Search

The impact of chromium oxide (Cr2O3) on the organizational, physical, mechanical, and photon shielding qualities of new chromium borate glasses with the chemical composition 50B2O3-25Bi2O3-25Li2O3-xCr2O3 (x=0 (Cr-00), 0.2 (Cr-0.2), 0.4 (Cr-0.4), 0.8 (Cr-0.8), and 1.5 (Cr-1.5) wt%) is investigated. The amorphous behavior of these glasses was verified via X-ray diffraction (XRD) and scan electron microscope (SEM) micrographs. Fourier transform infrared (FTIR) spectra of prepared glass samples revealed the presence of absorption bands due to Cr3+ ions. The density (ρglass) increased as the Cr2O3 concentration increased. The mass attenuation coefficients (MACs) of the proposed glasses were evaluated via the FLUKA code, XCOM program, and Phy-X/PSD software. The MACs values followed this trend: (MAC)Cr-00 < (MAC)Cr-0.2 < (MAC)Cr-0.4 < (MAC)Cr-0.8 < (MAC)Cr-1.5. At 0.015 MeV, the calculated linear attenuation coefficient (LAC) values were 127.913, 133.559, 137.984, 147.034, and 156.212 cm-1 for the Cr-00, Cr-0.2, Cr-0.4, Cr-0.8, and Cr-1.5 glass samples, respectively. The half-value layer (HVL) and mean free path (MFP) values followed this trend: (MAC,MFP)Cr-00 > (MAC,MFP)Cr-0.2 > (MAC,MFP)Cr-0.4 > (MAC,MFP)Cr-0.8 > (MAC,MFP)Cr-1.5. The Cr-00 glass sample had the lowest effective atomic number (Zeff) values, while the Cr-1.5 glass sample had the highest. The calculated exposure buildup factor (EBF) values decreased as the Cr2O3 content increased. The Cr-1.5 sample had a higher effective removal cross-section for fast neutrons (ΣR) value than other radiation shielding materials. The addition of Cr2O3 increased the rigidity and elastic constants (Young's (Y), bulk (K), shear (G), and longitudinal (L) moduli) and improved the level of radiation shielding provided. The prepared glasses can be used as gamma and neutron shielding tools in the medical area. [ABSTRACT FROM AUTHOR]

In this research paper, we studied the optical and nuclear shielding efficiency of newly developed BGO glasses with the following compositions (in wt%): 32Bi 2 O 3 –68GeO 2 , 42Bi 2 O 3 –58GeO 2 , 47Bi 2 O 3 –53GeO 2 , 52Bi 2 O–48GeO 2 , 62Bi 2 O 3 –38GeO 2. BGO glasses were prepared by traditional melt quenching method. To obtain the band gap values of fabricated BGO glasses, optical absorption spectra were used for evaluation of optical properties. The mass attenuation coefficients (μ/ρ) were achieved for prepared glasses at 0.015–15 MeV photon energies employing MCNPX Monte Carlo code and WinXcom program. Moreover, broad-range of nuclear shielding parameters for gamma ray, neutrons and charged particles such as mass attenuation coefficient, half value layer, effective atomic number, buildup factors, mass stopping powers, projected ranges, fast neutron removal cross sections and damage factors were calculated. The refractive index is calculated from E opt , As Bi 2 O 3 concentration is enhanced, E opt is also increased as well as the optical electronegativity and consequently the refractive index. In addition, the results showed that BIGE5 glass sample with highest Bi 2 O 3 contribution has excellent nuclear radiation shielding ability among the other fabricated glass samples. [ABSTRACT FROM AUTHOR]

This paper studies the radiation attenuation properties and build up (EBF and EABF) factors of different types of bioactive glasses in the 0.015–15 MeV photon energy range. EBF and EABF values of investigated bioactive glasses are determined by using the G-P fitting method. Moreover, effective removal cross-section values, alpha/proton mass stopping power (MSP), and alpha/proton projected range values (PR) are determined for fast neutrons and charged particles. The investigation indicates that TiO 2 additive in the bioactive glasses causes considerable variations in the attenuation properties of bioactive glasses. The results show that the BT2.5 bioactive glass sample has highest attenuation performance among the samples. [ABSTRACT FROM AUTHOR]

