of incoming photons divided by the total number of photons. The ANS standard was developed for the purpose of calculating gamma-ray BUFs for a point isotropic source operating at energies ranging from 0.015 to 15 MeV. In the energy absorption buildup factor (EABF), the quantity of interest is the amount of energy absorbed or contained in the interacting substance. Geometric progression (G–P) fitting is often used to record EABFs. After determining the Z eq values, the five G–P fitting parameters for the elements (b, a, c, and d Xk) are retrieved from the ANS-standard database, which contains a variety of elements with energies ranging from 0.015 to 15 MeV and OT of 40 MFP. The G–P fitting parameters for the glass materials were calculated using the interpolation approach. The exposure accumulation factor refers to the amount of radiation in the air after it passes through the shielding material (EBF). EABF and EBF are calculated using equations (12–14) for single-layered gamma-ray shielding enclosures (GSEs) with OT up to 100 MFP and energy between 0.015 and 15 MeV.
where E, x, and B denote incoming photon energy, penetration depth in MFP, and accumulation factor at 1 MFP, respectively, and K denotes the photon-dose multiplication factor.
2.2 Monte Carlo simulations using MCNPX (version 2.7.0)
According to the literature review, the relevance of mathematical tools and simulation techniques in radiation sciences is steadily expanding [21,22,23,24,25,26]. This is due to various physical constraints and the possibility of adverse consequences in experimental radiation investigations. On the other hand, authorized institutions should accredit radiation facilities in order to comply with safety regulations. As a result, enhanced simulation methods may be a viable option for increasing the consistency of the experimental phase and lowering the total cost of research. As such, many well-known Monte Carlo simulation-based radiation transportation codes, such as MCNP, Geant4, EGSnrc, and FLUKA, provide well-structured platforms for developing various sorts of solutions for radiation transportation-related investigations. Among the abovementioned codes, MCNPX [12] is well-known for its user-friendliness and reliability, as well as its promising technological aspects. The mass attenuation coefficients of the BMGs under discussion were determined in this inquiry using version 2.7.0 of the MCNPX general-purpose Monte Carlo method. The first step included the development of a generic gamma-ray transmission system based on experimental research. The two- and three-dimensional representations of the MCNPX code’s intended gamma-ray transmission arrangement are shown in Figure 1. In a lead (Pb) block, a point isotropic gamma-ray source has been established. Following that, an attenuator between the point isotropic source and detection field has been established. It is worth noting that the attenuator material was chosen based on the elemental characteristics of the investigated glasses (see Table 1). The BMGs’ elemental characteristics have been precisely described in the material (Mn) card of the MCNPX INPUT file. Finally, simulation was initiated for a total of 108 particle histories. It should be mentioned that each glass sample was examined for gamma-ray energies ranging from 0.015 to 15 MeV. The simulation results indicated that the relative inaccuracy for each track was less than 1%.
3-D model of the modeled MCNPX simulation setup (obtained from VISED_X_22S).
3 Results and discussions
In this study, eight different BMGs were characterized in terms of their gamma-ray attenuation competencies. The densities of Cu35Zr65, Cu40Zr60, Cu45Zr55, Cu50Zr50, Cu55Zr45, Cu60Zr40, Cu65Zr35, and Cu70Zr30 samples are shown in Figure 2. As seen in the figure, the glass density is increased from 7.01 to 7.86 g/cm3. The Cu70Zr30 sample with the greatest content of Cu had the highest glass density. Given that the linear attenuation coefficient is a density-dependent characteristic, it is assumed that a direct relationship exists between the density and the linear attenuation coefficient values, and hence, the amount of Cu contribution. The variation of linear attenuation coefficients (/cm) as a function of incoming photon energy (MeV) is shown in Figure 3. As can be seen, as the photon energy increased, linear attenuation coefficients decreased. The largest linear attenuation coefficients were observed in the low-energy region, where the photoelectric effect dominates the majority of photon–matter interactions [27,28,29,30,31,32]. However, when the glass densities are changed gradually, no significant variations in the linear attenuation coefficients are seen. We noticed an interesting impact of Cu on the photon resistance of glass samples at varying energies. Our results reveal that the Cu70Zr30 sample, which has the greatest concentration of Cu, has the maximum linear attenuation coefficients for all photon energies entering. This is explained by the Cu70Zr30 sample’s glass density, which included the largest quantity of studied glasses. For example, linear attenuation coefficients were reported as 0.409, 0.419, 0.425, 0.429, 0.438, 0.442, 0.455, and 0.462/cm for Cu35Zr65, Cu40Zr60, Cu45Zr55, Cu50Zr50, Cu55Zr45, Cu60Zr40, Cu65Zr35, and Cu70Zr30 samples at 1 MeV photon energy, respectively.
