Search

Samples of germanium borosilicate glasses with chemical formula 50.5B2O3 + 0.5CeO2 + 10SiO2 + (20‐x) CaO + 19Na2O + XGeO2 with 0 (GeO0) ≤ X ≤ 5 (GeO5) mol% were fabricated by using the melt quenching technique. Structure, physical, and optical properties as well as radiation attenuation capacity was examined. XRD data confirmed that GeOX samples were in amorphous state. The density (ρ) of the prepared glass samples increased from 2.24 to 2.55 g/cm3, while the molar volume (Vm) slightly declined from 26.8 to 26.42 cm3/mol. The UV absorption edge shifted to a higher wavelength as the concentration of GeO2 increased. The values of direct band gap (EgDirect)$(\bm{E_g^{Direct}})$ ranged from 3.36 to 2.91 eV, and the indirect (EgIndirect)$(\bm{E_g^{Indirect}})$ ranged from 3.12 to 2.75 eV. Urbach energy (Eu) values fluctuated between 0.65 to 0.16 eV. As the Ge4+ ion increased, the glass sample's refractive index enhanced. Mass attenuation coefficients (MACs) of GeOX samples increased from 6.788 to 10.381 cm2/g at 0.015 MeV. The GeO5 sample possessed the lowest half value layer (HVL) and mean free path (MFP). Effective atomic number (Zeff) of GeOX possessed the same trend of MAC. Results confirmed that the suggested GeOX glasses can be applied in different optical and radiation attenuation applications. [ABSTRACT FROM AUTHOR]

Samples of germanium borosilicate glasses with chemical formula 50.5B2O3 + 0.5CeO2 + 10SiO2 + (20‐x) CaO + 19Na2O + XGeO2 with 0 (GeO0) ≤ X ≤ 5 (GeO5) mol% were fabricated by using the melt quenching technique. Structure, physical, and optical properties as well as radiation attenuation capacity was examined. XRD data confirmed that GeOX samples were in amorphous state. The density (ρ) of the prepared glass samples increased from 2.24 to 2.55 g/cm3, while the molar volume (Vm) slightly declined from 26.8 to 26.42 cm3/mol. The UV absorption edge shifted to a higher wavelength as the concentration of GeO2 increased. The values of direct band gap (EgDirect)$(\bm{E_g^{Direct}})$ ranged from 3.36 to 2.91 eV, and the indirect (EgIndirect)$(\bm{E_g^{Indirect}})$ ranged from 3.12 to 2.75 eV. Urbach energy (Eu) values fluctuated between 0.65 to 0.16 eV. As the Ge4+ ion increased, the glass sample's refractive index enhanced. Mass attenuation coefficients (MACs) of GeOX samples increased from 6.788 to 10.381 cm2/g at 0.015 MeV. The GeO5 sample possessed the lowest half value layer (HVL) and mean free path (MFP). Effective atomic number (Zeff) of GeOX possessed the same trend of MAC. Results confirmed that the suggested GeOX glasses can be applied in different optical and radiation attenuation applications. [ABSTRACT FROM AUTHOR]

The effect of vanadium oxide (V2O5) on the structural, dielectric, and shielding features of borate-lead-fluoride glasses was investigated. The density of the glass network increased steadily from 3.18 to 3.28 g.cm−3 as the vanadium content increased from 0.0 to 10 mol%. The evolution of functional groups and units such as non-bridging BO3, and bridging BO4, in our newly developed glasses was exposed by FTIR analysis. Since the fraction of bridging units BO4 increases when V2O5 is added up to 2 mol%. This indicates that the conversion of BO3 groups into BO4 groups is facilitated by V2O5. However, at higher concentrations of V2O5 (> 2 mol%), a reversal reaction occurs wherein the BO3 unit fraction increases and the BO4 unit fraction starts to decrease. All the glasses loaded with different amounts of V2O5 mol% had a sharp decline in dielectric constant with increasing frequency over the low frequency interval. As the V2O5 level grew up to 2 mol%, the dielectric constant value was marginally reduced and then increased for higher concentrations. All of the glasses under examination displayed different relaxation peaks in the range of 100 Hz to 20 kHz on their measured loss tangent (tan δ), but vanadium doping caused them to shift to higher frequencies. At 0.015 MeV, the maximum MAC values for the V-0.0 to V-10.0 samples were found to be 29.205 cm2/g to 30.082 cm2/g. In terms of radiation shielding, the V-10.0 sample exhibited the highest values of mass (MAC) and linear (LAC) attenuation coefficients, while the same sample possessed the lowest values of half value layer and mean free path among all investigated glasses. Therefore, the investigate glass can be used in several optical and radiation shielding applications. [ABSTRACT FROM AUTHOR]

This work assessed highly effective bismuth borosilicate glasses' nuclear radiation shielding capabilities in terms of different concentrations of Bi2O3. Melt-quenching was the method used to create the glasses. The Phy-X/PSD program was used to compute the μm values. The bismuth borosilicate glasses' nuclear radiation shielding properties were determined in the 0.015–15 MeV energy range. Increasing Bi₂O₃ concentration resulted in an increase in mass attenuation coefficient, linear attenuation coefficient, and effective atomic number. Conversely, the half value layer and mean free path values decreased. The B48Bi17 sample, with its largest Zeff, is a great gamma attenuator. The results of a new study may help to clarify the nature of the Bi2O3 additive used in borosilicate glasses, which are a potential form of shield for use in industrial and medical radiation facilities.