Structural and gamma-ray/neutron radiation protection characteristics of (50-x)B 2 O 3 +40PbO+10Li 2 O + xAg 2 O (x = 0, 2.5, 5, 7.5, 10 wt fraction (wt) %) glass system encoded BPLA glasses have been extensively surveyed. The structure of the prepared glasses has been investigated over X-Ray Diffraction (XRD) patterns. With the addition of Ag 2 O, the glasses' amorphous structures have not deteriorated, and the density and molar volumes of BPLA glasses inversely varied. Mass attenuation coefficients (MAC) for BPLA glasses have been generated enjoying Monte Carlo N-Particle- Extended (MCNPX) simulation code for the broad gamma-ray energy range of 0.015–15 MeV. It has been observed that the MAC values of the BPLA10 glass are higher than the others at all energy levels. Furthermore, while Ag 2 O concentration in the glass has increased, Half Value Layer (HVLs) Energy Absorption and Exposure Buildup Factors (EABFs, and EBFs) have dropped off for photon energies which are important for shielding applications. It has been noticed from these results that owning higher equivalent atomic number (Zeq) values, BPLA10 can be employed effectively for gamma-ray attenuation. Lastly, the results found for fast neutron removal cross-sections (∑ R) have shown that the Ag 2 O additive grew the density and ∑ R values of the glasses. As with photon shielding, it is observed that BPLA10 glass can be more preferable in terms of neutron retention according to other glasses. One can conclude that Ag 2 O enhances the shielding capacity of the glass system studied and BPLA10 glass can be considered as a good material for gamma-rays/fast neutrons shielding. • A novel B 2 O 3 –PbO–Li 2 O–Ag 2 O glass system has been fabricated. • Nuclear shielding characterization of fabricated glasses was studied. • The theoretical WinXCOM data were compared with simulated MCNPX data. • Amorphous structure of the glasses were verified by XRD measurements. • BPLA10 glass sample with highest Ag2O contribution has excellent nuclear radiation shielding ability. [ABSTRACT FROM AUTHOR]

• Newly developed tellurium oxide glasses have been fabricated. • Nuclear shielding characterization of fabricated glasses has been extensively studied. • TeO 2 concentration has directly affected on studied glassy systems. • TEO6 has better performance in terms of shielding purposes than other glass samples. Newly developed glasses were produced using different compositions as follows (in wt.%): (85TeO 2 -15ZnO, 85.00TeO 2 -12.95ZnO-2.05Al 2 O 3, 85.40TeO 2 –3.20PbO-6.97ZnO-4.43Na 2 O, 83.5TeO 2 -16.5BaO, 82.77TeO 2 –17.23Nb 2 O 5, 54.6TeO 2 -22.6WO 3 -22.8Bi 2 O 3). The acquired mass attenuation coefficients (μ/ρ) were used to determine another vital parameters for gamma-ray shielding performance namely mean free path (MFP), half value layer (HVL), tenth value layer (TVL), energy absorption buildup factor (EABF), exposure buildup factor (EBF), effective atomic number (Z eff), respectively. Simultaneously, effective removal cross section (∑R) values for fast neutrons, proton projected range (PPR), alpha projected range (APR), proton mass stopping power (PMSP), alpha mass stopping power (AMSP), neutron absorption parameters (absorption neutron scattering cross section (σ abs)), SAFE factors and relative dose distribution (RDD) have been investigated for fabricated glass samples. The results showed that the 54.6TeO 2 -22.6WO 3 -22.8Bi 2 O 3 composition has the best performance in terms of nuclear shielding purposes. It is worth recommending the continuous investigations on chemical combinations and changes of TeO 2 concentration for future applications. [ABSTRACT FROM AUTHOR]

Ceramic concretes, with their exceptional durability and ability to incorporate a high percentage of heavy metal oxides, are of critical importance for nuclear radiation facilities, offering superior radiation attenuation characteristics essential for long-term safety and protection. This study presents a detailed evaluation of the gamma-ray shielding properties of various concrete composites, including Standard Concrete and Heavy Concretes (HC series), with densities ranging from 1.94 g/cm3 to 4.54 g/cm3. Utilizing computational methods, we analyzed several gamma-ray and neutron shielding parameters such as mass attenuation coefficients, linear attenuation coefficients, half and tenth value layers, mean free paths, exposure build-up factors, effective atomic number (Z eff), effective electron density (N eff), fast neutron effective removal cross-section (Σ R), and photon transmission factors (TFs). Our research reveals that the shielding efficacy of concrete is intrinsically linked to its density and elemental composition, with higher densities and the incorporation of heavy elements leading to enhanced attenuation capabilities. Among the concretes studied, Limonite with Steel Punch LS-a, which contains 74.53% Fe in its structure, exhibited the lowest transmission factors (TFs) across all tested thicknesses and energy levels (0.662, 1.1732, and 1.3325 MeV), indicating its superior photon attenuation potential. It can be concluded that the concrete samples with a higher Fe (iron) content in their structure demonstrate clear superiority in gamma-ray attenuation properties. [ABSTRACT FROM AUTHOR]

