Energy Absorption Buildup Factors Research Articles

Theoretical Calculation of Gamma-Ray and Neutron Shielding Properties for CsPbBr3-Polypropylene Composite Material

The impact of CsPbBr3, known for its high atomic number and cross section with neutrons, on the gamma-ray and neutron shielding properties of CsPbBr3-polypropylene (PP) composite material was investigated in this study. Critical shielding parameters, including linear attenuation coefficient μ, mass attenuation coefficient μm, half-value thickness, tenth-value layer, and mean free path (MFP), were calculated using Phy-X/PSD software. Additionally, two types of gamma-ray buildup factors, i.e., exposure buildup factor and energy absorption buildup factor, were computed within the range of 0.015 to 15 MeV for depths up to 40 MFP. Furthermore, the neutron shielding ability was evaluated by determining the neutron total effective removal cross section. The results demonstrate that the incorporation of CsPbBr3 enhances the gamma-ray and neutron shielding characteristics of the CsPbBr3-PP composite material.

Enhancement of Gamma-Ray and Neutron Shielding Properties of TeO2-Li2O-ZnO-Nb2O5 Glass System with the Addition of Sm2O3

Radiation shielding glass is widely used, as it protects people from ionizing radiation while allowing for the observation of irradiated areas. However, the performance of even the best-performing tellurite glass for radiation shielding still falls short compared to traditional radiation shielding materials. The effect of Sm2O3, with a high atomic number and cross section with neutron, on the gamma-ray and neutron shielding properties of a 75TeO2-5Li2O-10ZnO-(10-x)Nb2O5-(x)Sm2O3 glass system is studied in this work. Some critical shielding parameters, including linear attenuation coefficients, half-value thickness, tenth-value layer, and mean free path (MFP), have been calculated with the software Phy-X/PSD. Two kinds of gamma-ray buildup factors, the exposure buildup factor and the energy absorption buildup factor, have been calculated in the range of 0.015 to 15 MeV for depths up to 40 MFP. What’s more, their neutron shielding ability has been evaluated by calculating the neutron total effective removal cross section. It is shown that Sm2O3 promotes the gamma-ray and neutron shielding performance of the 75TeO2-5Li2O-10ZnO-10Nb2O5 glass system. The results indicate that the addition of Sm2O3 can be helpful for the radiation shielding performance of tellurite glass, which provides a practical way for designing glass with ideal shielding properties.

Analysis of structural, optical, mechanical properties and evaluation of radiation shielding effectiveness of strontium borate glasses doped with ZnO nanoparticles

This research meticulously explores the synthesis, structural, thermal and optical characterization of zinc oxide nanoparticles (NPs) infused strontium borate glasses (termed SZ glasses) and their applicability as radiation shielding. The glasses have been produced using the melt quenching process in the composition series of (60-x)B2O3: xZnO: 10SrO: 10Na2O: 10CaO: 10BaO, where x varied from 0 to 20 % mol. In order to dope ZnO into glasses, its structural and morphological characteristics were investigated after it was synthesized by solution combustion method. It was found that the inclusion of ZnO significantly impacted the glasses' density, molar volume, hardness, yield stress, and thermal stability. The optical properties of the produced glasses, such as transmittance, reflection, transparency, opacity and band gap energies, were examined and the effect of ZnO on the optical properties of the glasses was investigated. Crucially, the SZ glasses exhibited notable efficiency in shielding against gamma photons and fast neutrons. This is evidenced by the favourable change in the mass attenuation coefficients with increasing ZnO concentration. Parameters like the half-value layer, effective atomic number, and energy absorption buildup factors were calculated to gauge the radiation attenuation proficiency of the SZ glasses, demonstrating their potential utility in radiation protection. In conclusion, the developed SZ glasses display advantageous structural, thermal, and optical qualities, along with robust shielding capabilities against gamma photons and fast neutrons. This study contributes significant knowledge to the field of novel glass materials, paving the way for their application in various industrial and medical contexts requiring radiation shielding.