Abstract In this study, the microstructure and elemental analysis of aluminum-copper alloy type-2024, Al-2024, and aluminum-manganese alloy type-3003, Al-3003, have been investigated by using a scanning electron microscope (SEM) equipped with Energy dispersive spectroscopy (EDS) detector. Experimental and theoretical radiation shielding studies were performed to assess the radiation shielding capabilities of the studied alloys. Considering the radiation shielding theoretical assessment, some reliable software tools were used, such as Phy-X/PSD, MCNP5, NXCom, and MRCsC. The microstructural observations and results have shown the presence of second phases rich with the main alloying elements in both alloys. Considering Al-2024 alloy, coarse second-phase particles, having a size range of 8–15 μm, were found aligning in lines parallel to the rolling direction, whereas smaller ones, having a size range of 2–8 μm, were found decorated the grain boundaries. Also, dark holes represent the pull-out large particles separated during preparation indicated poor adhesion with the main matrix that could be a result of losing particle coherency with the matrix where the misorientation in-between the atomic planes increase. However, better adhesion of the second-phase particles with the matrix, which were found possessing smaller particle size, have been observed in the Al-3003 alloy indicating good coherency and better manufacturing process for the non-heat-treatable alloy. The second-phase particles in case of Al-2024 alloy were found containing significant content of high-Z elements like Cu with greater volume fraction equals 7.5%. On the other side, Al-3003 alloy has possessed second-phase particles which lack of high-Z elements with only volume fraction equals 3.5%. All the former besides the higher density and content of high-Z elements like copper in Al-2024 alloy in compare to Al-3003 alloy and pure aluminum, led to relatively better radiation shielding capabilities against energetic photons, the highest in the low energy band and decreases with the increase of the photon energy, and slight superiority in the case of fast neutrons with only 3%inc. over pure aluminum. For instance, the radiation protection efficiency (RPE) values dropped from about; 23.2, 21.6, and 20.8% at 0.100 MeV to only 5.7, 5.9, and 5.6% at Eγ = 2 MeV, for; Al-2024, Al-3003, and Al-Pure, respectively."Please check and confirm that the authors and their respective affiliations have been correctly identified and amend if necessary.""confirmed"

Gamma-ray, charged particles and neutron-shielding properties of ternary alloy materials, (97.3 – x) Pb – x Cd – 2.7Ag (x = 10, 18 and 30) have been theoretically investigated. First, the effectiveness of gamma-ray shielding for the alloys was studied by using the Phy-X/PSD programme. Mass and linear attenuation coefficients (MAC and LAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic numbers (Zeff), effective electron densities (Neff) and effective conductivity (Ceff) were calculated for photon energy range 0.015–15 MeV. Second, the mass stopping powers (MSPs; dE/ρdx; MeVcm2/g) and ranges for electron, proton and alpha particle interactions were calculated at energy 0.01–20 MeV. Finally, the removal cross-section of fast neutron (FNRCS) for the alloys was calculated by the partial density method. Moreover, the neutrons and gamma-rays shielding effectiveness of ternary alloys were investigated using Monte Carlo (MCNP4b). The MCNP4b calculations were performed for neutrons in the energies 4 and 4.5 MeV. While the shielding parameters of gamma rays were done in the energy range of 0.015–15 MeV. The obtained results of radiation shielding showed that the P1 sample owns a good shielding effectiveness against neutrons and gamma rays compared to previously published studies. The comparison of the computed values has revealed a reasonable agreement between Phy-X/PSD and MCNP4b. This study gives essential data for potential applications of these materials in nuclear reactor core design and other industries for the evaluation of effective ionising radiation shielding materials. [ABSTRACT FROM AUTHOR]

Environmental pollution increases due to the large amounts of waste production and raw material consumption depending on the increasing population. Agricultural and industrial wastes which are some of the sources of the pollution need to be reuse to reduce the negative impact on the environment and also contribute positive effect to the economy. In this context, industrial wastes such as clay types (red and green) and agricultural wastes such as egg shell, walnut shell and banana shell were used to prepare materials which can be used as replacement materials for construction industry. Radiation attenuation parameters (mass attenuation coefficients, effective atomic number, linear attenuation coefficients, mean free path, half-value layer, exposure and energy absorption build up factors, fast neutron removal cross-section) were acquired by Phy-X/PSD code. Spectroscopic techniques (XRD, EPR, SEM-EDS) were performed for the structural analysis. The existence of calcite main phase peaks (≈29.7) as well as SiO2 (≈20° and 26°) and cellulose phases (≈16° and 34.7°) were observed by XRD. Mn+2 sextet lines with five weak doublets attributed to the forbidden transition lines of Mn+2 and a singlet with a g value of ≈2.00 and linewidth of ≈10 G were recorded by EPR. Among the samples, it was found that K1 (Red clay (20%)-eggshell waste (60%)-Bayburt stone waste (20%)), K3 (Red clay (60%)-eggshell waste (20%)-Bayburt stone waste (20%)), C3 (Red clay (60%)-eggshell waste (20%)-walnut shell waste (20%)) and Z3 (Green clay (60%)-egg shell waste (20%)-Bayburt stone waste (20%)) have the highest shielding potentials. All samples examined with good protection performances can be used as substitute materials instead of cement or aggregate for the aim of reusing the wastes and supporting the environmental and economic benefits. [ABSTRACT FROM AUTHOR]

In the present study, a newly set of lutetium(III)-doped borosilicate glasses with the chemical formula (49–x)B2O3 + 13SiO2 + 18CaO + 20Li2O + XLu2O3: X takes values from 0 (Lu0.0) to 2 (Lu2.0) at intervals of 0.5 mol% has been prepared via the traditional quenching technique. The impact of the inclusion Lu3+ ions in the glasses network on the physical, and Raman spectroscopy has been investigated. XRD measurements confirmed the amorphous state of Lu-X glasses. The density (ρ) of Lu-X glasses varied from 25.10 × 10–1 g/cm3 for Lu0.0 glass sample to 26.40 × 10–1 g/cm3 for Lu-2.0 glasses. The molar volume (Vm) of Lu-X glasses was increased from 23.10 to 24.37 cm3/mol as Lu2O3 content increased from 0 to 2 mol%. The oxygen packing density (OPD) values reduced from 91.33 to 86.59 g atm/l. The oxygen molar volume (VO) values enhanced from 10.95 to 11.55 cm3/mol. The average boron–boron separation ⟨dB−B⟩ slightly changed in the glass matrix. The inclusion of Lu3+ ions into the host matrix of the Lu-X glasses leads to convert certain BO3 groups into BO4 groups, hence enhancing the amount of non-bridging oxygen bonds (NBOs). This fact is confirmed by Raman spectroscopy. The linear-(µ) attenuation absorption follows the order: (µ)Lu0.0 < (µ)Lu0.5 < (µ)Lu1.0 < (µ)Lu1.5 < (µ)Lu2.0. Values of half-value layer (HVL) follow the trend: (HVL)Lu0.0 > (HVL)Lu0.5 > (HVL)Lu1.0 > (HVL)Lu1.5 > (HVL)Lu2.0. Lu2.0 glass is located in the mid-point or a suitable point among the commercial concrete materials as γ-ray shields. [ABSTRACT FROM AUTHOR]