This study aimed to examine nuclear radiation shielding properties of a novel glass system, which has nominal compositions (40-x) B 2 O 3 +40Pb 3 O 4 +20ZnO + xEr 2 O 3 with several substitution proportions of Er 2 O 3 (x = 0, 1, 2, 3, 4 and 5). The conventional solid-state method was utilized to fabricate the Er 2 O 3 doped glasses. To obtain the amorphous nature of manufactured glass samples, X-ray diffraction (XRD) patterns were investigated. Moreover, mass attenuation coefficients (μ/ρ) of the prepared glasses were adjusted by employing MCNPX simulation code. Other important gamma-ray attenuation parameters namely Half Value Layer (HVL), Mean Free Path (MFP), Effective and Equivalent Atomic Numbers (Z eff and Z eq) and Exposure Buildup Factor (EBF) of the glasses were also extensively addressed by obtaining mass attenuation coefficients (μ/ρ). The outcomes indicated that the Er 2 O 3 additive enhances the photon attenuation qualification of the glasses. Moreover, the success of glasses in reducing fast neutrons was judged by calculating effective removal cross sections (Σ R). The results showed that increasing Er 2 O 3 additive upgraded the prepared glasses in the attenuation of neutrons as in gamma rays. In addition, the protection ability of the fabricated glasses against alpha and proton charged particles was also evaluated. Charged alpha and proton particles in BPZE5 glass have the shortest projected ranges which are 50.38 μm and 436.36 μm respectively. It was seen that the increase of Er 2 O 3 additive upgraded the prepared glasses in terms of attenuation of all of the selected radiation types. It can be deduced that these results might help for estimating the effect of Er 2 O 3 on different glass systems in the future. [ABSTRACT FROM AUTHOR]

We report the optical and experimental gamma-ray and neutron attenuation properties of tantalum pentoxide reinforced Bi 2 O 3 –TeO 2 –ZnO ternary glasses with a nominal composition of 10Bi 2 O 3 –70TeO 2 -(20-x)ZnO-xTa 2 O 5 (where x = 0,2,4, and 6 mol%). Measurements of transmittance and absorbance spectra for all of the synthesized samples are performed with Analytik Jena Specord 210 plus device between the range of 190–1100 nm. Moreover, 133Ba and 241Am/Be sources are utilized for experimental gamma-ray and neutron attenuation studies of BTZT glasses. According to results, the absorption edge is consistently moved from 380 nm to 390 nm as a result of ZnO/Ta 2 O 5 translocation. In addition to decrease in optical band gap values of glass series, the fact that doping the structure containing Ta 2 O 5 is lead to an increase in Urbach energies. The obtained irregularity through an increasing Ta 2 O 5 additive is also changed the overall nuclear radiation attenuation properties of the BTZT glasses. The gamma-ray attenuation properties are obviously enhanced within the energy range of 133Ba radioisotope. The attenuation properties against fast neutron emitted from 241Am/Be were significantly enhanced through increasing Ta 2 O 5 contribution. It can be concluded that BTZT6 glass sample may be regarded as a beneficial glass composition for multifunctional applications. It can be also concluded that ZnO/Ta2O5 translocation in Bi 2 O 3 –TeO 2 –ZnO ternary glasses may be regarded as a monotonic tool where the neutron attenuation properties should be strengthened in addition to gamma attenuation properties. [ABSTRACT FROM AUTHOR]

We present synthesis and thorough characterization phases of newly developed 20P 2 O 5 ·30TeO 2.(50-x)ZnO.xCdO (x = 0, 2, 4, 6, 8, 10 mol%) glasses. Experimental gamma-ray and neutron transmission systems are used in terms of exploring the monotonic effects of increasing CdO reinforcement on behavioural changes of synthesized glasses through well-known melt-quenching method. A conventional gamma-ray setup along with a high purity germanium detector as well as 133Ba radioisotope is used for determination of attenuation coefficients. Glass shields are irradiated with a241Am/Be neutron source using the Canberra NP-100B BF3 gas proportional detector. The addition of 10% mole CdO to the basic glass composition had a significant favorable impact on the transition resistance to gamma and neutron radiation. In comparison to all available shielding materials, (except RS-520), the C10 sample demonstrated superior gamma-ray attenuation capabilities. According to results, C glasses generally exhibit superior neutron attenuation capabilities than conventional moderators. It can be concluded that C glass family may be considered as suitable gamma-shield and neutron moderator in different types of applications from research to medical radiation fields. [ABSTRACT FROM AUTHOR]