Variation of glass densities (g/cm3).
Variation of linear attenuation coefficients (1/cm) of investigated glasses as a function of incident photon energy (MeV).
In Figure 3, a closer look on the variation trend of linear attenuation coefficients has also been provided as 0.232, 0.236, 0.238, 0.239, 0.242, 0.243, 0.248, and 0.250/cm for Cu35Zr65, Cu40Zr60, Cu45Zr55, Cu50Zr50, Cu55Zr45, Cu60Zr40, Cu65Zr35, and Cu70Zr30 samples at 8 MeV photon energy, respectively. Meanwhile, another critical statistic for gamma-ray shielding, namely mass attenuation coefficients (μ m), was calculated. Figure 4 depicts the shifting trend in mass attenuation coefficients as a function of incoming photon energy. In general, it was discovered that mass attenuation coefficients behave differently from linear attenuation coefficients. This is due to the density-independent character of the mass attenuation coefficient parameter. While increasing the Cu contribution improved the density of BMGs, it also lowered the contribution of Zr with a higher atomic number from Cu35Zr65 to Cu70Zr30. Considering the concept of mass attenuation coefficient, which is density-independent, it can be said that there is an inverse correlation between the linear attenuation coefficients and mass attenuation coefficients of the BMGs at the same energy values. The linear attenuation coefficients of the BMGs at 8 MeV photon energy have been listed above. Our results showed that the mass attenuation coefficients of the studied BMGs have an inverse trend at the same energy level. For example, the mass attenuation coefficients of the BMGs were reported as 0.0331, 0.0329, 0.0328, 0.0326,0.0324, 0.0322, 0.0320, and 0.0318 cm2/g for Cu35Zr65, Cu40Zr60, Cu45Zr55, Cu50Zr50, Cu55Zr45, Cu60Zr40, Cu65Zr35, and Cu70Zr30 samples at 8 MeV photon energy, respectively. The term HVL (also known as T 1/2) is significant in radiation shielding research since it allows for the quantification of the material thickness required to halve the initial gamma-ray intensity [33,34,35,36]. This is because radiation studies necessitate that shielding needs be determined in advance depending on the kind and energy of the radiation used. As a consequence, the quantity of the HVL required for each kind of prospective shielding material should be determined in terms of a more complete understanding of the gamma-ray attenuation capabilities during the incoming gamma ray’s contact with the attenuator specimen. Variation of HVL (cm) values of investigated glasses as a function of incident photon energy (MeV) is shown in Figure 5. As indicated in the Materials and Methods section, the linear attenuation coefficients and HVL quantities have an inverse relationship. As a result, it is reasonable to anticipate that the minimum HVL values would be found in the sample with the maximum linear attenuation coefficient values. Fortunately, our results indicated that the Cu70Zr30 sample with the highest glass density and linear attenuation coefficients has the minimum HVL values. For example, HVLs were reported to be 2.984, 2.934, 2.914, 2.902, 2.865, 2858, 2.792, and 2.769 cm for Cu35Zr65, Cu40Zr60, Cu45Zr55, Cu50Zr50, Cu55Zr45, Cu60Zr40, Cu65Zr35, and Cu70Zr30 samples at 8 MeV photon energy, respectively. The variations in the TVL (cm) values of the examined glasses as a function of incoming photon energy are shown in Figure 6. Similar to the behavior of the HVLs in BMGs, a direct relationship between the glass density and TVL values has also been reported. In other words, increasing glass density has influenced not only the material thickness needed to halve the incoming radiation intensity but also the material thickness necessary to reduce the incident radiation intensity by one-tenth. The MFP is the route taken by a photon through a substance without colliding [33,37,38]. Therefore, it can be said that a lower distance in MFP values is a clear indicator for superior attenuation properties. Figure 7 depicts the variation of MFP (cm) values of investigated glasses as a function of incident photon energy (MeV). As mentioned above for previous attenuation properties, the Cu70Zr30 sample with the highest glass density was also reported with its minimum MFP values. For instance, MFP