On the gamma radiation response of commercially available 3D printing materials for medical dosimetry

3D printing technology has rapidly spread for decades, allowing the fabrication of medical implants and human phantoms and revolutionizing healthcare. The objective of this study is to evaluate some radiological properties of commercially available 3D printing materials as potential tissue mimicking materials. Among fifteen materials, we compared their properties with nine human tissues. In all materials and tissues, exposure and energy absorption buildup factors were calculated for photon energies between 0.015 and 15 MeV and penetration depths up to 40 mean free path. Furthermore, the Geant4 Monte Carlo toolkit (version 10.5) was used to simulate their percentage depth dose distributions. In addition, equivalent atomic numbers, effective atomic numbers, attenuation coefficients, and CT numbers have been examined. All parameters were considered in calculating the average relative error (σ), which was used as a statistical comparison tool. With σ between 6 and 7, we found that Polylactic Acid (PLA) was capable of simulating eye lenses, blood, soft tissue, lung, muscle, and brain tissues. Moreover, Polymethacrylic Acid (PMAA) material has a σ value of 4 when modeling adipose and breast tissues, respectively. Aside from that, variations in 3D printing materials’ infilling percentage can affect their CT numbers. We therefore suggest the PLA for mimicking soft tissue, muscle, brain, eye lens, lung and blood tissues, with an infill of between 92.7 and 94.3 percent. We also suggest an 89 percent infill when simulating breast tissue. Furthermore, with a 96.7 percent infill, the PMAA faithfully replicates adipose tissue. Additionally, we found that a 59 percent infill of Fe-PLA material is comparable to cortical bone. Due to the benefits of creating individualized medical phantoms and equipment, the results might be seen as an added value for both patients and clinicians.

Gamma Ray Energy Absorption Buildup Factor Computation for Human Tissues in Energy Range of Medical Radionuclides Up to 10 Mean Free Paths

Gamma Ray Energy Absorption Buildup Factor Computation for Human Tissues in Energy Range of Medical Radionuclides Up to 10 Mean Free Paths

Attenuation properties of poly methyl methacrylate reinforced with micro/nano ZrO2 as gamma-ray shields

This research aimed to examine the radiation shielding properties of unique polymer composites for medical and non-medical applications. For this purpose, polymer composites, based on poly methyl methacrylate (PMMA) as a matrix, were prepared and reinforced with micro- and nanoparticles of ZrO2 fillers at a loading of 15%, 30%, and 45% by weight. Using the high purity germanium (HPGe) detector, the suggested polymer composites’ shielding characteristics were assessed for various radioactive sources. The experimental values of the mass attenuation coefficients (MAC) of the produced composites agreed closely with those obtained theoretically from the XCOM database. Different shielding parameters were estimated at a broad range of photon energies, including the linear attenuation coefficient (μ), tenth value layer (TVL), half value layer (HVL), mean free path (MFP), effective electron density (Neff), effective atomic number (Zeff), and equivalent atomic number (Zeq), as well as exposure buildup factor (EBF) and energy absorption buildup factor (EABF) to provide more shielding information about the penetration of γ-rays into the chosen composites. The results showed that increasing the content of micro and nano ZrO2 particles in the PMMA matrix increases μ values and decreases HVL, TVL, and MFP values. P-45nZ sample with 45 wt% of ZrO2 nanoparticles had the highest μ values, which varied between 2.6546 and 0.0991 cm−1 as γ-ray photon energy increased from 0.0595 to 1.408 MeV, respectively. Furthermore, the highest relative increase rate in μ values between nano and micro composites was 17.84%, achieved for the P-45nZ sample at 59.53 keV. These findings demonstrated that ZrO2 nanoparticles shield radiation more effectively than micro ZrO2 even at the same photon energy and filler wt%. Thus, the proposed nano ZrO2/PMMA composites can be used as effective shielding materials to lessen the transmitted radiation dose in radiation facilities.