This study explores the radiation shielding potential of Na 2 O–SiO 2 glass matrices doped with BaO, ZnO, CdO, and SrO, analysed across a broad energy spectrum. The research employed various computational tools such as Phy-X/PSD and PAGEX codes to calculate various shielding parameters, including Kinetic Energy Released in Material (KERMA), mass stopping power, fast neutron, and gamma-ray attenuation properties. Among the glass samples, S3, with its BaO content, exhibited the most advantageous properties in terms of radiation attenuation. The results showed that S3 has the lowest Half Value Layer (HVL) of 0.032 cm at 0.015 MeV and the highest KERMA value, peaking at 0.3 MeV with 0.18 MeV/g. The mass stopping power values for alpha particles in the S3 sample showed a pronounced peak at 0.7 MeV, reaching 150 MeV cm2/g, indicating superior energy absorption. The S3 sample, composed of 20% Na 2 O, 20% BaO, and 60% SiO 2 , demonstrated the highest density (i.e., 3.225 g/cm³) and effective atomic number (i.e., 17.5), which contributed to its superior shielding performance. The study's findings show that the careful manipulation of glass composition, particularly through the incorporation of high-atomic-number oxides, can significantly enhance shielding effectiveness. It can be concluded that the S3 glass sample would be an optimal configuration for practical applications in radiation protection, where the Na 2 O–SiO 2 glass matrices doped with BaO in terms of optimal material properties. • BaO-doped Na 2 O–SiO 2 glasses superior in gamma radiation shielding than ZnO, CdO, SrO. • S3 sample with 20% BaO exhibits best shielding, demonstrating high KERMA, mass stopping power. • Incorporating high-atomic-number oxides enhances glass shielding effectiveness significantly. • S3 glass composition is optimal shielding purposes. [ABSTRACT FROM AUTHOR]

In this study, four new phosphate-based glasses with the compositions of CaO–Na 2 O–K 2 O–P 2 O 5 (PN system), CaO–Na 2 O–K 2 O–Al 2 O 3 –P 2 O 5 (PA system) and CaO–Na 2 O–K 2 O–Al 2 O 3 –SiO 2 –P 2 O 5 (PS system) were synthesized and characterized through experimental gamma-ray and neutron spectroscopy methods. Glass densities were then measured experimentally and evaluated theoretically. Next, a high purity Germanium (HPGe) detector was used for determining the fundamental gamma-ray transmission parameters in 35.4–383 keV gamma-ray energies emitted from 133Ba source (Radioactivity: 3Ci). Additionally, the experimental setup was used to determine the equivalent dose (EAD) to get a better knowledge of fast neutron attenuation. Our findings indicate that experimental gamma-ray transmission measurements are consistent with standard theoretical data (EpiXS). Consequently, PA10 was shown to have higher gamma-ray and neutron attenuation capabilities when compared to the other glass samples studied. Our outcomes showed that increasing the molar contribution of Al 2 O 3 to the phosphate-based glasses increased not only their transparency but also their gamma-ray and neutron attenuation capacities. It can be concluded that substituting Al 2 O 3 for P 2 O 5 is a functional and monotonic tool for improving the optical, gamma-ray, and neutron attenuation of phosphate-based glasses, which are being evaluated as prospective shielding materials for medical and industrial radiation facilities. [ABSTRACT FROM AUTHOR]

