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A glass system with the nominal composition 10NaF - (89-x)B 2 O 3 - xBi 2 O 3 - 1Sm 2 O 3 (where x = 15, 20, 25, 30, and 35 mol%) has been fabricated by the melt quenching technique. Densities increased from 3.598 to 4.726 g/cm³ and a corresponding rise in molar volume from 35.880 to 44.089 cm³/mol. The decrement in oxygen packing density (OPD = 75.250–61.239 mol/cm3) and increment in oxygen molar volume (13.289–16.329 cm3/mol) indicate an expansion of the glass structure with the Bi3+ ions. Young's modulus decreases from 58.974 to 41.685 GPa as the concentration of Bi 2 O 3 increases from 15 to 35 mol%. The linear attenuation coefficient (LAC) shows an increasing trend, demonstrating improved attenuation ability with a higher molar concentration of Bi₂O₃. As the Bi₂O₃ concentration increases in the glass matrix, the effective atomic number (Z eff) increases from 61.214 to 72.116 at 59.54 keV, and from 15.829 to 25.988 at 662 keV. The half-value layer (HVL) decreases as bismuth oxide is introduced into the glass matrix, and prepared glasses exhibit lower values than Hematite-Serpentine Concrete, Ilmenite-Limonite Concrete, Basalt-Magnetite Concrete, Ilmenite Concrete, RS253, 55B 2 O 3 :20BaCO 3 :19.5ZnO:5Bi 2 O 3 :0.5Dy 2 O 3 , RS 323, LSGB1, and LSGB2 shielding materials. The mean free path (MFP) values reduced from 0.094 to 0.053 cm at 59.54 keV, and from 2.958 to 2.073 cm at 662 keV with the Bi 2 O 3 concentration. Consequently, the prepared glass can be reliable for gamma radiation shielding applications. [ABSTRACT FROM AUTHOR]

Concrete is the favored construction material, with more than 7 billion cubic meters manufactured annually. Aggregates constitute the crucial component of its structure and quality, responsible for its exceptional characteristic features. The characteristics of aggregates determine the mechanical durability and radiation performance of concrete. In this investigation, fabricated concrete specimens were generated by replacing sand and aggregate sizes with pyrophyllite in 10%–20%–30%–100% proportions. The study investigated the mechanical properties of concrete specimens using both pressure and ultrasound methods, as well as their durability under freeze–thaw and high-temperature (200°C–1,000°C) conditions. In addition, the microstructure and radiation permeability properties were examined over a 7–28–90-day period. Notably, the use of pyrophyllite sand and aggregate significantly increased the compressive strength of the specimens by 21%–63% when compared to the reference concrete after 7–28–90 days, while also reducing mass loss by up to 4.6% during freeze–thaw cycles. After subjecting the specimens to high temperatures, it was discovered that those with an air-cooling regime achieved a compressive value 45% higher than the reference concrete. Microstructure images revealed the formation of C─ S─ H, CH, and portlandite hydration products over 90 days, supporting the observed compressive strength values. The study also has an effective linear attenuation coefficient (LAC) for radiation-shielding properties. According to some radiation-shielding parameters calculated through LAC values, it was revealed that these concrete samples were suitable shielding materials. Pyrophyllite-reinforced specimens have demonstrated potential for high-strength concrete production, suitability for use in high-temperature environments, and effectiveness as shielding in areas with radiation sources. [ABSTRACT FROM AUTHOR]

The current work seeks to develop a novel CuO-doped lead calcium barium borate glass using the melt quenching method at 1100 °C. There was a 3.91–4.49 g/cm3 change in the fabricated glasses' density, with a respective 0–15 mol.% increase in the CuO concentration. Additionally, substituting CuO for B2O3 reduced the fabricated glasses mechanical properties due to the decreased dissociation energy between 63.99 and 60.50 kcal/cm3, and the packing factor decreased between 15.22 and 13.23 cm3/mol. Through increasing the fabricated glasses' CuO concentration, there was a decrease in the bulk, longitudinal, shear, and mechanical Young moduli. Moreover, Monte Carlo simulation (energy interval: 0.033–2.506 MeV) was employed to evaluate the fabricated glasses' ability to shield gamma rays. A 0–15 mol.% increase in the CuO concentration raised the linear attenuation coefficient (LAC) between 14.081 and 16.797 cm−1 (0.059 MeV), 0.325–0.371 cm−1 (0.662 MeV), and 0.154–0.176 cm−1 (2.506 MeV). The LAC enhancement reduced the required half value thickness of the fabricated glasses by 16.2 %, 12.53 %, and 12.85 % at the of 0.059, 0.662, and 2.506 MeV gamma ray energies. [ABSTRACT FROM AUTHOR]