Optical UV–visible, Raman spectroscopy, and gamma radiation shielding properties of borate glass systems; B2O3 + Na2O + Al2O3 / MgO/ Li2O

Three borate glass systems with chemical formula 65 B2O3 +  30 Na2O + 5 (x) wt%; x = Al2O3, MgO, and Li2O were fabricated by the common melting-annealing method and coded as BNAl, BNMg, and BNLi, respectively. XRD pattern revealed the non-crystalline form and the glassy states of the prepared samples. UV-optical absorption spectra showed UV cutoff peaks in the range 320–340 nm and optical energy gap (Eopt) by Tauc’s model (ETauc’s) and ASF method (EASF) revealed quite similar values ranged from 2.60 to 3 eV before irradiation and 2.23 to 2.60 eV after 20 kGy of gamma irradiation. Raman spectra show three detectable regions at; (i) 250–600 cm−1, (ii) 500–1000 cm−1 and (iii) 1000–2000 cm−1 correlated to different borate forms. Many radiation shielding parameters were theoretically calculated using Phy-X/PSD and simulated via Monte Carlo code (MCNP-5) in photon energy range (0.015–15 MeV). Mass attenuation coefficient (MAC), linear gamma attenuation coefficient (LAC), effective atomic number (Zeff), fast neutron macroscopic cross section (∑R), exposure buildup factor (EBF) and energy absorption buildup factor (EABF) at various penetration depths PD, as well as half (HVL) and tenth value layers (TVL) and mean free path (MFP) were also estimated. The shielding parameters showed the order of (MAC, LAC)BNAl > (MAC,LAC)BNMg > (MAC, LAC)BNLi. The stability of the glasses optical, and structural properties against gamma irradiation indicate the capable use of the glasses for radiation shielding applications specially Al2O3 glass with the heaviest atomic weight and the highest capacity for radiation shielding protection.

Gamma rays and neutrons attenuation performance of a developed lead borate glass for radiotherapy room.

The development of radiation therapy necessitated a continuous R&D for radiotherapy rooms' glass windows to reach the highest levels of protection for the staff of the radiotherapy facility. Therefore, in this article, a novel type of lead borate glass depending on parallel augmenting of lead and boron was produced to be used as gamma-rays and fast and thermal neutrons barriers in radiotherapy rooms. Neutrons and gamma rays' attenuation parameters, fast neutrons removal cross section ${\varSigma}_R$, thermal neutron total cross section ${\sigma}_T$, mass attenuation coefficient $\sigma$, linear attenuation coefficient μ, half-value layer, mean free path, effective atomic number Zeff, effective electron density Neff, and buildup factor for energy absorption (energy absorption buildup factor) and exposure (exposure buildup factor) were studied extensively. Three tools, Phy-X/PSD, EpiXS and XCOM computer programs and the standard mixture rules were utilized to estimate the attenuation parameters. The improvement caused by the augmentation of lead and boron in both gamma rays and neutrons attenuation was evident from the obtained results. The glass containing the highest lead and boron concentration PbB5, 40Pb-50B, which is the most efficient attenuator for gamma rays and both thermal and fast neutrons was recommended to be a distinguished choice as a shield in a radiotherapy room.

An innovative approach for estimating energy absorption buildup factors (EABF) with HVL and TVL.

The current study proposes an empirical formula for absorption buildup factors as a function of target thickness. The present formula produces absorption buildup factors of compounds and mixtures with simple inputs of linear attenuation coefficient (μ), tenth value layer (TVL) and half value layer (HVL) of interacting target for the atomic number region 29<Z<92 for the energies 0.2MeV<E<1.5MeV. This method is used to compute the energy absorption buildup factors using HVL and TVL.

Investigation of radiation shielding parameters of boron compounds

The radiation shielding parameters such as effective atomic number, effective electron density, mean free path (MFP), half value layer (HVL) and tenth value layer (TVL) were calculated experimentally and theoretically for Boron Carbide(BC4), Boron nitride (BN), Boric acid (H3BO3), Iron boride (Fe2B), Lanthanum borate (BLaO3), Sodium borohydride (NaBH4), Borax (Na2H20B4O17), Titanium diboride (TiB2), and Zirconium diboride (ZrB2) compounds. In experimental measurements, the compounds were irradiated by 137Ba, 152Eu and 241Am radioactive gamma-ray sources. The theoretical results obtained with the help of the WinXCom computer program were compared with the experimental results and they were found to be in good agreement. Moreover, energy absorption buildup factor (EABF) and exposure buildup factor (EBF) values were calculated for compounds using the geometric progression (G.P.) fitting formula for the energy range of 0.015–15 MeV and penetration depth up to 40 mfp (mean free path). Buildup factors (EABF, EBF) increased with increasing penetration depth. In general, the buildup factors for all compounds formed a Gaussian curve and had the highest values in the energy range dominated by Compton scattering. As a result of the findings obtained in the study, it was seen that Lanthanum borate gave the best results in radiation shielding.

