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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]

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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]

The melt quenching technique was utilized to prepare a novel mixed alkali bioglass composition, denoted as 30B2O3–20SiO2–xNa2O–(20–x)Li2O–20CaO–10ZnO, where x = 0,5,10,and 20 and samples codes were BSCZ0, BSCZ5, BSCZ10, BSCZ15 and BSCZ20. The sample code of present samples indicate as BSCZ0 to The glass properties were evaluated using density, FTIR, and radiation shielding capacity, and the simulated body fluid (SBF) solution was prepared according to Kokubo's method. The bio-activeness of the prepared glasses was confirmed by XRD and FTIR spectra, which exhibited crystalline peaks at various reflections due to the formation of calcite and hydroxyapatite layers on the glass surface. The FTIR spectra revealed the formation of hydroxyapatite layers after fourteen days of SBF treatment, as evidenced by the strong intensive peaks around 1020 cm−1. The experimental density values vary between 3.1926 g/cc to 3.1605 g/cc. The glass density decreased with increasing Na2O content due to the decreasing number density correlated to the alkali content. To predict the glass density, an artificial intelligence density model was applied to the present glasses, which utilized 10,000 oxide glass samples. Among the different regression models tested, random forest regression produced the best R2 value (0.917), followed by artificial neural network and polynomial regression. In the case of RFR the predicted density values varies from 3.1626 g/cc to 3.1305 g/cc which were closer values to the experimental density values. The radiation shielding properties of present glasses studied by Phy-X/PSD program and simulated by FLUKA code in the photon energy range of 0.015–15 MeV. Results show that there is a good agreement between the obtained results. BSCZ0, which was free of Na2O, exhibited the highest values of mass (µm) and linear (µ) attenuation coefficients compared to all other glasses, and the effective atomic number (Zeff) achieved the same trend as µm and µ. Sample BSCZ0 also exhibited the lowest values of half value layer (HVL) parameter at all incident photon energies. [ABSTRACT FROM AUTHOR]

Tungsten with its superior features such as high melting point and relatively high thermal conductivity is significant for many high temperature applications. The materials, including tungsten, which have important mechanical properties should also be investigated by their radiation attenuating abilities. The goal of the study is to contribute to the carried out studies from a different perspective by calculating radiation-matter interaction parameters of self-passivating tungsten alloys. Radiation shielding capabilities of the alloys were determined in the range of 1 keV - 100 GeV by Phy-X/PSD code. XCOM, a well-known code, was also used for seeing the validity of obtained mass attenuation coefficients of the alloys. It was observed that half value layer and mean free path values of the studied alloys are lower, and mass attenuation coefficients are higher than those of previously reported alloys. The alloys with higher amounts of tungsten and yttrium have higher shielding ability, while the alloys with lighter elements titanium and silica have less. Additionally, depending on the obtained fast neutron removal cross section values, the studied self-passivating tungsten alloys can be also evaluated for neutron shielding. It can be concluded that the self-passivating alloys have good radiation protection potentials besides the significant mechanical properties. [ABSTRACT FROM AUTHOR]

All-in-one radiation shielding is an emerging concept in developing new-generation radiation protection materials since various forms of ionizing radiation, such as neutrons and gamma rays, can occur simultaneously. In this study, we examine the ability of transition metal borides to attenuate both photon and particle radiation. Specifically, fourteen different transition metal borides (including inner transition metal borides) are selected for examination based on their thermodynamic stabilities, molecular weights, and neutron capture cross-sections of the elements they contain. Radiation shielding characteristics of the transition metal borides are computationally investigated using Phy-X/PSD, EpiXS and NGCal software. The gamma-ray shielding capabilities of the transition metal borides are evaluated in terms of the mass attenuation coefficient (μm), the linear attenuation coefficient (µ), the effective atomic number (Zeff), the half-value layer (HVL), the tenth-value layer (TVL), and the mean free path (MFP). The mass and linear attenuation factors are identified for thermal and fast neutrons at energies of 0.025 eV and 4 MeV, respectively. Moreover, the fast neutron removal cross-sections (∑R) of the transition metal borides are calculated to assess their neutron shielding abilities. The results revealed that borides of transition metals with a high atomic number, such as Re, W, and Ta, possess outstanding gamma shielding performance. At 4 MeV photon energy, the half-value layers of ReB2 and WB2 compounds were found as 1.38 cm and 1.43 cm, respectively. Most notably, these HVL values are lower than the HVL value of toxic Pb (1.45 cm at 4 MeV), which is one of the conventional radiation shielding materials. On the other hand, SmB6 and DyB6 demonstrated exceptional neutron attenuation for thermal and fast neutrons due to the high neutron capture cross-sections of Sm, Dy, and B. The outcomes of this study reveal that transition metal borides can be suitable candidates for shielding against mixed neutron and gamma radiation. [ABSTRACT FROM AUTHOR]