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. [ABSTRACT FROM AUTHOR]

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. [ABSTRACT FROM AUTHOR]

Copyright of Afyon Kocatepe University Journal of Science & Engineering / Afyon Kocatepe Üniversitesi Fen Ve Mühendislik Bilimleri Dergisi is the property of Afyon Kocatepe University, Faculty of Science & Literature and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

Abstract Regarding to their unique physical and mechanical features, glasses and glass–ceramics are suitable materials for shielding purposes. The present study evaluates the shielding properties of the CaF2–CaO–B2O3–P2O5–SrO–Ta2O5 glass system using Monte Carlo GEANT4 and MCNPX codes for X-ray radiations with an energy range of 20 to 100 keV. MAC values of the Ta0, Ta1, Ta2, Ta2.5, and Ta3 samples of the CaF2–CaO–B2O3–P2O5–SrO–Ta2O5 glass were computed using Phy-X/PSD, GEANT4, and MCNPX codes and compared. According to the results, the programs have good compatibility with each other. For instance, in the energy of 40 keV and for the Ta2 sample, GEANT4 and MCNP codes are 1.445765406 and 1.517801204 cm2/g, respectively, indicating 7.419529525 and 2.829628418% differences with 1.562 cm2/g obtained using the Phy-X/PSD software. According to recent estimations, the Ta3 sample of the CaF2–CaO–B2O3–P2O5–SrO–Ta2O5 glass system can be selected as the best shield compared with the other samples.

The study of lead-free glasses for radiation shielding applications has drawn global attention. This work aimed to theoretically investigate the impact of Bi2O3 on X-ray shielding characteristics of telluro-borate-bismuth glass samples, in the 15−300 keV energy region. Sample S5 (55Bi2O3 - 5TeO2 - 20SrO - 5ZnO - 15Bi2O3 ) yielded highest LAC, MAC, and Ze f f (1.066−252.061 cm−1, 0.249−58.893 cm² /g, and 67.81−30.16), alongside the lowest HV L, TV L, and MFP (0.003− 0.650 cm, 0.009−2.160 cm, and 0.004−0.938 cm). Hence, S5 emerged as the most effective X-ray shielding glass among the samples studied. [ABSTRACT FROM AUTHOR]

In the study, four novel Ni-based superalloys were produced and radiation shielding efficiencies of the alloys were investigated. Ni, Fe, Mo, Cr, Ta and W were selected for developing NiyTaxW7Cr7Fe7Mo7B7 (x = 0–20; y = 65–45%) alloys based on Ni. Phy-X/PSD code was used to calculate the attenuation parameters. Results were compared by XCom and some reported values in the literature for a meaningful evaluation. In addition, experimental results were provided based on x-ray diffraction, scanning electron microscopy, energy-dispersive spectroscopy and electron paramagnetic resonance spectroscopic techniques. It is obtained that the crystallite sizes of the alloys calculated based on the Debye Scherrer equation vary between 44.13 and 68.33 nm. The mapping images and EDS analysis indicate that the Ni3 alloy has the most homogeneous structure. There is a direct relation between the amount of Ta and the radiation protection capability of the alloys. Newly fabricated Ni-based superalloys have good shielding properties and the usability of the alloys can be recommended as effective shielding materials in radiation-related applications. [ABSTRACT FROM AUTHOR]

Radiation shielding plays a crucial role in safeguarding human health, and ongoing research is exploring alternative materials for this vital purpose. Herein, physical and radiation-shielding features of the manufactured glasses via melt-quenching technique doped with ZrO2 within a glassy system, (100-x-y)[SrTiO3]-x[2B2O3·SiO2]-y(ZrO2), (39 ≤ x ≤ 40, and 0 ≤ y ≤ 4 mol % ZrO2) were studied. The density (ρ) and field-strength (Fs) values of the synthesized glasses were found to be in an increasing order of 2.6068–3.0720 g/cm3 and 5.2401–14.2399 Å−2 respectively. The study also encompassed an exploration of the radiation shielding properties such as mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half value length, tenth value length, mean free path, effective atomic number (Zeff), and effective electron-density (Neff) of the synthesized glasses, employing the freely available 'Phy-X/PSD' software within the energy range of 0.015–15 MeV. The highest values of MAC, LAC, and Neff at 0.02 MeV were found to be 25.275 cm2/g, 77.644 cm−1, and 8.42 × 1023 electrons/g for SrTZ4 (x = 39 and y = 4) glass respectively. Notably, among all the fabricated glasses, SrTZ4 emerged as the standout performer, demonstrating superior gamma-radiation protecting abilities along with effective physical properties. Thus, the fabricated SrTZ4 glass with its remarkable radiation shielding properties holds promising applications for the development of radiation protection equipment. [ABSTRACT FROM AUTHOR]

AbstractThe 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. [ABSTRACT FROM AUTHOR]