Energy build-up factors estimation for BaZr0.10Ti0.90O3, Ba0.90La0.10TiO3 and Ba0.90La0.10Zr0.10Ti0.90O3 ceramics in shielding applications

The search for materials that serve as good shields for radiation has become very important in light of the increasing exposure to ionizing radiation in various vital sectors. The aim is to search for novel materials with better radiation shielding properties that are stable, nontoxic, and abundant and environment friendly. The solid-state reaction approach has been used to synthesize a few ceramics, including BaZrXTi1-XO3, Ba1-XLaXTiO3 and Ba1-XLaXZrXTi1-XO3 (with x = 0.10) i.eBaZr0.10Ti0.90O3 (BZT), Ba0.90La0.10TiO3 (BLT), and Ba0.90La0.10Zr0.10Ti0.90O3 (BLZT). The density of the prepared samples varies from 6.3471 to 11.6003 g/cm3. The X-ray diffraction technique, shows strong peaks to confirm the crystalline structure of prepared ceramic samples. Using the G-P fitting approach, the advanced radiation shielding parameters (build-up factor) have been evaluated in the photon energy region of 1.5 keV–15 MeV. It is observed from the results that exposure buildup factor (EBF) and energy absorption buildup factor (EABF) are maximum for BLZT and has the minimum value for BZT in the entire photon energy regime. The results of this work should be useful in radiation shielding applications such as in industry, medicine, and nuclear engineering.

Evaluation of photon, proton, and alpha interaction parameters of EDTMPLu and MDPLu medications used for some bone cancer

In this study, we explore the interactions of photons, protons, and alpha with matter in the context of two drugs, MDPLu and EDTMPLu, delving into the interesting field of radiation shielding. Our research is focused on the mass attenuation coefficient (GMAC), effective atomic number (Zeff), buildup factors (EBF and EABF), and dosimetry parameters with the goal of understanding how these factors affect how well these drugs work as radiation shields. Our results show that the effective atomic number was higher in substances with a higher percentage of Z element component, and that the GMAC values for MDPLu medications were the highest, while the GMAC values for EDTMPLu medications were the lowest. Additionally, MDPLu showed the lowest exposure buildup factor (EBF) and energy absorption buildup factor (EABF), further validating its efficacy as a shielding material. Moreover, MDPLu displayed a higher mass-stopping power (MSP) for proton interactions in the lower energy range, making it a prime candidate for specific radiation shielding applications. These insights contribute to our understanding of the radiation-shielding efficacy of bone cancer treatment medications.

Investigations of Gamma and Neutron Shielding Parameters of Ti-Nb-Fe-Cr Alloys with Varying Cr Concentrations

The Ti-Nb-Fe-Cr alloys are used in various fields, such as nuclear radiation shielding, cladding material in nuclear reactors, and implants in the medical field. It is one of the best materials for biomedical applications as it is biocompatible, is corrosion resistant, and has good mechanical properties. As nuclear radiation emanates from various sources in a nuclear reactor, the behavior of this alloy with the interaction of gamma and neutrons has not been well studied. In the present investigations, the interaction of gammas and neutrons with Ti-27Nb-7Fe-xCr (x = 0, 2, 4, 6, and 8 wt%) alloys is studied in order to understand the radiation shielding properties and their usefulness in biomedical applications. Gamma-ray–interaction parameters such as MAC, HVL, MFP, Zeff, Zeq, Neff, and multilayer energy absorption buildup factor (MLEABF) are estimated using EpiXs, PyMLBUF, and NGCal software in the energy range of 1 keV to 15 MeV. The multilayer buildup factor (MLBF) is calculated for cortical bone and for alloys with varying Cr concentrations. Comparison of the MLBF values of alloys with cortical bone shows that in the lower-energy region as well as the higher-energy region above 0.5 MeV, alloys and cortical bone yield the same values, indicating that the alloys behave as cortical bone in this energy region. Mass attenuation factors (MAFs) of thermal and fast neutrons are also calculated for various elastic modulus values of selected alloys at thermal and fast neutrons. It is found that the elastic modulus increases with increasing MAF values of both fast and thermal neutrons. By increasing the Cr content in the Ti-27Nb-7Fe alloy, the elastic modulus decreases. The relationship between the MAF of neutrons and the elastic modulus of the alloy is established for the first time.