Moduli of elasticity and the ability of gamma radiation shielding as well as transmission factor (TF) of four samples of tungsten bario-phosphate glasses with chemical formula xBaO-40WO3-(60-x)P2O5: (x = 10, 20, 30, and 40 mol% glasses) have been examined. The glass samples have been coded as S1: 10BaO-40WO3-50P2O5, S2: 20BaO-40WO3-40P2O5, S3: 30BaO-40WO3-30P2O5, and S4: 40BaO-40WO3-20P2O5. Makishima-Mackenzie model, the newly online Phy-X/PSD software, and Monte Carlo code were applied to achieve the mentioned purposes. The total dissociation energy (Gt) values were decreased from 62.58 (kJ/cm3) for S1 glasses to 55.92 (kJ/cm3) for S4 glasses. The total packing density (Vt) was 0.613, 0.626, 0.612, and 0.643, for S1, S2, S3, and S4, respectively. Values of Young's (EMM) modulus were 76.759 GPa, 75.631 GPa, 71.167 GPa, and 71.966 GPa and Poisson's ratio (σMM) possessed the values 0.273 GPa, 0.278 GPa, 0.273 GPa, and 0.284 GPa for S1, S2, S3, and S4, respectively. The S4 sample possessed the highest values of both linear (µ) and mass (µm) attenuation coefficients. However, (µ, µm)S1 < (µ, µm)S2 < (µ, µm)S3 < (µ, µm)S4. Also, The S4 sample possessed the lowest values of half value layer (HVL), tenth (TVL) value layers, and mean free path (MFP) among all studied glasses. Therefore, (HVL, TVL, MFP)S4 < (HVL, TVL, MFP)S3 < (HVL, TVL, MFP)S2 < (HVL, TVL, MFP)S1. Both effective atomic number (Zeff) and electron density (Neff) of the investigated glasses have as similar trend. In terms of transmission factor (TF), the sample S4 achieved the minimum values at a thickness of 3 cm. However, the S4 sample exhibited superior radiation shielding characteristics. [ABSTRACT FROM AUTHOR]

Ionizing radiation is becoming increasingly prevalent in various applications on Earth and in space. This study evaluates the radiation shielding performance of five quaternary glass systems with different chemical compositions of 60SiO 2 -35Pb 3 O 4 -(5-x)ZnO-xWO 3 (0 ≤ x ≤ 5 mol%) using theoretical software and Monte Carlo simulations. The study calculates various shielding parameters, including attenuation coefficients, mean free path, half value layer, tenth value layer, effective atomic number, electron density, and build-up factors, for the photon energy range of 1 keV to 100 GeV. PZSW3 and PZSW5 show comparable attenuation coefficients at low and high energy levels, which are higher than the other selected samples. Additionally, PZSW5 has a neutron removal cross-section of 0.120 cm−1, slightly less than PZSW4's 0.122 cm−1 and greater than the other three samples. On average, PZSW5 (60SiO 2 -35Pb 3 O 4 -5WO 3) exhibits greater radiation attenuation than other samples and most of the compared 19 samples in terms of shielding parameters. The study also analyzes the trajectories of 10 5 photons in the system and finds that PZSW5 has the most effective radiation protection capability among the glass composites studied. [ABSTRACT FROM AUTHOR]

Investigations on metallic glasses have increased significantly due to their obvious qualities such as high glass–forming ability, corrosion resistance, and chemical, mechanical, and magnetic properties. By considering the importance of Cobalt– and Iron–based metallic glasses with various Tantalum concentrations, a Monte Carlo simulation (Geant4 code) and Phy–X/PSD software were used to investigate their gamma–ray attenuation properties, such as mass attenuation coefficient, effective atomic number, and half–value layer for different photon energy ranges. The mass attenuation coefficient (MAC) was calculated numerically using the Phy–X/PSD software between 0.015 and 15 MeV, and the results were compared to Monte Carlo simulations. The mass attenuation coefficients of the alloys were ranged between 108.6 and 94.3 cm2/g for lowest the photon energy, while reduced to 0.0458 cm2/g at the high energy region. These results showed that the radiation protection effectiveness values may be correlated with the alloys' magnetization. The obtained results revealed that Tantalum density and larger atomic numbers are the most important factors in improving the radiation attenuation capabilities and then the shielding performance of the investigated glassy alloys. [ABSTRACT FROM AUTHOR]