Herein, various aspects on the optical, structural, and radiation shielding characteristics of the synthesized glasses doped with Fe2O3 via melt-quenching technique in the system (30-x)BaO–30TiO2–40SiO2–xFe2O3 (0 ≤ x ≤ 6) were studied. To verify the amorphous nature of the prepared glasses, XRD was performed. Physical properties like density (ρ) and oxygen packing density (OPD), revealed their enhanced values within the ranges of 3.5312–4.4135 g/cm3 and 75.7678–96.7366 g-atom/l. However, the molar volume (Vm) of the fabricated glasses was found to be in decreasing order from 30.3559 to 23.7759 cm3/mol respectively. Further insight into the molecular structure was performed via FTIR and Raman spectroscopies which showed the formation of different bonding such as Si–O–Si, Ti–O, and Si–O–Ti along with non-bridging oxygens (NBOs). However, UV–visible spectroscopic results showed the indirect energy band gap ( E g ind ) decreases from 3.922 to 3.502 eV with increasing the content of Fe2O3 while the refractive index (η), and optical dielectric constant (ɛ) were found to be in an increasing range of 2.185–2.274 and 4.774–5.169. Further, to determine the elemental distribution and their corresponding electronic states of a tentative glass sample (BTS6F), X-ray photoelectron spectroscopy (XPS) was carried out. In order to study the radiation shielding properties of all the fabricated glasses, the Phy-X/PSD software across a spectrum of energies from 0.015 to 15 MeV was successfully executed. Among all the glasses, the glass BTS6F demonstrates superior gamma-radiation shielding capabilities along with effective optical properties. Therefore, this glass sample can be used for optoelectronics and radiation shielding applications. [ABSTRACT FROM AUTHOR]

In this study, the interaction parameters of neutrons, charge particles and gamma rays in seven inorganic scintillation materials with densities ranged from 3.86 to 8.30 g/cm3 were theoretically examined. SRIM Monte Carlo software was used to determine the range of $ {H^ + },H{e^{ + + }},A{u^ + }and\textrm{ }\,{O^{ - - }} $ H + , H e + + , A u + and O − − ions in the energy range (0.01–20) MeV, Phy-X/PSD while Py-MLBUF computer programs were used to estimate gamma radiation interaction parameters in the energy range (0.02–15) MeV. The electron total stopping power and range values at energies ranging from 0.01 to 1000 MeV were calculated using the ESTAR NIST program. The fast neutron removal cross-section (FNRCS) and the macroscopic effective removal cross-section (MRCS) were calculated using the Phy-X/PSD and MRCS tools, respectively. The outcomes of this research showed that the range of $ {H^ + },H{e^{ + + }},A{u^ + }and\textrm{ }\,{O^{ - - }} $ H + , H e + + , A u + and O − − ions increased with decreasing sample density but decreased with increasing projectile energies; the largest range of $ {H^ + } $ H + is 2090 µm in the lowest density S1 sample, while the range of $ \textrm{ }A{u^ + } $ A u + is 5.16 µm in the same sample. The denser sample S7 had the highest stopping power and the lowest range at higher electron energies. The S1 sample had the highest calculated HVL value of 5.403 cm, while the S7 sample had the lowest calculated HVL value of 0.0008 cm. Rising sample density causes the MAC to rise, while rising gamma energy causes the MAC to decrease. The highest MAC value recorded was 107 cm2/g at 0.015 MeV in the S7 sample, and the lowest value recorded was 0.0369 cm2/g at 15 MeV in the S1 sample. For all inorganic scintillation samples at particular gamma energies, the standard deviations for the MAC, HVL and Zeff values between the Phy-X/PSD and, Py-MLBUF programs were calculated. With energy range variation, the results for Zeff for the two samples S2 and S4 appeared to be constant. Regards to the fast neutrons, the heights value's of FNRCS, and MRCS were recorded for S7. [ABSTRACT FROM AUTHOR]

In this research, gamma-ray, fast neutron, and H1/He+2 ion shielding characteristics of xSb2O3—(35 − x)B2O3–60Bi2O3–5TeO2 ( x = 10 , 20 , and 30 in mol%) glass system were analyzed over 15 keV to 15 MeV by using Phy-X/PSD and SRIM software. The shielding properties of the aforementioned glasses were compared with those of two different bismuth–borate–tellurite glasses for the purpose of evaluation. Results indicate that the addition of Sb2O3 generally improves the overall shielding properties of the glass system enhancing the mass attenuation coefficient, linear attenuation coefficient, half-value layer, tenth-value layer, effective atomic number, etc. The obtained values of attenuation coefficients calculated by using Phy-X/PSD and XCOM(NIST) software were compared and a good agreement between them was confirmed at all selected energies. The maximum values of linear attenuation coefficients obtained at the lowest photon energy of 15 keV for samples S1, S2, S3, S4, and S5 were 590.123, 601.463, 610.986, 477.481, and 422.572 cm−1, respectively. The calculated mass stopping power and projected range values obtained through the utilization of SRIM software demonstrated superior shielding capability for H1/He+2 ions in the sample with the highest Sb2O3 content. A similar trend was observed in the fast neutron removal cross section values. Our findings strongly suggest that all of the chosen samples, especially S3 (for x = 30 ), have superior radiation shielding characteristics, and thus can be used as an alternative material to replace the conventional material: lead for radiation shielding. [ABSTRACT FROM AUTHOR]

Thermoplastic polyurethane (TPU) composites with eutectic gallium (Ga) and indium (In) (eGaIn) fillings of 0 wt%–75 wt% were prepared using the electrostatic spinning method. Field emission scanning electron microscopy (SEM), X-ray diffraction (XRD), and Fourier-transform infrared (FTIR) spectroscopy were used to characterize the eGaIn NDs/TPU composites. To evaluate their X-ray shielding properties, Phy-X/PSD and WinXCom were employed to calculate the mass attenuation coefficients, linear attenuation coefficients, half-value layers, tenth value layers, mean free paths, and adequate atomic numbers of the eGaIn NDs/TPU composites. The SEM results indicated that the eGaIn nanodroplets were evenly distributed throughout the TPU fibers, and the flowable eGaIn was well-suited for interfacial compatibility with the TPU. A comparison of the eGaIn NDs/TPU composites with different content levels showed that the composite with 75 wt% eGaIn had the highest μm at all the evaluated energies, indicating a superior ability to attenuate X-rays. This non-toxic, lightweight, and flexible composite is a potential material for shielding against medical diagnostic X-rays. [ABSTRACT FROM AUTHOR]