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The gamma shielding parameters of an admixture of waste borosilicate glass (BS) and geopolymer (GP) made from activated metakaolin are presented in the present study. The influence of the BS quantity on the density and different gamma shielding quantities is investigated over a wide gamma energy range. Four batches of the G-BS composite were prepared using the solid-state diffusion method, containing 0 (G), 10 % (G-10BS), 20 % (G-20BS), and 30 % (G-30BS) by weight of BS, respectively. The chemical compositions of the G-xBS samples were determined through X-ray fluorescence spectrometry. In addition, the density of the BS-doped geopolymers was determined using the liquid displacement method using deionized water as the displacement fluid. The theoretical determination of estimating shielding parameters began by estimating the mass (μ ρ) and linear (μ) attenuation coefficients of the geopolymers for photon energies in the range of 15 keV to 15 MeV using the XCOM data library. The B and Si content and density of the geopolymer samples increased as the BS weight proportion increased in the geopolymer. The values of the attenuation coefficients (ACs) decreased with energy. For μ, the decrease was from 9.1533 to 0.0355 cm−1, 6.7486 to 0.0374 cm−1, 10.2964 to 0.0396 cm−1, and 10.7722 to 0.0414 cm−1, while for μ ρ , it was 5.3217 to 0.0206 cm2 g-1, 5.3860 to 0.0206 cm2 g-1, 5.3627 to 0.0206 cm2 g-1, and 5.3594 to 0.0206 cm2 g-1, for G, G-10BS, G-20BS, and G-30BS, respectively. There are no significant differences between the photon energy absorption capacity of the geopolymers, especially at energies greater than 1 MeV. The photon buildup factors of the G-xBS samples have very close relative values with no clear order. The introduction of waste borosilicate glass is therefore a way of improving the photon attenuation capacity of geopolymer and, therefore, the potential of shielding applications of geopolymer-based concrete. [ABSTRACT FROM AUTHOR]

The radiation shielding properties of different samples of borate-tellurite glass were investigated using WO3 modifiers. Geometric optimization and modification of pristine borate-tellurite with WO3 were carried out based on density functional theory calculations using plane wave basis sets and pseudo-potentials. It was observed that the changes in the physical properties of the white box testing glass (WBTG) systems were determined by WO3 content. Analysis of the linear attenuation coefficient of the sampled glasses, which yielded a value of 7.43 cm for WBTG1 at 20 keV, indicated that WBTG1 was able to stop gamma radiation from Cs-137 and Th-237 sources. Both the µ and µm values were zero above 0.15 MeV, indicating that the WBTG composite was only able to attenuate low-energy photons such as gamma rays. It was found that the characteristic behavior of the WBTG was generally determined primarily by oxygen content, which is in good agreement with theoretical and experimental data. [ABSTRACT FROM AUTHOR]

This study focuses on the development and evaluation of a novel cement-free gamma-ray-resistant ultrahigh-performance concrete (UHPC), known as UHPC-CAS. UHPC-CAS is composed of calcium oxide–activated slag, iron and barite powders, and steel fibers, making it a type of ultrahigh-performance geopolymer concrete (UHPGC). In this study, the effects of replacing silica sand with varying percentages of iron and barite powders on the mechanical and radiation properties of UHPC-CAS were investigated. The optimal replacement ratio of iron powder was found to be 50%, resulting in the highest compressive, tensile, and bending strengths among all mixtures without fibers. Furthermore, the UHPC-CAS samples reinforced with steel fibers and containing barite powder exhibited a more pronounced softening zone than those containing iron powder. With 100% iron powder and 3% steel fibers, UHPC-CAS achieved superior resistance to gamma rays, as evidenced by the highest attenuation coefficient of 0.234 cm and the lowest half-value layer of 2.96 cm. This research demonstrates the potential for developing sustainable cement-free UHPC for use in nuclear facilities and other applications requiring high radiation shielding. [ABSTRACT FROM AUTHOR]