This study aimed to fabricate six different Copper(II) oxide reinforced Calcium-Borate glasses with different types of substitutions such as Al 2 O 3 /V2O 5 , BaO 2 /V 2 O 5 , and ZnO/V 2 O 5. Accordingly, a depth characterization process has been performed for ACV, BCV and ZCV glasses with a nominal composition of 55B 2 O 3 –35CaO–9Al 2 O 3 -0.5CuO-0.5V 2 O 5 , 55B 2 O 3 –35CaO-8.5Al 2 O 3 -0.5CuO–1V 2 O 5 , 55B 2 O 3 –35CaO–9BaO 2 -0.5CuO-0.5V 2 O 5 , 55B 2 O 3 –35CaO-8.5BaO 2 -0.5CuO–1V2O5, 55B2O3–35CaO–9ZnO-0.5CuO-0.5V2O5, 55B2O3–35CaO-8.5ZnO-0.5CuO–1V 2 O 5. Optical, structural, physical, and experimental neutron/gamma shielding properties of synthesized glasses were determined, respectively. Experiments measuring neutron exposure indicated how well glass samples attenuated fast neutrons. The RADACS software was used to record data from a BF3 gas proportional detector from the Canberra NP-100B series and a 241Am/Be neutron source with a 10 mCi activity. The absorption edge belonging to the samples are found between 420 nm and 480 nm. Our findings showed that the optical band gaps for the samples ranged from 1.179 to 2.022 eV. The wavenumber range of 400–1600 cm-1 was evaluated for the resulting peaks. The region with the highest band formation was approximately 760–1170 cm-1. While BCV0.5 and BCV1 glasses with 9% and 8.5% BaO 2 insertion have the largest MAC values ranging between 2.255–0.076 and 2.156–0.076 cm2/g, the lowest MAC values varying between 0.361–0.0761 and 0.366–0.076 cm2/g belong to ACV0.5 and ACV1 glasses with 9% and 8.5% Al 2 O 3 addition. Our results showed that the BCV glass family has superior material properties among the fabricated glasses. It can be concluded that BaO 2 /V 2 O 5 glasses may be used in replacement of Copper(II) oxide glasses to provide monotonic behavior on crucial characteristics while maintaining the greatest density increase for large gamma ray shielding properties. [ABSTRACT FROM AUTHOR]

This research article aims to study the effect of CdO addition on the radiation shielding characteristics of boro-tellurite glasses in the composition of 50B 2 O 3 - (50-x) TeO2- xCdO, where x = 0, 10, 20, 30, 40 and 50 mol%. These glasses were exposed to gamma radiation and the transmitted gamma photons were evaluated for energies varying from 15 keV to 15 MeV using Geant4 simulation toolkit. The number of transmitted photons was then used to characterize the gamma shielding for the studied glasses in terms of linear/mass attenuation coefficients, MFP, Z eff , and HVL. The simulation outcomes were theoretically confirmed by using Phy-X software. The beta (electron) shielding characterization of the involved glasses was also investigated by determining the projectile range and stopping power using ESTAR software. Additionally, the fast neutron shielding characterization of the glasses was achieved by evaluating removal cross-section (Σ R). The results reveal that the CdO has a small influence on the shielding performance of the boro-tellurite glasses against gamma, beta, and neutron radiations. The shielding performance of the boro-tellurite glasses was compared with that of common shielding materials in terms of MFP. It can be concluded that the boro-tellurite glasses regardless of the concentration of CdO content have promising shielding performance to be used for radiation applications. [ABSTRACT FROM AUTHOR]

In this study, the uncharged/charged and photon shielding features of TeO 2.Ta 2 O 5.ZnO/ZnF 2 tellurite-rich glass system with different ZnO/ZnF 2 ratio (encoded as TTZ, TTZF4, TTZF8, TTZF12 and TTZF16) were comprehensively discussed. The mass attenuation coefficients (MAC) were achieved employing MCNPX simulation codes and the outcomes were verified with theoretical data computed by WinXCOM software. The MACs varied between 47.667 to 0.034 for TTZ glass (for ZnO=16 mol%) and the largest MAC values were gained for TTZ glass among the others. Several MAC-based photon attenuation parameters, Half Value Layer (HVL), equivalent atomic number (Z eq) and Exposure Buildup Factor (EBF), of TTZF glasses were also determined for the energy range of 0.015–15 MeV. The results indicated that the enhancement in ZnO grows the gamma-ray attenuation competences of TTZF glasses. Furthermore, removal cross section of fast neutrons (∑ R) for TTZF glasses was found and it has been noted that higher glass density has enhanced the ∑ R values. The Σ R values of TTZF glasses change between 0.1103-0.1174 cm-1. At last, projected range (PR) and mass stopping power (MSP) for charged particles has been investigated within the kinetic energy range between 0.01–10 MeV. It is found that all TTZF glasses possess nearly close MSP and PR values for proton and alpha particles. We trust that the results of this study will guide the radiation protection capabilities of tellurite-rich glass systems. [ABSTRACT FROM AUTHOR]