Gamma radiation, neutron, electron and charged ions interaction properties of ten nitrogen-based explosive compounds were theoretically evaluated. Different computer programs were deployed in the computation. Results showed that interaction properties of all investigated explosive samples were majorly dependent on density, mean excitation potential and chemical composition of the sample. Among all investigated explosives, higher gamma ray interaction was observed in E7 (Nitrocellulose) and E3 (HMTD) explosives. Range of charged ions increased with decrease in density of samples but increased with projectile energies of charged ions. E1 (Ammonium nitrate) gave the maximum stopping power at the highest electron energy and minimum range at highest electron energy. The E1 (Ammonium nitrate) also displayed the highest value of FNRCS (0.121 cm−1), while E8 (Nitroglycerin) gave the lowest value of FNRCS (0.044 cm−1). These interaction properties are veritable parameters of consideration in characterization and detection of these explosives. The average relative deviations between Phy-X/PSD and Gamma rays attenuation shielding parameters (GRASP) computer programs in the measurement of MAC is 0.0501%. The mean relative deviation between Auto-Zeff and GRASP programs is 0.3390%. This implies that the newly developed GRASP can be deployed for the computation of gamma rays' interaction parameters with reasonable accuracy. [ABSTRACT FROM AUTHOR]

This study employed machine learning (ML) algorithms to predict the linear attenuation coefficients (LACs) of materials in inorganic scintillation detectors, which are crucial for evaluating self-shielding properties. Predictions from various ML models were compared with results from the Phy-X/PSD program across different photon energies. The Gradient Boosting Regressor (GBR) model was identified as the most accurate model, achieving a testing set accuracy of 96.40%. This research showcases the potential of ML for efficiently and accurately estimating LACs, with the GBR model showing promise for applications in radiation detection and material science.

Present work analyze the ionizing radiations attenuation behaviour, photon trajectories and dose rate reduction properties of silver tellurite glasses to investigate their potential application in radiation shielding. The shielding capability of five glass systems with different elemental compositions have been calculated with the help of theoretical software: Phy-X/PSD and NIST XCOM. For the photon energy range of 1.00 keV to 100.00 GeV, various shielding parameters are calculated, including attenuation coefficients ( MAC , LAC ), mean free path, half value layer, tenth value layer, effective atomic number, effective electron density, energy build up factors, energy absorption buildup factors, and fast neutron removal cross section. While the energy stopping potentials, projected range of ions (H ^+ , He ^+ , and C ^+ ) has been presented with the help of SRIM software. Additionally photon trajectories and dose rate attenuating behavior of 10 ^5 photons generated from ^137 Cs and ^60 Co sources with activity 200.00 GBq has been studied with the help of particle and heavy ion transport (PHITS) code. It is observed that at both low and high energy levels, the glass composition, labelled S _4 , (70TeO _2 -25Ag _2 O-2Nb _2 O _5 -2BaO-1PbO), exhibits comparable attenuation coefficients to previously recommended glass samples for radiation shielding applications. In addition to S _4 , nine different types of glass samples and polymers with comparable densities to our glass sample, along with water, were included for comparison. The findings indicate that among all the samples tested, S _4 demonstrates the highest and comparable radiation-protective performance, positioning it favourably for such applications.

This study investigates the effect of substituting boron oxide (B 2 O 3) with heavy metal oxides (HEMOs) on the structural, mechanical, and gamma-ray shielding properties of potassium borate (KB) glass systems. The glass compositions analyzed include 80B 2 O 3 –20K 2 O and 65B 2 O 3 –20K 2 O-15HEMO (where, HEMO = BaO, Bi 2 O 3 , or Pb 3 O 4). All samples were prepared using the melt-quenching method, and their amorphous nature was confirmed through X-ray diffraction (XRD). Fourier-transform infrared spectroscopy (FTIR) had revealed BO 3 , BO 4 , and BiO 6 groups beside the B– O –B linkages. The density increased with the addition of HEMOs, following the order: Pb 3 O 4 (KB4) > Bi 2 O 3 (KB3) > BaO (KB2) > and pure KB (KB1). This trend was also observed in the molar volume (Vₘ) and oxygen molar volume (Vₒ), while the oxygen packing density (P ρ) decreased. Mechanical properties assessed using the Makishima-Mackenzie model indicated that KB3 exhibited the highest elastic modulus (Yₘ) and Poisson's ratio (μ). The microhardness (Hₘ) followed the sequence KB2 > KB3 > KB4 > KB1, attributed to the higher bonding energy in KB2. Gamma-ray shielding parameters, including mass attenuation coefficients (MAC), were calculated using Phy-X and XCOM software for photon energies between 0.2835 MeV and 1.333 MeV. KB4 (Pb 3 O 4) showed superior shielding performance with the highest linear attenuation coefficient (LAC) and the lowest half-value layer (HVL) and mean free path (MFP). Despite KB4's high density, KB3 (Bi 2 O 3) is suggested as a more suitable candidate for radiation shielding applications due to its balanced combination of mechanical strength and γ-ray attenuation efficiency. • This study examines the impact of BaO, Bi 2 O 3 , and Pb 3 O 4 on KB glass properties. • Pb 3 O 4 -doped glass (KB4) showed the highest density and best γ-ray shielding. • Bi 2 O 3 -doped glass (KB3) displayed the best mechanical strength and solid radiation shielding. • Bi 2 O 3 -doped glass (KB3) combines strength and shielding, ideal for durable radiation protection. [ABSTRACT FROM AUTHOR]