values (cm) were reported as 4.305, 4.233, 4.204, 4.187, 4.133, 4.123, 4.029, and 3.995 for Cu35Zr65, Cu40Zr60, Cu45Zr55, Cu50Zr50, Cu55Zr45, Cu60Zr40, Cu65Zr35, and Cu70Zr30 samples at 8 MeV photon energy, respectively. Figure 8 illustrates the variation of the effective atomic number (Z eff) values of investigated metallic glasses as a function of incident photon energy (MeV). From Figure 8, one can observe that the sample Cu35Zr65 has the maximum values of Z eff, while Cu70Zr30 sample has the minimum values of Z eff. This is due to the fact that with the increasing amount of copper ions (Z = 29) and decreasing amount of zirconium ions (Z = 40), Z eff will be decreased. Figure 9 shows the variation of the effective electron density (N eff) values of the investigated metallic glasses as a function of incident photon energy (MeV). It is clear that the trend of N eff is inverse for the Z eff, where the Cu35Zr65 sample has the minimum values of N eff, while the Cu70Zr30 sample has the maximum values of N eff. This trend of N eff can be attributed to the PE process. In the photon energy zone from 0.1 to 1 MeV, a quick decrease in the N eff values was observed in all investigated samples, and this trend was related to the CS process, which was dominant in this region. In the energy zone greater than 2 MeV, an increase in the N eff values was observed and attributed to the PP process, which was dominant in this region. Figure 10 depicts the variation of effective conductivity (C eff) values of the investigated glasses as a function of incident photon energy (MeV). As seen in Figure 10, the trend of C eff of all investigated samples is similar to that of N eff, where the C eff is directly proportional to N eff as in equation (7). The BUF is required for an accurate evaluation of gamma attenuation, although it has the potential to degrade the measurement quality. Gamma-ray measurement is required in nuclear technology since it is used in a variety of applications including industry, medicine, agriculture, education, research, and defense applications. It is also required for the building of radiation protective structures to protect human health from radiation exposure. When gamma radiation travels through the shielding material, it generates two forms of radiation that may be found either within or outside the shield: uncollided photons and colliding photons. Uncollided photons are the most common type of radiation found inside the shield. Consequently, the accumulation factor is an extremely important parameter for gamma-ray measurements. A particle count is defined as the ratio of the total number of particles at a point to the total number of particles that have not collided at that site at a certain time. Figures 11 and 12 show the wide range of EBF and EABF values observed across all glass samples. Gamma rays absorb most of their energy in the low and high energy levels, where the majority of absorption occurs [39–43]. Consequently, the EBF values in the Compton area are among the highest in the low-energy zone. Our results showed that the Cu70Zr30 sample has the minimum EBF and EABF values at all gamma-ray energies studied.
Variation of mass attenuation coefficients (cm2/g) of investigated glasses as a function of incident photon energy (MeV).
Variation of HVL (cm) values of investigated glasses as a function of incident photon energy (MeV).
Variation of TVL (cm) values of investigated glasses as a function of incident photon energy (MeV).
Variation of MFP (cm) values of investigated glasses as a function of incident photon energy (MeV).
Variation of effective atomic number (Z eff) values of investigated glasses as a function of incident photon energy (MeV).
Variation of effective electron number (N eff) values of investigated glasses as a function of incident photon energy (MeV).
Variation of effective conductivity (C eff) values of investigated glasses as a function of incident photon energy (MeV).
Variation of exposure buildup factor (EBF) values of glasses at different MFP values (from 0.5 to 40 MFP) as a function of incident photon energy (MeV).
Variation of EABF values of glasses at different MFP values (from 0.5 to 40 MFP) as a function of incident photon energy (MeV).