In this study, five different glasses encoded Pb25, Pb30, Pb35, Pb40 and Pb45 based on xPbO- (50-x) MoO 3 –50V 2 O 5 (25 ≤ x ≤ 45 mol %) glass system were fabricated. MCNPX code, XCOM and XMuDat have been utilized to compute the mass attenuation coefficient (μ m) values of the xPbO-(50-x)MoO3–50V 2 O 5 glass system at 0.015–15 MeV photon energies. X-ray diffraction (XRD), was characterized for fabricated glasses. Moreover, different shielding parameters such as Half Value Layer, Tenth Value Layer, relaxation length, effective atomic numbers and effective electron densities, basic gamma-ray attenuation properties such as Exposure Buildup Factors (EBF) and Energy Absorption Buildup Factors (EABF) at different penetration depths, Effective Removal Cross Section against fast neutrons have been calculated. In addition to nuclear radiation shielding parameters, numerous physical and mechanical parameters were determined. The experimental elastic modulus results were compared using the theoretical models Makishima-Mackenzie and Rocherulle model. The values of these moduli have been compared to their experimental values. The results observed that the composition has the highest value of PbO (45 mol. %) showed excellent nuclear radiation shielding and elastic properties. [ABSTRACT FROM AUTHOR]

In this study, mechanical and nuclear radiation shielding behaviors of highly efficient alkaline phosphate glasses with various GeO 2 concentrations were evaluated for their nuclear radiation shielding applications. Moreover, the glass rigidity parameters of alkaline phosphate glasses were calculated for determination mechanical properties. The μ m values were calculated using XCOM program and MCNPX simulation code. The nuclear radiation shielding properties (gamma and neutron) such as μ m , HVL, TVL, MFP, Z eff , EBF, EABF, and Σ R were calculated for all alkaline phosphate glasses with various GeO 2 concentrations. The results showed that μ m , Z eff , and Σ R increased as the Bi 2 O 3 concentration increased. The G14 glass sample had the minimum HVL, TVL, MFP, EBF and EABF. The G14 sample had the largest μ m , Z eff , and the number of network bonds, and can be considered as an excellent attenuator for gamma and neutron shielding. The outcomes of recent investigation can be useful to understand the nature of GeO 2 additive into alkaline phosphate glasses, which can be considered as a candidate shield type in medical and industrial radiation facilities. [ABSTRACT FROM AUTHOR]

The present work reports the physical, structural, elastic, optical, and radiation shielding studies on (80˗X)H 3 BO 3 +10TeO 2 +9.5Nb 2 O 5 +XBaO+0.5Sm 2 O 3 (where X = 10, 20, 30, 40, 50 in wt%) glasses which is prepared by the melt quenching technique. The bending and stretching vibrations of the different compounds used are analyzed through FTIR instrumentation. The density and refractive indices are measured experimentally following Archimedes's principles and by using Abbe's refractometer, respectively. Various structural parameters are calculated to resolve the actual placement of atoms in the glass complex, which explains the compactness of the network. Elastic properties of the synthesized glasses are calculated to estimate the resistance of glass under stress. Additionally, the optical band gap is calculated, and the nature of bonds in the network is ionic compared to the covalent nature. Boron–Boron distance is the lowest for 50BNTBSm sample. The decrease in OPD content is linked with the decrease in the number of oxygen atoms, for 10BNTBSm and 50BNTBSm glasses, it is 289 and 209 oxygen atoms, respectively. Λ th value is high for 10BNTBSm glass sample with the minimum BaO reinforcement. The Urbach's energy varies from 0.534 to 0.967 eV, corresponding to xBNTBSm samples indicating fewer defects in the glasses. Moreover, gamma-ray and fast neutron attenuation properties of xBNTBSm are determined and compared with numerous shielding materials such as concrete and other types of glasses. Results showed that replacing 40% of H 3 BO 3 with BaO leads to a net improvement in gamma-ray attenuation properties. However, this situation was the opposite in the fast neutron absorption properties. A clear superiority of sample 50BNTBSm was also reported against the compared absorbent materials. It can be concluded that replacing 40% of H 3 BO 3 with BaO would provide some significant improvements to Niobium Bariumtelluroborate glasses. • Niobium Boro-tellurite (xBNTBSm) glasses were fabricated via melt-quenching technique. • 50BNTBSm glass is verified as the most compact one by the structural properties. • As the amount of BaO increases, the Z eff increases with it at all energies. • 50BNTBSm sample had the lowest EBF and EABF. • 50BNTBSm glass is the more effective shield due to highest MAC and lowest MFP values. [ABSTRACT FROM AUTHOR]