The project's goal is to create new, low-cost materials with low density that can withstand the transport of γ-photons with low and intermediate energy. As a result, a set of four epoxy resins reinforced with different amounts of heavy metallic debris were created. By enlarging the waste component of the manufactured composites by 0–40 wt%, the density of the composites increased from 1.134 ± 0.022 to 1.560 ± 0.0312 g/cm3. The experimental assessment of the linear attenuation coefficient shows an increase with factors of 6.6, 2, and 1.5 times, respectively, for—photon energies of 33, 121, and 662 keV. The augmentation composites density has an impact on these parameters. The half-value thickness and the transmission factor for the fabricated composites decreased with enriching the heavy metallic waste composition, where the half-value thickness decreased from 5.95 to 3.08 cm as well as the transmission factor decreased from 89.01 to 79.86% with enriching the heavy metallic waste concentration from 0 to 40 wt%. The study shows the invalidity to use the fabricated samples to attenuate the γ-photons with energies higher than 662 keV, where the linear attenuation coefficient enhanced by a factor of 19% from 0.078 to 0.094 cm−1. [ABSTRACT FROM AUTHOR]

Double perovskites are emergent materials because of their exciting characteristics, such as their stable crystal structure. Thermoelectric, optical, structural, elastic, electrical, magnetic, and perovskite Rb2FeCdO6 properties are explored within the framework of spin-polarized density functional theory, all computations were carried out using the full-potential linear augmented plane-wave approach. The potential was applied using GGA with an extra onsite Coulomb parameter (GGA + U), including the Hubbard parameter. The phase stability calculation shows that Rb2FeCdO6 should remain stable in a ferromagnetic state and a cubic geometry (space group Fm-3 m). This Rb2FeCdO6 compound is mechanically and chemically stable, as confirmed by the computed formation energy, tolerance factor, and elastic constants. Poisson and Pugh's ratios were used to study ductile and brittle behaviour. Using the GGA + U methods, the results reveal that double perovskite has a semiconductor nature with a magnetic moment of 5.5 µB, as determined by the magneto-electronic characteristics. The band structure calculations show the direct band gap of 2.2 eV (Up) and 1.8 eV (Dn) for Rb2FeCdO6 Double perovskites. The optical properties were also studied in detail, including complex dielectric constants, refractive indices, reflectivity, extinction coefficients, absorption coefficients, and optical conductivity functions up to 13.0 eV. Using the phy-x: PDS program, The mass attenuation coefficient (GMAC), linear attenuation coefficient (GLAC), half value (GHVL), mean free path (GMFP), effective, calculated atomic number (Zeff) were determined gamma radiation shielding properties of Rb2FeCdO6), and the effective electron density (Neff). The study shows that GMAC and GLAC values for Rb2FeCdO6 decrease with increasing photon energy, with a remarkable increase near K-edge absorption due to photoelectric effect dominance at low energy GHVL and GMFP increase with photon energy increases, indicating a decrease in photon interaction. We computed thermoelectric responses to evaluate potential and go into depth about the outcomes of the investigation. The Seebeck coefficient's positive and negative values classify double perovskites as exhibiting n and p-type semiconductors. These materials have high power factor values of 6.0 × 1011 Wm−1 K−2 s−1 and a figure of merit of 0.9, indicating good power conversion efficiency at high temperatures. Our results highlight the compound's potential for optoelectronic and thermoelectric devices. [ABSTRACT FROM AUTHOR]

This work presents an in-depth analysis of the linear attenuation coefficient (LAC), effective atomic number (Zeff) and half value layer (HVL) for borosilicate glasses doped with ZnO. Utilizing Akima splines and piecewise cubic Hermite interpolating polynomials (PCHIP), we predicted the LAC, Zeff and HVL for the investigated glasses in a wide energy range of 0.015–15 MeV. The results showed that the LAC values for the four prepared glasses predicted by Akima splines and PCHIP closely match the theoretical data at all the selected energy levels. This suggested that both Akima splines and PCHIP are a reliable technique for evaluating the LAC of the prepared borosilicate glasses in the energy range of 0.015–15 MeV. The same agreement between the theoretical and predicted data was also reported for the Zeff and HVL. Also, we examined the accuracy in the Akima splines and PCHIP methods in predicting the radiation shielding properties for the selected glasses at certain energy values emitted by Eu-152. The results demonstrated excellent agreement between Akima splines and PCHIP with the theoretical data, which confirms the usefulness of these two interpolation methods in predicting the radiation shielding parameters in the energy range of 0.0395–1.46 MeV. [ABSTRACT FROM AUTHOR]