This paper delves into the effect of replacing B 2 O 3 with CuO on the structural, optical absorption, thermal, mechanical, and gamma(γ)-ray shielding properties of four CKB glasses formulated as (65-y)B 2 O 3 –15Bi 2 O 3 –20K 2 O-yCuO (where y = 0, 0.3, 0.6, and 1.2 mol%). The glasses were created using the melt-quenching technique, and their non-crystalline structure was verified by X-ray diffraction (XRD) analysis. Fourier-transform infrared (FTIR) spectroscopy identified several structural groups, predominantly consisting of BO 3 , BO 4 units, and B– O –B linkages. Thermal properties, assessed via Differential Scanning Calorimetry (DSC), indicated that the glass transition temperature was highest for the 0.3 mol% CuO sample (CKB0.3), demonstrating enhanced thermal stability in comparison to other compositions. Density measurements correlated positively with CuO concentration, peaking at 1.2 mol%, while molar volume, boron molar volume, oxygen packing density, and boron-boron separation distances showed a decreasing trend with increased CuO concentration. UV–Vis absorption spectroscopy indicated a decline in the optical energy gap and an increase in Urbach energy, attributed to the conversion of BO 3 into BO 4 units in the glass matrix. Mechanical properties, evaluated using the Makishima-Mackenzie model, demonstrated enhancements in elastic moduli and micro-hardness with rising CuO concentration. The γ-ray shielding properties (γ-RPs) were examined at energies of 0.662, 1.173, and 1.333 MeV, revealing that both the linear attenuation coefficient and effective atomic number reached their maximum values at 1.2 mol% CuO (CKB1.2). While CKB1.2 exhibited excellent mechanical and γ-ray shielding performance, CKB0.3 excelled in thermal stability and demonstrated γ-ray shielding efficiency comparable to CKB1.2. This suggests that CKB0.3 is a promising candidate for radiation shielding applications requiring a balanced combination of thermal stability and effective γ-ray attenuation properties, particularly at 0.662 MeV. • New B 2 O 3 –Bi 2 O 3 –K 2 O–CuO (CKB) glasses synthesized via melt-quenching with varying CuO concentrations. • XRD, FTIR, DSC and UV-absorption spectroscopy characterized the CKB glasses. • Elastic moduli and micro-hardness improved with CuO concentration. • CKB0.3 showed excellent thermal stability and γ-ray shielding, rivaling CKB1.2, especially at 0.662 MeV. [ABSTRACT FROM AUTHOR]

In this study, radiation shielding composite materials were created by combining epoxy with cement bypass dust (CBPD) at different weight percentages (0%, 10%, 20%, and 30%). The solution casting technique was employed to construct these materials. The FTIR spectra confirmed the formation of the composites and the production of complexes. The morphology and elemental content of the produced composite samples were illustrated using SEM pictures and EDX spectra. In addition, the research findings demonstrated that the composites exhibited improved resistance to changes in temperature as the loading of CBPD increased. The gamma-ray attenuation coefficients of composites consisting of Epoxy + x% CBPD exhibited an increase, along with an increase in the neutron removal cross-section. However, there was a gradual increase in both the mean free path (MFP) as well as the half value layer (HVL) with increasing energy. Additionally, the experimental and theoretical data for attenuation parameters were compared using the Phy-X/PSD software. The relationship between the effective atomic and electron numbers of the Epoxy + x% CBPD composites has been studied. The values of fast and thermal neutron attenuation were analyzed using the NGCal software. In general, these composites are appropriate for use in radiation shielding applications. • Fabrication of polyepoxide (Epoxy) reinforced by cement bypass dust (CBPD) at different weight percentages. • The characteristic analysis of the Epoxy/CBPD composites. • Thermal stability of the Epoxy/CBPD composite increases in presence of CBPD. • The gamma radiation and neutron attenuation properties of the Epoxy/CBPD composites were analyzed. [ABSTRACT FROM AUTHOR]

• Novel Co and W based alloys have been produced. • Photon protection parameters of the alloys have been calculated. • The CoBAs and WBAs can be considered as novel radiation shields. In light of the growing number of applications resulting in high-radiation levels, it is of considerable importance to develop strategies aimed at reducing the negative consequences of radiation exposure. There is a significant requirement for the design of materials capable of withstanding high temperatures, particularly within the nuclear industry. The goal of the study is to develop new cobalt and tungsten based alloys and to examine the structural and radiation shielding properties of the alloys which can be used in nuclear industry and other technological fields. For this purpose, two cobalt based (Co40Al5Ni35Cr5Ta5W7Mo2B1 and Co40Al5Ni35Cr5Ta5W7Nb2) and two tungsten based (W40Ni15Cr15Ti10Mo5Al5Co10 and W40Ni15Cr15Ta5Mo5Al5Co10Nb5) alloys were produced and the radiation shielding performances were investigated. The photon protection of the alloys was calculated by Phy-X/PSD. In addition, SEM-EDS, XRD and EPR results of the alloys were investigated for the structural characteristics. The α-Ti, β-Ti (Mo), ε-W, α-Cr, γ-Co, γ-Ni, γ-Nb matrix phases were observed by XRD phases. An EPR signal with g value of 2.75 was observed for only cobalt based alloys. Among the alloys, tungsten based alloys show higher shielding efficiency than the cobalt based ones. It can be stated that the alloys based on cobalt and tungsten would be of particular importance for shielding in nuclear applications, especially in nuclear reactors operated at high temperatures. [ABSTRACT FROM AUTHOR]