We present the preparation phase and comprehensive analysis of nuclear radiation shielding characteristics of novel melt-quenched 20P 2 O 5 ·30TeO 2.(50-x)ZnO.xCdO (x = 0, 15, 20, 30, and 40 mol percent) quaternary-tellurite glasses. The primary objective is to compare the changes in nuclear radiation absorption qualities that come from maintaining high transparency and increasing the CdO contribution rate to maximum values, such as 40 mol%. Consequently, experimental gamma-ray and neutron transmission systems are used to investigate the monotonic impacts of increasing CdO reinforcement on the functioning of synthesized glasses utilizing the well-known melt-quenching method. For the determination of attenuation coefficients, a standard gamma-ray setup is used with an Ultra germanium detector and 133Ba radioisotope. In addition, using the Canberra NP-100B BF3 gas proportional detector, glass shields are bombarded with a 241Am/Be neutron source (10 mCi/4.5 MeV) using a gas proportional detector. The addition of 40% mole CdO to the basic composition of glass significantly improved the transition resistance to gamma and neutron radiation. Furthermore, it was shown that the degree of transparency in the C40 sample synthesized with a 40% CdO additive ratio was equivalent to that of an ideal transparent glass sample. Moreover, C40 sample had better gamma-ray attenuation properties than all other shielding materials (except for RS-520). According to the findings, C glasses have a greater capacity for neutron attenuation than investigated conventional moderators. It can be concluded that C glass family is an effective gamma-shield and neutron moderator for research and medical radiation applications. • The maximum CdO contribution had no negative impact on the glassy structure. • The degree of transparency was seen in the acceptable levels. • The highest CdO contribution increased the glass density significantly. • The most effective operating conditions were achieved with the maximum CdO contribution. • Fast neutron absorption of C group glasses better than those of conventional neutron moderators. [ABSTRACT FROM AUTHOR]

We report the synergistic effects of boron nitride and graphene nanosheets on physical, structural, and nuclear radiation attenuation properties of polyester matrix-incorporated nanocomposites. Some critical material properties are thoroughly evaluated for several types of synthesized samples. Polyester is employed to strengthen graphene and boron nitride nanolayers, and their characteristics are investigated in detail. Additionally, we report the gamma-ray and fast neutron attenuation characteristics of synthesized nanocomposites to get a better understanding of the reinforcing effect as a function of material type and weight percentage. Thermal analysis findings indicate that adding graphene lowers the decomposition temperature but co-adding graphene and BNNS enhances thermal decomposition in comparison to graphene itself. Tensile tests showed that the inclusion of both GRP and GRP/BNNS strengthens the material. Among the polyester composite samples analyzed, the G3 sample with the most GNP reinforcement had the lowest HVL values throughout the broadest range of energy levels investigated. The recent findings may be beneficial to the scientific community in terms of incorporating these reinforcing types and ratios into polyester materials for a variety of applications, including industrial and research purposes. [Display omitted] • Synergistic effects of boron nitride and graphene nanosheets are investigated. • Polyester is employed to strengthen graphene and boron nitride nanolayers. • Adding graphene lowers the decomposition temperature. • Inclusion of both GRP and GRP/BNNS strengthens the material. • Maximum GNP reinforcement provided lowest HVL values against gamma-rays. [ABSTRACT FROM AUTHOR]

This study aimed to fabricate a new glass system based on x Bi 2 O 3 – (100-x)CRT (x; 0, 1, 3, and 5 wt%)) and to carry out a broad range characterization studies. For this aim, the glasses produced by melt quenching method were coded as Bi0, Bi1, Bi3 and Bi5, and their physical properties were figured out. The amorphous nature of the glasses was confirmed by XRD measurements. FTIR spectroscopy was used to detect possible vibration modes of glasses produced. UV- absorption spectra of Bi0-Bi5 glasses were saved between 300 and 1100 nm. The direct band gap (E g) values reduce from 3.50 to 3.46 eV with the enhancing Bi 2 O 3 insertion while the indirect E g s declined from 3.40 to 3.29 eV. The gamma-transmission measurements were performed for 30.9–383 keV photon energies using radioactive source of 133Ba. Mass attenuation coefficients (MAC) of the Bi0-Bi5 samples were calculated experimentally and matched with EpiXS program and MCNPX simulation outcomes. Using MAC data, other concerned gamma parameters were obtained. We found from results observed that the addition of Bi 2 O 3 obviously enhanced the photon protection ability of the waste CRT glasses. Additionally, it was found that adding Bi 2 O 3 had no discernible effect on attenuation effectiveness against fast neutrons. The findings indicate that Bi5 glass could be a feasible alternative for optical and nuclear shielding applications. [ABSTRACT FROM AUTHOR]