The current work aims to synthesize new zirconium tungstate (Zr4W8O32)-doped ZrO2 composites for radiation shielding applications using the hydrothermal reaction process. The characterization of the synthesized composites was proved using various analysis techniques including X-ray diffraction, scanning electron microscope, transmission electron microscopy (TEM), and energy-dispersive X-ray spectroscopy. The density of the synthesized Zr4W8O32-doped ZrO2 composites reduced between 5.15 and 4.98 g/cm3, with raising the W concentration between 13 and 28 wt%. Additionally, the average crystallite size proved by TEM analysis was determined as 27.7 nm and 33.2 nm, respectively, for composites ZW-1 and ZW-2. Furthermore, the Monte Carlo N-particle transport code (version-5) was applied to estimate the gamma ray shielding properties of the synthesized zirconium tungstate (Zr4W8O32)-doped ZrO2 composites. The linear attenuation coefficient for the synthesized composites showed variation between 104.50 and 0.200 cm−1 (for ZW-1 composite) and 92.35 and 0.196 cm−1 (for ZW-2 composite) when the gamma photon increased between 0.033 and 2.506 MeV. Therefore, the radiation protection efficiency for a 3 cm thickness of the synthesized composites reaches 54.27% and 53.57% for samples ZW-1 and ZW-2, respectively. As a result, the fabricated composites can be used to produce ceramics with high shielding properties to be used in radiation shielding applications. [ABSTRACT FROM AUTHOR]

Hydrothermal treatment procedures were employed, to generate hydroxyapatiteCa10(PO4)6(OH)2,(HAP) powder, from the femur and ribs of bovine bone samples. This investigation delves into the effect of gamma rays, from a Cs-137 activity equal to 220 µCi at integral doses of 20 kGy, on the surface structures, vibration properties, and attenuation coefficient of HAP, in the bovine femur bone and ribs. The mass attenuation coefficients for HAP powder were registered as E= 511 keV, with 1276 keV gamma energy released from the 22Na radioisotope, and 662 keV gamma energy released from the 137Cs radioactive isotope. We used the Nist XCom program to calculate the mass attenuation coefficient of HAP before and after radiation for photon energies ranging from 0 keV to 100 keV. [ABSTRACT FROM AUTHOR]

This paper studied the radiation shielding properties of new lead‐free telluride glass with different BaF2 content. The 65TeO2–15Bi2O3–(20 − x)ZnO–xBaF2 glass systems (where x = 1, 3, 5, 7, 9 mol%) were tested through the X‐ray diffraction, ultraviolet–visible spectrophotometer, and differential scanning calorimetry. The glass system exhibited good thermal stability and a uniform surface without surface crystallization. The linear attenuation coefficient of the TBZBF series glass was tested using five different gamma radiation sources (241Am, 133Ba, 57Co, 137Cs, and 60Co). They were calculated to the mass attenuation coefficient, half‐value layer, mean free path, and effective atomic number through numerical simulations with XCOM software. The maximum mass attenuation coefficient for TBZBF‐9 was calculated to be 5.3577 cm2/g. Comparisons were made between this glass system and other tellurite and leaded glasses reported in the literature. The glass system exhibited superior radiation shielding capability compared to leaded tellurite glass under the same testing conditions. The gamma radiation shielding capacity increased with BaF2 content in the glass system. These results show that TBZBF‐9 exhibited the best gamma radiation shielding effectiveness while maintaining glass transparency. [ABSTRACT FROM AUTHOR]