Investigation of shielding properties of gamma and neutrons in some natural radioprotective drugs

In radiation therapy, various radioprotective materials are used to protect normal cells from damage due to ionizing radiation. Natural products such as apigenin, bergenin, caffeine, chlorogenic acid, coniferyl aldehyde, curcumin, delphinidine, and quinic acid have been found to be good radioprotectors as they have low toxicities. In order to select the best natural radioprotector, it is essential to understand the interaction of gamma and neutrons with these radioprotectors and to determine radiation shielding parameters. The radiation parameters such as mass attenuation coefficient (MAC), effective atomic number (Zeff), equivalent atomic number (Zeq), effective electron density (Neff), exposure buildup factor (EBF), and energy absorption buildup factor (EABF) have been determined for the natural radioprotectors using EpiXs and NGCal software. The estimated results show that the Zeff values of selected radioprotectors are higher in the low-energy region and lower in the high-energy region, indicating that they are suitable for shielding low-energy gamma photons. Among selected natural radioprotectors, quinic acid is the best radioprotector for shielding thermal and fast neutrons. The relationship between MAF and Zeff/Neff has been established for the first time, and it has been found that MAF for thermal and fast neutrons decreases with an increase in the Zeff/Neff values of selected natural radioprotectors.

The Fundamental Gamma Rays and Charge Particle Interactions of the CeBr3 Scintillator

The research aims to study the primary interaction between gamma radiation in CeBr3 crystal. The analysis of mass attenuation coefficient (MAC), effective atomic number (Z eff), electron density (N eff), mean free path (MFP), and energy absorption buildup factor (EABF) was evaluated using the using the WinXCom software. Also, the interaction with charged particles as the total mass stopping power (TMSP), projected range (PR) of proton () and alpha () particles were evaluated by SRIM programming. The results found that the MAC depends on the energy ranges, the photoelectric effect is the main interaction at low energy ranges, Compton scattering phenomena illustrate and evidents at intermediate energy ranges, and pair production characteristics dominate over on 1.022 MeV in high energy ranges. Moreover, absorption edges appear on energy’s discontinuity at low energy. The Z eff and N eff show similar trends and correspond to the energy ranges. The MFP of the CeBr3 compared with some standard scintillators such as NaI and BGO crystal and found that the BGO responds to faster interaction than CeBr3 and NaI crystals. The EABF shows scattering energies followed by atomic equivalent (Z eq), and they also increase with increasing penetration depth (mfp). The TMSP and PR depend on charged particles, density, and the unit path distance of a material.

Investigation of the nuclear radiation parameters of some Ti alloys for biomedical applications

This study investigates the nuclear radiation parameters of selected Ti alloys with potential biomedical applications. The compatibility with nuclear radiation is essential for these alloys in biomedical applications. To understand the nuclear radiation compatibility for this selected alloy, the gamma rays, neutrons, and charged particle interaction parameters were estimated using EpiXS, NGCal, ESTAR, and SRIM. The gamma rays, neutrons, and charged particle interaction parameters of selected Ti alloys relative to the cortical bone were studied. The Zeff of selected alloys relative to the cortical bone reaches unity in the lower photon energy region. Similar values of energy absorption buildup factor for selected alloys and cortical bone when the gamma energy region lies between 200 keV and 3 MeV. For neutron interaction at incident energy of thermal neutron at 25.4 meV and fast neutron 4 MeV, significant differences exist between selected alloys and cortical bone. From the estimated data, it is observed that among selected alloys, Ti-6Al-4V and Ti-6Al-4V-2.5Cu are comparable with cortical bone in terms of gamma rays and charged particle interactions. The results indicate that Ti-6Al-4V and Ti-6Al-4V-2.5Cu are the most suitable alloys for biomedical applications such as knee, hip, and elbow joints.