This study investigates the nuclear radiation attenuation characteristics of bioactive glasses with the system (26-x)Na 2 O-xBaO-29CaO–45P 2 O 5 , where x represents the molar percentage of BaO (0, 5, 10, 15). For this purpose, several parameters of shielding gamma radiation, such as the mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Z eff), effective electron density (N eff), atomic cross-section (ACS), electronic cross-section (ECS), equivalent atomic number (Z eq), and transmission factor (TF) were calculated. The calculations were performed across different photon energy ranges (0.015–15 MeV) using Phy-X/PSD software and validated using the WinXCOM program. The results obtained from both the software platforms exhibited a high degree of agreement. Among the investigated glasses, the BNCP-15 glass, which had the highest BaO concentration, demonstrated the highest values for MAC, LAC, Z eff , N eff , ACS, ECS, and Z eq , while displaying the minimum values for HVL, TVL, MFP, and TF. For example, the LAC values at 15 MeV were found to be 0.056, 0.063, 0.070, and 0.077/cm for BNCP-0, BNCP-5, BNCP-10, and BNCP-15, respectively. Consequently, the BNCP-15 glass exhibited superior radiation attenuation performance in comparison to the other BNCP glasses examined in this study. • Four bioactive glasses (Na 2 O–BaO–CaO–P 2 O 5) are investigated for radiation attenuation purposes. • Phy-X/PSD and WinXCOM program are employed for shielding parameters. • Significant influence of BaO content on radiation attenuation characteristics is observed. • High-BaO bioactive glasses are recommended for diverse radiation attenuation uses. [ABSTRACT FROM AUTHOR]

In this study, the interaction cross sections of heavy oxide scintillators, which have a very important place in high energy physics research, with photon and particle radiation were comparatively investigated. In this context, the interaction parameters of six different Ce-doped heavy oxide scintillators were obtained using updated software. The interactions of photons with energies between 1 keV and 100 GeV with scintillators were evaluated in the light of the results produced by the Phy-X/PSD software. In addition to the continuous energy range, calculations were also made on the photon energies emitted with the highest probability of emission from sources 241Am (59.54 keV), 133Ba (356 keV), 22Na (511 and 1280 keV), 137Cs (662 keV) and 152Eu (1460 keV). Additionally, evaluations of energy absorption build-up factors valid under broad beam conditions are also included in this study. Fast neutron absorption cross sections and changes in the range (R) values for heavy particle radiation in the range of 1 keV–20 MeV were also determined with SRIM and ESTAR software. All data obtained depending on energy are explained according to the mass percentages of Lu, Gd, Hf, Y, Al and O elements in the scintillators. The highest interaction cross section for photons was obtained in the Lu 2 Gd 2 SiO 5 (Ce 0.3%) scintillator (HOS2). The interaction cross section of this scintillator was obtained as 3.115 and 0.042 cm2/g at 0.1 MeV and 10 MeV photon energies, respectively. On the other hand, the highest cross-sections of the fast neutrons were observed in the scintillator (HOS5) containing GdAlO 3 (Ce 1.0%) as 0.148 cm−1. This difference in neutron radiation has been explained by calculating the individual attenuation abilities of the elements in the structures. It is hoped that the data obtained will guide researchers working on the detection of different types of radiation. [ABSTRACT FROM AUTHOR]

This study presents the production and comprehensive assessment of a Refractory High Entropy Alloy (RHEA) with a ZrNbTaMoW composition for possible usage nuclear reactor applications. The alloy was synthesized using the mechanical alloying (MA) method, and its radiation properties were examined. Elemental powders of Zr, Nb, Ta, Mo, and W were utilized in equimolar quantities during the 120-hour MA process, conducted under a high-purity Ar atmosphere to prevent oxidation. The obtained HEA was then subjected to a mechano-thermal process to transform it into Refractory High-Entropy Oxide (RHEO) for comparing their radiation-shielding performance under oxide conditions. The characterization of the produced alloys through X-ray diffraction (XRD), scanning electron microscopy (SEM), and electron dispersive spectroscopy (EDS). The photon shielding parameters of the alloys were experimentally obtained for various energies emitted from a 133Ba radioactive source, employing a Canberra UltraLEGe semiconductor detector. Furthermore, theoretical calculations were performed to validate the experimental data and to evaluate the alloys' photon shielding capabilities comprehensively. For this purpose, Phy-X/PSD software was employed to determine mass attenuation coefficients, half-value layer, effective atomic number, and effective electron density. Fast neutron absorption capabilities were determined through the calculation of average absorption cross-sections in the 2–12 MeV energy range. The results showed that the oxidation process significantly diminished the photon absorption capacity of RHEA. • Successfully synthesized a novel ZrNbTaMoW refractory high-entropy alloy (RHEA) through mechanical alloying. • Transformed the RHEA into refractory high-entropy oxide (RHEO) using a mechano-thermal process. • Investigated the structural and gamma-ray absorption capacities of both RHEA and RHEO simultaneously. • Explored fundamental parameters related to photon and particle radiations. • Conclusively determined that the radiation absorption ability of RHEA is significantly higher compared to that of RHEO. [ABSTRACT FROM AUTHOR]

Herein, this study primarily investigates the structural, physical, optical properties, and radiation shielding capabilities of the fabricated glass samples. The bulk (pellet) glass samples with compositions (30-x)BaO-30TiO2-40SiO2-xZrO2 (0 ≤ x ≤ 6), were fabricated using a traditional melt-quenching technique. Further, XRD was performed to validate the amorphous state of the prepared glasses. Density of all the glass samples was calculated using mass-volume formula and observed to be in the range of 3.613–3.821 g/cm3. Additionally, to examine the optical behavior, UV-visible spectroscopy was performed. Indirect band gap energies were estimated from the Tauc’s plots, and found to be 4.191, 4.093, 4.042, and 3.841 eV for glasses BTSZ0, BTSZ2, BTSZ4, and BTSZ6 respectively. Moreover, refractive index and optical dielectric constant were found to be increased such as 2.134–2.201 and 4.554–4.846 with increasing content of ZrO2. Furthermore, radiation shielding behaviour was studied using “Phy-X/PSD” software within the energy range of 0.015-15 MeV. At 0.02 MeV, BTSZ6 (24BaO-30TiO2-40SiO2-6ZrO2) glass exhibited the maximum values for MAC, LAC, HVL, and TVL are 18.078 cm2/g, 69.072 cm− 1, 0.01 cm, and 0.033 cm respectively. The BTSZ6 glass, with 6% ZrO2, demonstrated superior gamma radiation protection and excellent optical and physical properties, making it highly suitable for optoelectronic, photonics, and radiation safety applications. [ABSTRACT FROM AUTHOR]