4 Conclusion
In the present research, the nuclear shielding properties including the effective conductivity and BUFs of eight different CuxZr100-x: x = 35 (Cu35Zr65) − 70 (Cu70Zr30) in steps of 5 wt% metallic glass systems have been studied. The density of samples was varied from 7.01 g/cm3 for the Cu35Zr65 sample and 7.86 g/cm3 for the Cu70Zr30 sample. The studied nuclear radiation shielding parameters were calculated via MCNPX simulation code and the Phy-x PSD software. The results reveal that the Cu70Zr30 sample with the greatest Cu concentration and lowest Zr content has the maximum linear attenuation coefficient (μ) for all photon energies entering, while the Cu35Zr65 (low Cu and high Zr) sample has the minimum value. The general trend of the μ value was (μ)Cu35Zr65 < (μ)Cu40Zr60 < (μ)Cu45Zr55 < (μ)Cu50Zr50 < (μ)Cu55Zr45 < (μ)Cu60Zr40 < (μ)Cu65Zr35 < (μ)Cu70Zr30. As the mass attenuation coefficient (μ m) is density-independent, it has the trend (μ m)Cu35Zr65 > (μ m)Cu40Zr60 > (μ m)Cu45Zr55 > (μ m)Cu50Zr50 > (μ m)Cu55Zr45 > (μ m)Cu60Zr40 > (μ m)Cu65Zr35 > (μ m)Cu70Zr30 for the studied metallic glasses. Our results indicated that the glasses studied reported HVL (in cm) values of 2.984, 2.934, 2.914, 2.902, 2.865, 2858, 2.792, and 2.769 cm for Cu35Zr65, Cu40Zr60, Cu45Zr55, Cu50Zr50, Cu55Zr45, Cu60Zr40, Cu65Zr35, and Cu70Zr30 samples at 8 MeV photon energy, respectively. The MFP (in cm) has the same trend of HVL values of 4.305, 4.233, 4.204, 4.187, 4.133, 4.123, 4.029, and 3.995 cm for all studied samples Cu35Zr65, Cu40Zr60, Cu45Zr55, Cu50Zr50, Cu55Zr45, Cu60Zr40, Cu65Zr35, and Cu70Zr30 at 8 MeV photon energy, respectively. The Cu70Zr30 sample possessed the maximum values of both the effective conductivity (C eff) and effective electron density (N eff). The results showed that the Cu70Zr30 sample has the minimum EBF and EABF values at all gamma-ray energies studied.
Acknowledgements
The authors thank the “Dunarea de Jos” University of Galati, Romania, for the APC support.
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Funding information: This work was performed under Princess Nourah bint Abdulrahman University Researchers Supporting Project Number (PNURSP2022R149), Princess Nourah bint Abdulrahman University, Riyadh, Saudi Arabia. The authors express their sincere gratitude to Princess Nourah bint Abdulrahman University.
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Author contributions: Conceptualization: H.O.T., A.B., H.M.H.Z., and S.A.M.I.; methodology: G.K., H.O.T.; software: H.O.T., G.L., H.M.H.Z., and A.E.; validation: S.A.M.I., Y.S.R., and A.E.; formal analysis: G.K., Y.S.R., H.M.H.Z., and G.S.; investigation: G.K. and H.O.T.; resources: G.K., G.S., and A.B.; data curation: S.A.M.I. and A.E.; writing – original draft preparation: H.O.T., G.S., G.L., Y.S.R., and A.W.; writing – review and editing: H.M.H.Z., S.A.M.I., and A.E.; visualization: Y.S.R. and G.S.; supervision: H.M.H.Z. and A.B.; project administration: H.O.T. and S.A.M.I; funding acquisition: A.E. All authors have read and agreed to the published version of the manuscript.
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Conflict of interest: The authors declare no conflict of interest.
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Ethical approval: The conducted research is not related to either human or animal use.
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Data availability statement: The data presented in this study are available on request from the corresponding author.