The impact of TeO2 on the elastic and radiation shielding properties of phospho-tellurite glasses doped with varying amounts of Sm2O3 has been studied. The elastic properties, such as packing factor, packing density, Young's modulus, bulk modulus, shear modulus, and Poisson's ratio, were determined by using the Makashima-Mackenzie and Rocherulle models. The gamma-ray shielding parameters, such as mass attenuation coefficient, half-value layer, tenth-value layer, effective atomic number, equivalent atomic number, exposure buildup factor, and energy absorption buildup factor, were calculated using Phy-X/PSD software in the energy range from 0.015 to 15 MeV at penetration depths up to 40 mean free paths for selected glasses. The fast neutron removal cross section was also determined using Phy-X/PSD software. The results show that the mass attenuation coefficient decreases with increasing photon energy but is not influenced by the addition of Sm2O3. The exposure buildup factor values and energy absorption buildup factors have lower values in the low- and high-energy regions and higher values in the intermediate energy region. The 1.5 mol % concentration of Sm2O3 in the selected glass shows higher exposure buildup factor and energy absorption buildup factor values in the intermediate energy region. Among the selected glasses, PZBTS1.5 has the highest value of fast neutron removal cross sections. The high density, high effective atomic number, and transparency to visible light of these materials indicate that they can be used as shielding materials in nuclear reactors and nuclear technology. [ABSTRACT FROM AUTHOR]

The aim of this study is to assess the individual gamma-ray transmission factors (TFs) and some fundamental gamma-ray attenuation properties of several types of glasses based on WO3–TeO2–B2O3 glasses system. MCNPX (version 2.7.0) is used for the calculation of TFs. Other critical parameters are determined using the Phy-X/PSD program. To determine the TFs of studied glasses, several medical radioisotopes are determined along with their characteristic gamma-ray energies. The superior values for the investigated parameters are found in glass sample S6. Furthermore, the exposure build-up factor and energy absorption build-up factor values for glass sample S6 were the lowest. S6 glass sample with the chemical composition 0.03833B + 0.26075O + 0.11591Zn + 0.52783Te + 0.05718W and a density of 3.3579 g/cm3 is found to have exceptional gamma-ray attenuation qualities, according to our findings. It can be concluded that the prospective attributes of WO3-doped glass systems and associated glass compositions would be beneficial for scientific community in terms of providing a clearer view for some advanced applications of these glass types.

We report some fundamental gamma-ray shielding properties and individual transmission factors (TFs) of five distinct glass samples with a nominal composition of xSb2O3·(40 − x)PbO·60B2O3·0.5CuO and (where; 0 ≤ x ≤ 40 mol%). Phy-X/PSD and MCNPX (version 2.7.0) Monte Carlo code are utilized to determine several critical parameters, such as cross-sections, attenuation coefficients, half and tenth value layers, build-up factors, and TFs. A general transmission setup is designed using basic requirements. Accordingly, TFs are evaluated for several medical radioisotopes. Next, the gamma-ray shielding parameters and TFs are assessed together in terms of providing the validity of the findings. Our results showed that there is a positive contribution of increasing Sb2O3 amount in the glass matrix owing its direct effect to the density increment as well. This positive effect on gamma-ray shielding properties is also observed for decreasing mean free path values from S1 to S5 samples. The exposure build-up factor (EBF) and energy absorption build-up factor (EABF) values, increasing the quantity of Sb2O3 supplementation, resulted in a general reduction in EBF and EABF values (i.e., from 0.5 to 40 mfp). When the quantity of Sb2O3 rises from S1 to S5, the collision rate of incoming gamma rays in glass samples increases significantly. The TF figures reveal that S5 showed the least transmission behavior across all the above-mentioned studied glass thicknesses. It can be concluded that increasing the Sb2O3 additive is a beneficial and monotonic technique, when the gamma-ray shielding qualities or TF values must be further enhanced.