Gamma-ray, fast neutron and charged particle shielding characteristics of Dy3＋ activated glasses with composition 15Li 2 O-25BaO-(40-x)B 2 O 3 -20P 2 O 5 -xDy 2 O 3 (x = 0, 0.2, 0.4, 0.6, 0.8, and 1.0 mol %) are analyzed in a wide incident energy for the first time. For gamma-ray shielding analysis, mass attenuation coefficient (MAC), mass energy absorption coefficient (μ e n), linear attenuation coefficient (LAC), mean free path (MFP), half-value layer (HVL), atomic cross-section (ACS), electronic cross-section (ECS), effective atomic number (Z e f f), equivalent atomic number (Z e q), effective conductivity (C e f f), effective electron density (N e f f), buildup factors (EABF and EBF), and kinetic energy released per unit mass of the absorbing material (KERMA) are calculated by using Phy-X/PSD and PAGEX softwares. For fast neutrons, fast neutron removal cross-section (FNRCS) is computed for all glass samples. For charged particle shielding analysis, mass stopping power (MSP), projected range (Rp), radiation yield (Ry), Z e f f and N e f f are computed using SRIM, ESTAR and PAGEX softwares. It is found that the glasses with increasing Dy3＋ have higher shielding potential. This suggests that the LBPDy1.0 sample has a potential use as shielding material for various applied fields. • Photon and neutron protection parameters of Dy3＋ activated glasses have been calculated. • Charged particle protection parameters of Dy3＋ activated glasses have been calculated. • Dy3＋ activated glasses with a composition of 15Li 2 O-25BaO-(40-x)B 2 O 3 -20P 2 O 5 -xDy 2 O 3 can be used as shielding materials. [ABSTRACT FROM AUTHOR]

In this study, the radiation shielding effectiveness of iron phosphate glass (Fe 2 O 3 –P 2 O 5) doped with antimony (Sb) and tellurium (Te) is assessed in detail using advanced computational methods. The projected range, mass stopping power, and KERMA (Kinetic Energy Released per unit MAss) for fourteen different iron phosphate glass samples are calculated through the PAGEX and SRIM software. Mass attenuation coefficients, linear attenuation coefficients, mean free path, half value layers, tenth value layers, and effective atomic number are determined in 0.015–15 MeV energy range. The research reveals that doping iron phosphate glass with Sb 2 O 3 significantly enhances its shielding capabilities when compared to the inclusion of TeO 2. Another important aspect is, the IPGSb50 sample exhibited the highest KERMA values, indicating its exceptional capacity for energy absorption from ionizing radiation. Additionally, the IPGSb50 sample exhibited the lowest projected range for alpha particles, also this sample demonstrated a similar prowess in limiting the penetration of proton particles. Our findings indicate that the incorporation of Sb 2 O 3 and TeO 2 into iron phosphate glass matrices results in a noticeable improvement in gamma radiation shielding effectiveness. These doped glasses could serve as potent alternatives to traditional lead-based shielding materials, offering a safer and potentially more effective barrier against a variety of radiation types. • Investigated radiation shielding in iron phosphate glass doped with antimony and tellurium using advanced computations. • Analysed fourteen samples for mass stopping power, KERMA values, and gamma attenuation parameters. • Found antimony-doped glass significantly outperforms tellurium-doped glass in radiation shielding effectiveness. • Research implications include applications in medical imaging, nuclear energy, and space exploration sectors. [ABSTRACT FROM AUTHOR]

Emission of radiation is a significant phenomenon having impacts on various fields, and its harmful effects must be minimized. To achieve this, radiation protection and dosimetry have been developed to ensure safe radiation limits. In this experimental study, we investigated the gamma-ray shielding properties of a composite material made from natural rubber with six different proportions of Barium Tungstate (ranging from 0 to 100 phr). The study revealed that the addition of Barium Tungstate (BaWO 4) to natural rubber significantly improved the characteristics of gamma radiation shielding. The composite containing maximum proportion of BaWO 4 (NRBW-100) exhibited the highest linear attenuation coefficient (LAC) value, measuring 0.307 cm-1 at an energy of 662 keV. At the same energy value, the LAC values were found to vary from 0.137 to 0.307 cm-1 across samples having different concentrations of BaWO 4 (0 to 100 phr). To further assess the shielding properties, simulations were conducted using the Phy-X/PSD code, and the characteristic parameters such as mass attenuation coefficient (MAC), mean free path (MFP), half-value length (HVL), tenth-value length (TVL), effective atomic number (Z eff), effective electron density (N eff), effective conductivity (C eff), and fast neutron removal cross-section (FNRCS) were theoretically evaluated. FNRC values range from 0.068 cm-1 to 0.108 cm-1 across concentrations of BaWO 4 from 0 to 100 phr. Experimental measurements showed good agreement with theoretical calculations obtained from simulation results. We have also compared the shielding characteristics of these samples with that of other commonly used materials. • BaWO 4 in natural rubber forms a flexible, lead-free gamma radiation shield. • NRBW-100 coded composite provided remarkable gamma radiation shielding enhancement. • NRBW-100 had highest LAC at 662 keV: 0.307 cm-1, indicating superior gamma radiation shielding. • FNRC varied from 0.068 cm-1 to 0.108 cm-1 across BaWO 4 concentrations (0 to 100 phr). • Experimental measurements closely matched with Phy-x/PSD simulations, validating the accuracy of our calculations. [ABSTRACT FROM AUTHOR]

In this study, the gamma-ray attenuation properties and transmission factors of different types of glasses formed in the (B 2 O 3) 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. • Behavioural changes as a function of increasing HMO are investigated. • MCNPX and Phy-X/PSD are utilized for calculations. • TF values and shielding parameters are determined. • A straight correlation is found between HMO and shielding properties. • S1 is recommended as a suitable shield. [ABSTRACT FROM AUTHOR]