In this work we investigated new different glass compositions 20PbO–20BaO–(60 − x)B2O3–xZnO (x = 0, 5, 10, 15 and 20 mol%) to study the radiation shielding capability of these glass composites. The shielding ability was measured experimentally using narrow beam method (which including HPGe detector, point sources and lead collimators). The accuracy was verified by XCOM software, the linear attenuation coefficient (LAC) of the produced glasses was ascertained using both methods. We noticed that the B40Z20 glass composite (contain 20 mol%) has the highest LAC at the four examined energies (0.060, 0.662, 1.173 and 1.333 MeV) since the LAC enhances as the ZnO content increases from 0 to 20 mol%. The based shielding parameters such as HVL and RSE or called radiation shielding efficiency were determined experimentally. The HVL reduces as the glasses' density (or, more accurately, the amount of ZnO) increases. At 0.06 MeV, the HVL have the following values: 0.041, 0.039, 0.038, 0.036 and 0.035 cm for the glasses with density of 3.582, 3.739, 3.897, 4.055 and 4.212 g/cm3 respectively. [ABSTRACT FROM AUTHOR]

Polydimethyl silicone rubber-based polymer composites filled with molybdenum and bismuth were fabricated using simple open mold cast technique. The physical and chemical structure and gamma shielding parameters like attenuation coefficient, half-value layer (HVL) thickness and relaxation length have been investigated for the said novel materials using X-ray diffraction (XRD), Fourier transform Infrared spectroscopy (FTIR) and gamma ray spectrometer. XRD study reveals the crystalline nature of the composites. It is evident from FTIR studies that there is no chemical interaction between the polymer matrix and filler particles. The results of attenuation studies reveal that the linear attenuation coefficient increases with addition of Bi and Mo and is found to be 0.653, 1.341 and 1.017, 1.793 and 0.102, 0.152 cm−1 for 1MMB and 2MMB polymer composites at 80, 356 and 662 keV gamma rays, respectively. The HVL thickness of the materials is found to be 1.06, 0.51 and 0.68, 0.38 and 6.73, 4.532 cm for 1MMB (20Mo + 10Bi phr) and 2MMB (40Mo + 20Bi phr) at these energies, respectively. The mass attenuation coefficient of the novel composites 1MMB and 2MMB is found to be higher than the conventional materials like lead and barite for 356 keV gamma rays. In addition, the material is found to be light weight and flexible enabling to be molded in required forms, thus being a substitute for the material lead that is known to be heavy and toxic by nature. [ABSTRACT FROM AUTHOR]

This study investigates the individual and combined effects of micro and nano lead monoxide (PbO) and granodiorite (GD) on concrete's mechanical and radiation shielding properties. Both materials were partially substituted for cement at varying ratios. Additionally, mixtures with optimal radiation shielding performance were prepared to explore the synergy of combining them. The mentioned materials are used for the first time in an extensive study at the nano scale to investigate their impact on concrete's mechanical properties, microstructure, and gamma radiation attenuation. Two gamma ray sources of uranium (U238) and cesium (Cs137) were used measure the radiation attenuation coefficients for all designed concrete mixes. A simple methodology was followed to assess the concrete shields efficiency via utilizing portable handheld gamma‐ray spectrometer that offers two reading modes. Results indicated that increasing the ratio of PbO is directly proportional to the concrete ability to attenuate radiation, where the optimal individual replacement ratios were recorded at 5% for micro and nano particle sizes. At this ratio, the linear attenuation coefficient (μ) values were improved by 39.57% and 24.78% for the nano and micro PbO, respectively. Additionally, the optimal ratio for improving mechanical properties was at 3% and 2% for nano and micro PbO, while the higher ratios showed a decline in mechanical properties especially at 5% micro PbO with 7.02% reduction in the compressive strength value. Regarding GD powder, the optimal replacement ratios for improving concrete radiation shielding were consistent with those enhancing its mechanical properties at 4% and 7% in both nano and micro scales, respectively. The combined mixes further enhanced the overall concrete performance, especially its radiation shielding ability. Compared to the control mix, the compressive strength, tensile strength, and μ were increased by 25.7%, 16.2%, and 44.7% at the optimal mixture of 5% nano PbO + 4% nano GD. [ABSTRACT FROM AUTHOR]