References
[1] Şekerci M , Özdoğan H , Kaplan A . An investigation on gamma-ray shielding properties of Zr-based bulk metallic glasses. HNPS Proc. 2020;27:48. 10.12681/hnps.2477.Search in Google Scholar
[2] Mattern N , Schöps A , Kühn U , Acker J , Khvostikova O , Eckert J . Structural behavior of CuxZr100−x metallic glass (x = 35−70). J Non-Cryst Solids. 2008;354(10–11):1054–60.10.1016/j.jnoncrysol.2007.08.035Search in Google Scholar
[3] Louzguine-Luzgin D , Inoue A . Bulk metallic glasses. Handbook of magnetic materials. 2013;21:131–71. 10.1016/B978-0-444-59593-5.00003-9.Search in Google Scholar
[4] Ding J , Liu Z , Wang H , Zhang T . Large-sized CuZr-based bulk metallic glass composite with enhanced mechanical properties. J Mater Sci Technol. 2014;30(6):590–4.10.1016/j.jmst.2014.01.014Search in Google Scholar
[5] Inoue A . Stabilization of metallic supercooled liquid and bulk amorphous alloys. Acta Mater. 2000;48(1):279–306.10.1016/S1359-6454(99)00300-6Search in Google Scholar
[6] Liu Z , Li R , Liu G , Su W , Wang H , Li Y , et al. Microstructural tailoring and improvement of mechanical properties in CuZr-based bulk metallic glass composites. Acta Mater. 2012;60(6–7):3128–39.10.1016/j.actamat.2012.02.017Search in Google Scholar
[7] Pauly S , Liu G , Gorantla S , Wang G , Kühn U , Kim D , et al. Criteria for tensile plasticity in Cu–Zr–Al bulk metallic glasses. Acta Mater. 2010;58(14):4883–90.10.1016/j.actamat.2010.05.026Search in Google Scholar
[8] Stevick J , Waniuk T , Pham Q . Radiation shielding structures. California, US: World Intellectual Property organization; 2013.Search in Google Scholar
[9] Şakar E , Özpolat Ö , Alım B , Sayyed M , Kurudirek M . Phy-X/PSD: development of a user friendly online software for calculation of parameters relevant to radiation shielding and dosimetry. Radiat Phys Chem. 2020;166:108496.10.1016/j.radphyschem.2019.108496Search in Google Scholar
[10] Computer Code Collection RS. MCNPX User’s Manual Version 2.4.0. Monte Carlo N-Particle Transport Code System for Multiple and High Energy Applications. 2002.Search in Google Scholar
[11] Mostafa AM , Zakaly HM , Al-Ghamdi SA , Issa SA , Al-Zaibani M , Ramadan RM , et al. PbO–Sb2O3–B2O3–CuO glassy system: evaluation of optical, gamma and neutron shielding properties. Mater Chem Phys. 2021;258:123937.10.1016/j.matchemphys.2020.123937Search in Google Scholar
[12] Issa SA , Zakaly HM , Pyshkina M , Mostafa MY , Rashad M , Soliman TS . Structure, optical, and radiation shielding properties of PVA–BaTiO3 nanocomposite films: an experimental investigation. Radiat Phys Chem. 2020;180:109281.10.1016/j.radphyschem.2020.109281Search in Google Scholar
[13] Tekin HO , Singh VP , Manici T . Effects of micro-sized and nano-sized WO3 on mass attenuation coefficients of concrete by using MCNPX code. Appl Radiat Isot. 2017;121:122–5.10.1016/j.apradiso.2016.12.040Search in Google Scholar PubMed
[14] Tekin HO , Kavaz E , Altunsoy EE , Kamislioglu M , Kilicoglu O , Agar O , et al. Characterization of a broad range gamma-ray and neutron shielding properties of MgO-Al2O3-SiO2-B2O3 and Na2O-Al2O3-SiO2 glass systems. J Non-Cryst Solids. 2019;518:92–102.10.1016/j.jnoncrysol.2019.05.012Search in Google Scholar
[15] Rammah YS , Olarinoye IO , El-Agawany FI , El-Adawy A , Gamal A , Yousef ES . Elastic moduli, photon, neutron, and proton shielding parameters of tellurite bismo-vanadate (TeO2–V2O5–Bi2O3) semiconductor glasses. Ceram Int. 2020;46(16):25440–52.10.1016/j.ceramint.2020.07.014Search in Google Scholar
[16] Rammah YS , Sayyed MI , Ali AA , Tekin HO , El-Mallawany R . Optical properties and gamma-shielding features of bismuth borate glasses. Appl Phys, A Mater Sci Process. 2018;124(12):1–9.10.1007/s00339-018-2252-7Search in Google Scholar