Investigations have been made on the mechanical and gamma-ray attenuation properties of the zinc bismuth-borate ternary glass system with the chemical formula (70-x)Bi2O3–xB2O3–30ZnO, where x = 20 (S1), 25 (S2), 30 (S3), 40 (S4), 45 (S5), and 50 (S6) mol%. Makishima-Mackenzie model and Phy-X/PSD software were used to accomplish this goal. Our research showed that the packing density (Vt) and dissociation energy (Gt) values reduced from S1 glass sample (with B2O3 = 20 mol% and Bi2O3 = 50 mol%) to S6 glass sample (with B2O3 = 50 mol% and Bi2O3 = 20 mol%), respectively, from 0.522 to 0.352 and from 31.53 kJ/cm3 to 26.97 kJ/cm3. By increasing the amount of B2O3 in the glasses, the efficiency of their mechanical features was reduced. The S1 glass sample's linear (µ) and mass attenuation (µm) coefficients had the highest values among the glass materials examined, i.e., (µ, µm)S6 < (µ, µm)S5 < (µ, µm)S4 < (µ, µm)S3 < (µ, µm)S2 < (µ, µm)S1. The S1 glass sample exhibits the lowest values for half value layer (T0.5) and mean free path (λ) of all the examined glasses. Consequently, (T0.5, λ)S6 > (T0.5, λ)S5 > (T0.5, λ)S4 > (T0.5, λ)S3 > (T0.5, λ)S2 > (T0.5, λ)S1. The analyzed glasses' effective atomic numbers (Zeff) follow the same trend for mass and linear attenuation coefficients. Our results show that the values of exposure (EBF) and energy absorption (EABF) accumulation factors decreased with increasing Bi2O3 and lowering B2O3 reinforcement for all mean free path values (i.e., from 0.5 to 40 mfp). Results show that of all the glasses under study, the S1 glass sample has the best gamma-ray shielding properties. [ABSTRACT FROM AUTHOR]

In this study, glass composition based on tungsten oxide (WO3) doped tellurium, titanium glasses: (100 − x − y) TeO2–xTiO2–yWO3: where (x = 5) and (y = 5, 10, 15, 20, 25) coded as TT5W5, TT5W10, TT5W15, TT5W20, and TT5W25 were investigated for shielding properties against ionizing radiation. Gamma radiation shielding parameters such as mass attenuation coefficients (MAC) are calculated through MCNPx code and Phy-X/PSD software in the energy range of 0.015–15 MeV. Obtained MAC values are then used to calculate other gamma radiation shielding parameters such as mean free path (MFP) and effective atomic number (Zeff). Besides this, the exposure buildup factor (EBF) was also calculated by using EXABCal software at different penetration depths (PDs) in the energy range of 0.015–15 MeV. Sample TT5W25, which has a larger WO3 content of 25 mol% shows higher values of MAC and lower values of MFP among all the examined glass samples. Our investigated TeO2–TiO2–WO3 glass samples possess the lowest MFP values in comparison with the different types of concretes and commercially available shielding glasses. In addition, fast neutron shielding characteristics in light of fast neutron removal cross-section have also been computed. Glass sample TT5W25 possesses the higher values of fast neutron removal cross-section as compared to the other glass samples. The results indicate that the adding up of WO3 improves shielding against the fast neutron and gamma radiation. [ABSTRACT FROM AUTHOR]

This study aimed to assess the radiation shielding properties of ten low-density high-entropy alloys (LWHEAs) using Phy-X/PSD software to analyze various shielding parameters, such as attenuation coefficients (μm and μ), mean free path (λ), effective atomic number (Zeff), and removal cross-section (ΣR), in the energy range of Image 1 to Image 2. A comprehensive evaluation was performed to compare the attenuation outcomes provided by HEAs with a range of shielding materials documented in the literature. The study also calculated the build-up factors (BUFs) of the alloys by using the GP-fitting interpolation method. The stopping power of the alloys against H1/He+2 ions was analyzed using the SRIM Monte Carlo code, considering total stopping power (TSP) and projected range (PR). The results indicated that HEA8 (Al3.88Cr14.95Mo27.58Nb26.71Ti13.76Zr13.11) had the best performance in terms of shielding against γ-rays, fast neutrons, and H1/He+2 ions, as it achieved the highest values of parameters such as μm, μ, Zeff, and ΣR, along with the lowest values of HVL, TVL, λ, BUFs (Image 3Image 4), TSP, and PR. On the other hand, HEA10 (Mg10.77Al11.96Mn24.35Fe24.75Cu28.17) had the lowest BUFs in both lower (Image 5Image 4) and higher (Image 6Image 4) energy regions. The order of μm for the alloys was found to be HEA5

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.