The Properties of Bi2O3 Additive on Radiation Shielding and Elastic Moduli Properties of TeO2–P2O5 Based Glass System

The radiation shielding and elastic moduli properties of (60–x)TeO2–30P2O5–xBi2O3 (x increased from 10–50 mol% in 10 mol% increments) glass series have been discussed. The radiation shielding quantities such as mass attenuation coefficient (µ m), effective atomic numbers (Z eff), half value layer (HVL) and mean free path (MFP) were calculated using Phy–X/PSD program at energies ranging from 1 keV–100 GeV while exposure and energy absorption buildup factors (EBF and EABF) were evaluated using geometric progression (G–P) fitting method at energies ranging 0.015–15 MeV for penetration depths (PD) until 40 mean free path (mfp). In addition, the density and elastic moduli were estimated. The results found that the TPB5 glass sample having the largest content of Bi2O3 possessed the highest density and excellent radiation shielding properties. This reflected that replacing TeO2 with Bi2O3 improved effective radiation shielding. In addition, the MFP for glass series were lower than the hematite-serpentine concrete. It indicated that this glass series are photon shielding better than the hematite-serpentine concrete. Whereas, this sample had the lowest elastic moduli. These results indicated that Bi2O3, a network modifier, has broken glass network bonds and formed non–bridging oxygen (NBOs) which affects the elastic moduli of the glass system.

Nuclear shielding characteristics of newly developed composite metal foams: Role of CeO2 addition and foam type

In present study, new composite materials which were produced by filling open-cell aluminum foams of different thickness and pore size with various additives were surveyed with respect to photon and fast neutron shielding effectiveness. The metal foam samples were prepared in two different series (A: 30 mm thick with a pore size of 2 pores/cm and B: 10 mm thick with a pore size of 16 pores/cm) according to thickness and pore sizes, and the foams were filled with different mixtures which include Epoxy(60)-B2O3(20)-CaO(20-x)-CeO2(x); (x; 0, 5, 10, 15 and 20 wt%) chemical compositions. Gamma, X-ray and neutron measurements of the produced samples were performed using Ultra-Ge detector, linear accelerator (LINAC) and BF3 neutron detector, respectively. The gamma-transmission measurements were achieved for 30.9, 59.54, 75, 81, 276, 303, 356, 384, and 662 keV photon energies using radioactive sources of 241Am, 137Cs, 133Ba. Linear Attenuation Coefficients (LAC) of the samples were figured out with the data acquired from the measurements and MAC, HVL, Zeff and Ne values were found by way of these values. The MAC, Zeff and Ne values of the samples increased with the rising in the percentage of CeO2 added to the mixture. The energy absorption (EABF) buildup factors of the composite metal foam samples were also determined for the energy range of 0.015–15 MeV at 1–40 mfp penetration depths. It was found that the A5 and B5 samples with 20% CeO2 additive had the least EABF values. Lastly, the shielding capability of the fabricated samples against fast neutrons was specified by executing equivalent dose measurements (EAD) and calculated macroscopic cross section (∑R) values. It was established that the A2 sample had the highest absorption dose rate of 49%. The largest of the theoretically calculated ∑R values belongs to the B5 sample with 20% CeO2 additive. Generally, it was concluded that the samples in the B series, which are thinner and have more pores, have better radiation attenuation capabilities.

Computation of gamma-ray buildup factors for (25-x)CaF2-xAl2O3–15Bi2O3–59B2O3–CuO glasses

High energetic gamma rays are used in different fields and thus it may cause high risks for public if it is absorbed over limited dose. In order to be protected from these hazardous effect of radiation, the shielding is an effective ways and this requires shielding materials. For this purpose the gamma radiation shielding parameters for four different types glasses which was formulated as (25-x)CaF2-xAl2O3–15Bi2O3–59B2O3–CuO (x = 3,6,9,12 mol%) have been investigated. For this purpose, the linear absorption coefficients (LAC, μ) were calculated using Phy-X/PSD within the gamma ray energy range of 10−3-105 MeV. From using the equivalent atomic number (Zeq) and Geometric progression (G–P) method, the exposure buildup factor (EBF) and energy absorption buildup factor (EABF) values were evaluated at 0.015 MeV–15 MeV gamma rays. The values of EBF and EABF were calculated for 1, 5, 10, 20, 30, and 40 cm mean free path (mfp).

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

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