[17] Zakaly HM , Abouhaswa AS , Issa SA , Mostafa MY , Pyshkina M , El-Mallawany R . Optical and nuclear radiation shielding properties of zinc borate glasses doped with lanthanum oxide. J Non-Cryst Solids. 2020;543:120151.10.1016/j.jnoncrysol.2020.120151Search in Google Scholar
[18] Zakaly HM , Ashry A , El-Taher A , Abbady AG , Allam EA , El-Sharkawy RM , et al. Role of novel ternary nanocomposites polypropylene in nuclear radiation attenuation properties: in-depth simulation study. Radiat Phys Chem. 2021;188:109667.10.1016/j.radphyschem.2021.109667Search in Google Scholar
[19] Zakaly HM , Rashad M , Tekin HO , Saudi HA , Issa SA , Henaish AM . Synthesis, optical, structural and physical properties of newly developed dolomite reinforced borate glasses for nuclear radiation shielding utilizations: an experimental and simulation study. Opt Mater. 2021;114:110942.10.1016/j.optmat.2021.110942Search in Google Scholar
[20] Saudi HA , Zakaly HH , Issa SM , Tekin HO , Hessien MM , Rammah YS , et al. Fabrication, FTIR, physical characteristics and photon shielding efficacy of CeO2/sand reinforced borate glasses: experimental and simulation studies. Radiat Phys Chem. 2022;191:109837. 10.1016/j.radphyschem.2021.109837.Search in Google Scholar
[21] Akkurt I , Malidarre RB . Gamma photon-neutron attenuation parameters of marble concrete by MCNPX code. Radiat Eff Defects Solids. 2021;176(9–10):906–18.10.1080/10420150.2021.1975708Search in Google Scholar
[22] Akkurt I , Malidarreh PB , Malidarre RB . Simulation and prediction of the attenuation behavior of the KNN-LMN based lead free ceramics by FLUKA code and artificial neural network (ANN) – based algorithm. Env Technol. 2021;1–15. 10.1080/09593330.2021.2008017.Search in Google Scholar PubMed
[23] Akkurt I , Tekin HO . Radiological parameters for bismuth oxide glasses using Phy-X/PSD software. Emerg Mater Res 9-. 2020;3:1020–7. 10.1680/jemmr.20.00209.Search in Google Scholar
[24] Rammah YS , Kumar A , Abdel-Azeem Mahmoud K , El-Mallawany R , El-Agawany FI , Susoy G , et al. SnO-reinforced silicate glasses and utilization in gamma-radiation-shielding applications. Emerg Mater Res. 2020;9(3):1000–8. 10.1680/jemmr.20.00150.Search in Google Scholar
[25] Tekin HO , Issa SAM , Mahmoud KA , Agawany FI , Rammah YS , Susoy G , et al. Nuclear radiation shielding competences of Barium (Ba) reinforced borosilicate glasses. Emerg Mater Res. 2020;9(4):1131–44. 10.1680/jemmr.20.00185.Search in Google Scholar
[26] Akkurt I , Tekin HO , Mesbahi A . Calculation of detection efficiency for the gamma detector using MCNPX. Acta Phys Polonica A. 2015;128(2B):332–4. 10.12693/APhysPolA.128.B-332.Search in Google Scholar
[27] Issa SAM , Tekin HO , Saddeek YB , Sayyed MI . Effect of Bi2O3 content on mechanical and nuclear radiation shielding properties of Bi2O3-MoO3-B2O3-SiO2-Na2O-Fe2O3 glass system. Results Phys. 2019;13:102165.10.1016/j.rinp.2019.102165Search in Google Scholar
[28] Sayyed , MI , Issa SAM , Tekin HO , Saddeek YB . Comparative study of gamma ray shielding and elastic properties of BaO–Bi2O3–B2O3 and ZnO–Bi2O3–B2O3 glass systems. Mater Chem Phys. 2018;217:11–22.10.1016/j.matchemphys.2018.06.034Search in Google Scholar
[29] Nasser KA , Marimuthu K , Al-Buriahi MS , Amani A , Tekin HO . Influence of Bi2O3 concentration on barium-telluro-borate glasses: Physical, structural and radiation-shielding properties. Ceram Int. 2020;47(1):329–40.10.1016/j.ceramint.2020.08.138Search in Google Scholar
[30] Kilicoglu O , Tekin HO . Bioactive glasses and direct effect of increased K2O additive for nuclear shielding performance: a comparative investigation. Ceram Int. 2020;46(2):1323–33.10.1016/j.ceramint.2019.09.095Search in Google Scholar
[31] Gaikwad AK , Obaid SS , Tekin HO , Agar O , Sayyed MI . Experimental studies and Monte Carlo simulations on gamma ray shielding competence of (30 + x)PbOe10WO3e 10Na2O−10MgO – (40-x)B2O3 glasses. Prog Nucl Energy. 2019;119:103047.10.1016/j.pnucene.2019.103047Search in Google Scholar