The mechanical and shielding characteristics of (100 − x)% NaPO3−x% MoO3 (where x = 20,40,60) and (100-x)% NaPO3-x% WO3 (where x = 20,40,60) glass systems were studied to evaluate their ability to act as shielding materials. Using the Makishima-Mackenzie theory, the mechanical parameters of all glass samples and their dependence on the MoO3 content (mol%) for the first series and on the WO3 content (mol%) forthe second glass series were also investigated. The results showed thatthe mechanical properties and micro hardness were significantly enhanced by increasing the concentration of MoO3 from 20 to 60% for the first glass series and the concentration of WO3 from 20 to 60% for the second glass series. The shielding parameters of both glass series were also studied. The mass attenuation coefficient (μm) was computed by the Phy-X/PSD program for energies ranging from 0.015 to 15 MeV. The results are in excellent agreementwith the results calculated by the WinXCom software program and the results simulated by Geant4 Monte Carlo simulation. The computed μm values were used to deduce the other significant shielding parameters for all glass samples. The fast neutron removal cross-sections of all glass samples were examined and compared with those of standard materials. A strong correlation between the shielding parameters and the molar volume, oxygen packing density, and oxygen molar volume was found. The results revealed that thestudied glasses possessed superior shielding properties, especially the glass sample 0.4NaPO3-0.6MoO3 (mol%) which showed the most promising characteristics for radiation-shielding applications among the tested glasses.

The role of dysprosium oxide (Dy2O3)-doped PbO–B2O3–SiO2 glasses on gamma and neutron radiation shielding properties was investigated and evaluated in terms of potential use in radiation protection. The glass composition was arranged according to the formula (55–x)B2O3–25PbO–20SiO2–xDy2O3 (0 ≤ x ≤ 5) (mol%). The Monte Carlo simulation (MCNPX) code was utilised to simulate the mass attenuation coefficient (MAC) of the glasses. When photon energies were in the range of 0.015–15 MeV, the resulting simulated mass attenuation (µm) values were evaluated with conventional Phy-X/PSD database findings. The Phy-X/PSD collected data and the predicted µm findings were in good agreement. The half-value layer (HVL), effective atomic number (Zeff), exposure and energy absorption build-up factors (EBF and EABF) of the glass samples were evaluated. 5 mol% Dy2O3-doped sample has significant γ-ray shielding efficacy in the complete energy range due to lower values of HVL, higher values of MAC and effective atomic number. The build-up factors follow a similar pattern with incident photon energy and penetration depth, growing on a steeply increasing trend up to a maximum at 0.5–1.5 MeV energy, then gradually reducing as photon energy increases up to 15 MeV. The build-up factors show the same routine with penetration depth and incident photon energy. They tend to steeply rise to a peak level at 0.5–1.5 MeV energy, then gradually decrease as the photon energy increases to 15 MeV. Also, the neutron shielding ability was detected and the effective removal cross-section Σ R (cm−1) was estimated theoretically. Due to the greatest value of effective removal cross-section, 5 mol% Dy2O3-doped glass exhibits stronger neutron shielding characteristics than the other glass samples. [ABSTRACT FROM AUTHOR]

The mechanical properties and radiation attenuation competence of Tb3+ ions doped boro-germanate-aluminiophosphate (BGAP) glasses with codes Tb15, Tb20, Tb25, Tb30, Tb35, and Tb40 have been investigated. Bond compression model (B–C) and Phy-X/PSD software are used to achieve these aims. All elastic moduli were reduced with increasing the Tb2O3 content in the BGAP glasses. Values of bulk (KB–C) elastic modulus were possessed decreasing from 86.676 GPa for Tb15 glass sample to 80.205 GPa for Tb40 sample. The values of Young's (EB-C) modulus were found to decrease from 118.197 to 115.641 Gpa and Poisson's ratio (σB-C) of the BGAP glasses were reduced from 0.272 to 0.259. The highest values of linear (μ) and mass (μm) attenuation coefficients were possessed for the Tb40 glass sample. Therefore, (mass, linear)Tb40 > (mass, linear)Tb35 > (mass, linear)Tb30 > (mass, linear)Tb25 > (mass, linear)Tb20 > (mass, linear)Tb15. Half value layer parameter (T1/2) and mean free path (λ) of BGAP glasses were have a similar trend; (λ, T1/2)Tb40