The effect of PbO and TeO 2 concentration on the photon, fast neutron and charged particles shielding capacity of the ternary ZnO-PbO-TeO 2 glass systems with the form [(TeO 2) 0.7 -(PbO) 0.3 ] 1−x (ZnO) x : x = 0.15–0.25 mol% (TPZ1-TPZ5) glass system was investigated. For this purpose, the mass attenuation coefficient (MAC=μ ρ) values of the glasses were produced with MCNPX codes and WinXCOM program in the wide energy range of 0.015–15 MeV. Due to the high PbO and TeO 2 contributions, the largest MAC values were obtained for the TPZ5 glass. Then important gamma parameters such as effective atomic number, half value layer, effective electron density, equivalent atomic number, and exposure and energy absorption buildup factors (Z eff , HVL, N el , Z eq and EBF and EABF) were also calculated for TPZ glasses. While the highest Z eff values were found for TPZ5 glass, changing between 48.43 and 51.01, the lowest HVL, EABF and EBF values were calculated for TPZ5 glass. As can be seen from the removal cross section, mass stopping power, and projected range (Σ R , MSP, and PR) results for TPZ glasses, the TPZ5 glass can also be a good shielding material for fast neutrons and alpha-proton particles. As a result, the hypothesis of the study has been confirmed and we believe that the obtained data from this study will be beneficial for the potential use of Te-based glasses in shielding applications. [ABSTRACT FROM AUTHOR]

In this research article, the radiation shielding properties of newly developed high Fe content amorphous alloys were reported. The chemical compositions of these alloys were Fe 83 B 9 C 3 Si 4 P 1 , Fe 84 B 10 C 2 Si 2 P, Fe 85 B 8 C 3 Si 3 P 1 , and Fe 86 B 5 C 8 P 1. Monte Carlo simulation method was successfully used to study the problem of radiation propagation through theses alloys under suitable boundary conditions of vacuum. Our results indicate that MAC value decays as photon energy grows varying from 0.0997 to 0.0387, 0.0997–0.0387, 0.0998–0.0387, and 0.0998–0.0387 cm2/g for FBCSP1, FBCSP2, FBCSP3, and FBCSP4 respectively. However, gradual increase was observed in both parameters of mean free path (MFP) and half value layer (HVL) as energy increases. The maximum and minimum value of the effective atomic number (Z eff) was 23.09 and 22.97, 23.29 and 23.17, 23.41 and 23.30, and 23.4 and 23.29 for FBCSP1– FBCSP4 respectively. FNRC (Fast Neutron Removal Cross-section) values were: 0.1538, 0.1538, 0.1536, and 0.1561cm-1 for FBCSP1– FBCSP4 respectively. Moreover, an extensive comparison was reported between the radiation shielding proficiency of the studied alloys and that of the traditional materials. It can be concluded that, FBCSP alloys can conveniently replace the traditional materials in photon shielding application especially when space is a constraint. • High Fe content amorphous alloys were reported for radiation shielding applications. • Simulations were successfully applied in the design of vacuum system for radiation propagation. • The optimum thickness for narrow beam transmission geometry is less than 1 MFP. • FBCSP alloys can conveniently replace the traditional materials. [ABSTRACT FROM AUTHOR]

This study aimed to investigate the shielding performance of SrO–LiF–B 2 O 3 glasses glass system for nuclear security applications. The MCNPX code (version 2.6.0) and GEANT4 are used to determine the shielding parameters and the dependence with the composition of each glass, as well as the influence of Cr 2 O 3 additive. A wide-range of nuclear radiation shielding investigation for gamma-ray, proton particles, fast neutrons have been studied for five different types of glasses. The calculated values for mass attenuation coefficients (μ m) were utilized to determine other vital shielding properties against gamma-ray radiation. Furthermore, some of the investigated parameters have been determined by using SRIM code and special calculation methods such as G-P fitting parameters for EBF and EABF calculation. The results showed that C25 glass with the highest Cr 2 O 3 additive had a satisfactory capacity in nuclear radiation shielding. Image 10182 • The effect of C 2 O 5 additive in LiF–SrO–B2O3 glass structures were examined. • MCNPX and GEANT4 codes were utilized for MAC calculation. • A broad range of nuclear radiation shielding parameters were determined. • C25 glass sample with highest Cr 2 O 3 additive had a satisfactory performance against nuclear radiation. [ABSTRACT FROM AUTHOR]