In an attempt to reutilize marble waste, a new approach is presented in the current study to promote its use in the field of shielding against ionizing radiation. In this study, we aimed to develop a novel and sustainable/eco-friendly lead-free radiation shielding material by improving artificial marble (AM) produced from marble waste combined with polyester by reinforcing it with bismuth oxide (Bi2O3) nanoparticles. Six samples of AM samples doped with different concentrations ( 0 % ,   5 % ,   10 % ,   15 % , 20 % , and 25 % ) of Bi2O3 nanoparticles were prepared. The linear attenuation coefficient ( L A C ) values were measured experimentally through the narrow beam method at different energies (0.0595   M e V , 0.6617   M e V , 1.1730   M e V , and 1.330   M e V ) for all samples with various concentrations of Bi2O3. Radiological shielding parameters such as half value layer ( H V L ), tenth-value layer ( T V L ), and radiation shielding efficiency ( R S E ) were estimated and compared for all the different samples. The results prove that increasing the concentration of Bi2O3 leads to the enhancement of the radiation shielding properties of the AM as a shielding material. It was observed that as the energy increases, the efficiency of the samples falls. High energy dependence was found when calculating the H V L and T V L values of the samples, which increased with increases in the energy of the incident photons. A comparison between the sample with the most efficient gamma radiation attenuation capability (AM- 25 % ), concrete, and lead was conducted, and a discussion regarding their radiation shielding properties is presented herein. The results show that the AM- 25 % sample is superior to the ordinary concrete over all the studied energy ranges, as evidenced by its significantly lower H V L s . On the contrary, lead is superior to the AM- 25 % sample over all the studied energy ranges owing to its unbeatable density as a shielding material. Overall, this new type of artificial marble has the potential to be used as a radiation shielding material at low- to medium-gamma energy regions, specifically in medical imaging and radiation therapy. [ABSTRACT FROM AUTHOR]

Due to the high demand for the utilization of ionizing radiations in several vital fields, it is necessary to reduce their risks and protect humans and their surroundings through the use of protective materials with enhanced radiation attenuating capabilities. In this study, we report the synthesis, crystalline structure, optical, and resisting anti-radiation attributes of the pure superconducting ceramic oxide YBa2Cu3Oy (noted YBCO-123), successfully made by the simple solid-state reaction route. YBCO-123 was then subjected to irradiation with different doses of 0 kGy, 2.5 kGy, and 50 kGy. Variations in the lattice constants, cell volume, oxygen content, microstrain, and bandgap energy were noticed after the irradiation effect with different doses. The microstrain was found to decrease while the density was slightly enhanced with increasing gamma-ray doses. Furthermore, the gamma-ray doses showed a slight effect on the radiation shielding features of the YBCO-123 sample. The linear attenuation coefficient (LAC) at 20 keV showed an enhancement from 206 to 207 cm−1 for 0 kGy and 50 kGy samples. The exposure buildup factor (EBF) and energy absorption buildup factor (EABF) are very low at lower energies and rise with rising penetration depth. The specific absorbed fraction of the energy (SAFE) parameter showed the ability of the YBCO-123 sample to absorb photons at low energies. It can be deduced that the YBCO offered good stability against gamma rays with a high capacity to absorb gamma-ray photons, making it a good candidate for use in the radiation shielding field. [ABSTRACT FROM AUTHOR]

A series of barium borotellurite glass networks (BT-Ba) were produced to study their effectiveness in attenuating gamma rays at different energies and fast neutrons. A host borotellurite glass network of the composition 25TeO2-25B2O3-10CaO-10ZnO-30Na2O (BT) was proposed and reinforced with 10, 20, and 30 mol% of BaO (BTBa1, BTBa2, and BTBa3) at the expense of Na2O. The proposed BT-Ba glasses were produced using the melting/annealing method. The structural properties of the studied BT-Ba glass network were examined using X-ray diffraction (XRD), density and density-based parameters, and Fourier transform infrared (FTIR) spectra. These studies revealed the ability of BaO to enhance the amorphous phase of the studied borotellurite glass network and enrich it with non-bridging oxygen units (NBOs) through the conversion of the bridging ones (BOs). The visible light transparency of the produced BT-Ba glass series was examined by recording the optical transmittance spectra in the UV–visible light regions. Using EpiXS software, the gamma ray attenuation ability of the studied BT-Ba glasses was examined at different gamma ray energies of 302.851, 383.849, 661.657, 1173.228, 1332.492, 1408.013, and 1528.1 keV. While the fast neutron removal cross section was estimated according to the standard mixture rule. The dependence of the behavior of the mass and linear attenuation coefficients, half-value layer, effective atomic number, and effective electron density on BaO concentrations was extensively investigated to explore the attenuation ability of the studied glasses. Among the studied glasses, BT, BTBa1, BTBa2, and BTBa3, the fabricated glass BTBa3 had high transparency (more than 82%) and reduced the required half-value layer from 1.552 to 3.688 cm of BT to 1.041–2.965 cm for the studied gamma ray energies. On the other hand, a slight improvement in fast neutron attenuation with increasing BaO concentrations was observed. The BTBa3 glass had the highest fast neutron cross-section of 0.104 cm−1. Hence, the BTBa3 glass is considered effective as a protective glass for gamma rays and fast neutrons, opening horizons for it in nuclear applications. [ABSTRACT FROM AUTHOR]