[32] Mahmoud IS , Shams AMI , Saddek YB , Tekin HO , Kilicoglu O , Alharbi T , et al. Gamma, neutron shielding and mechanical parameters for vanadium lead vanadate glasses. Ceram Int. 2019;45:14058–72.10.1016/j.ceramint.2019.04.105Search in Google Scholar
[33] Almisned G , Zakaly HM , Issa SA , Ene A , Kilic G , Bawazeer O , et al. Gamma-ray protection properties of bismuth-silicate glasses against some diagnostic nuclear medicine radioisotopes: a comprehensive study. Materials (Basel). 2021;14(21):6668.10.3390/ma14216668Search in Google Scholar PubMed PubMed Central
[34] Almisned G , Tekin HO , Zakaly HMH , Issa SAM , Kilic G , Saudi HA , et al. Fast neutron and gamma-ray attenuation properties of some HMO tellurite-tungstate-antimonate glasses: impact of Sm3+ ions. Appl Sci. 2021;11(21):10168. 10.3390/app112110168.Search in Google Scholar
[35] Ilik E , Kavaz E , Kilic G , Issa SAM , Zakaly HMH , Tekin HO . A closer-look on Copper (II) oxide reinforced Calcium-Borate glasses: Fabrication and multiple experimental assessment on optical, structural, physical, and experimental neutron/gamma shielding properties. Ceram Int. 2021. 10.1016/j.ceramint.2021.11.229.Search in Google Scholar
[36] ALMisned G , Kilic G , Ilik E , Issa SAM , Zakaly HMH , Badawi A , et al. Structural characterization and Gamma-ray attenuation properties of rice-like α-TeO2 crystalline microstructures (CMS) grown rapidly on free surface of tellurite-based glasses. J Mater Res Technol. 2022;16:1179–89. 10.1016/j.jmrt.2021.12.059.Search in Google Scholar
[37] Ilik E , Kavaz E , Kilic G , Issa SA , ALMisned G , Tekin HO , et al. Synthesis and characterization of vanadium(V) oxide reinforced calcium-borate glasses: Experimental assessments on Al2O3/BaO2/ZnO contributions. J Non-Cryst Solids. 2022;580:121397.10.1016/j.jnoncrysol.2022.121397Search in Google Scholar
[38] Lakshminarayana G , Ashok Kumar HOT , Issa SAM , Al-Buriahi MS , Dong MG , Lee D-E , et al. Illustration of distinct nuclear radiation transmission factors combined with physical and elastic characteristics of barium boro-bismuthate glasses. Results Phys. 2021;105067:105067.10.1016/j.rinp.2021.105067Search in Google Scholar
[39] Ilik E , Kilic G , Issever UG , Issa SAM , Zakaly HMH , Tekin HO . Cerium (IV) oxide reinforced lithium-borotellurite glasses: a characterization study through physical, optical, structural and radiation shielding properties. Ceram Int. 2022;48(1):1152–65. 10.1016/j.ceramint.2021.09.200.Search in Google Scholar
[40] ALMisned G , Tekin HO , Ene A , Issa SA , Kilic G , Zakaly HM . A closer look on nuclear radiation shielding properties of Eu3+ doped heavy metal oxide glasses: impact of Al2O3/PbO substitution. Materials (Basel). 2021;14(18):5334.10.3390/ma14185334Search in Google Scholar PubMed PubMed Central
[41] Lakshminarayana G , Kumar A , Tekin HO , Issa SAM , Al-Buriahi MS , Dong MG , et al. Probing of nuclear radiation attenuation and mechanical features for lithium bismuth borate glasses with improving Bi2O3 content for B2O3 + Li2O amounts. Results Phys. 2021;25:104246. 10.1016/j.rinp.2021.104246.Search in Google Scholar
[42] Lakshminarayana G , Elmahroug Y , Kumar A , Tekin HO , Rekik N , Dong M , et al. Detailed inspection of γ-ray, fast and thermal neutrons shielding competence of calcium oxide or strontium oxide comprising bismuth borate glasses. Materials (Basel). 2021;14(9):2265.10.3390/ma14092265Search in Google Scholar PubMed PubMed Central
[43] Tekin HO , Shams AMI , Kilic G , Hesham MHZ , Tarhan N , Sidek HAA , et al. A systematical characterization of TeO2–V2O5 glass system using boron (III) oxide and neodymium (III) oxide substitution: resistance behaviors against ionizing radiation. Appl Sci (Basel). 2021;11(7):3035.10.3390/app11073035Search in Google Scholar
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