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

Lead (Pb)-based materials are very effective in radiation shielding due to their high density of Pb. However, they pose health risks to humans because of the toxicity of lead. As a result, the investigation of radiation shielding properties of various lead-free glass materials has drawn a lot of attention from researchers. In this work, the γ radiation competence of the Bi2O3–ZnO–B2O3–SiO2 glass network was investigated, for the first time in the 0.015–15 MeV energy range, using Phy-X/PSD and XCOM software systems. The results showed that 45Bi2O3–5ZnO–20B2O3–30SiO2 glass sample has the highest linear attenuation coefficient, mass attenuation coefficient, and effective atomic number, and it has the lowest half-value layer, tenth-value layer, and mean-free path. Therefore, 45Bi2O3–5ZnO–20B2O3–30SiO sample is more effective on γ ray shielding than 10Bi2O3–40ZnO–20B2O3–30SiO, 20Bi2O3–30ZnO–20B2O3–30SiO, 30Bi2O3–20ZnO–20B2O3–30SiO, and 40Bi2O3–10ZnO–20B2O3–30SiO samples. The comparison of the results with the literature also revealed that the 45Bi2O3–5ZnO–20B2O3–30SiO glass sample is even more effective than some of Bi2O3-based glass systems, which were recently developed in the literature, by at least a factor of 2. [ABSTRACT FROM AUTHOR]

Due to the country's rapidly expanding economy, Jordanian citizens are replacing their old homes with contemporary multistory structures. Because of the many benefits that come with glasses, these materials are employed for both structural and ornamental purposes. In this study, we investigate the ionising radiation protection and attenuation capabilities of commercial glasses. The shielding capabilities of three glass samples (JOR-1, JOR-2, and JOR-3) with varying elemental weight fractions were examined using a well-shielded NaI detector. We reported the fundamental attenuation coefficients for the glasses under investigation at photon energies of 0.662, 1.173, and 1.333 MeV. The chemical composition of these glasses was examined using Energy Dispersive X-ray (EDX) analysis. JOR-1 is mainly composed of O (40.88%) and Si (25.97%), with minor contributions from Na (7.59%), Mg (1.57%) and Ca (4.74%). JOR-2 contains Sn (2.37%) in addition to O (42.58%), Si (36.35%), Na (7.74%), and Mg (1.92%). JOR-3 has similar composition with JOR-2 and contains O (43.86%) and Si (36.90%), and notable amounts of Na (8.88%), Mg (1.81%), Ca (8.31%), and S (0.25%). We studied the effective atomic number (Zeff) for the commercial glasses and we found that the elevated amount of elements with higher atomic numbers, like Ca, Si and S, led to superior Zeff values for JOR-2 glass. The absence of Carbon in JOR-2 further improved its Zeff, with Tin's presence in JOR-2 slightly edging its Zeff over JOR-3. We compared the HVL for the current commercial glasses with other commercial glasses at 0.662 MeV. We found that JOR-1, JOR-2 and JOR-3 glasses provide better radiation attenuation than rider, PHP and Osmania glasses, while they have higher HVL than RS-360 and very close HVL with RS-253-G18. [ABSTRACT FROM AUTHOR]

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

This work examines a number of synthetic glasses with the molecular compositions 60B2O3, 5CaO, 5Bi2O3, and xEr2O3 (BBCEr-x, where x = 0.0–2.0 mol%) to determine their structural, optical, mechanical, physical, and γ-rays protective properties. Glass was shown to be in an amorphous state by XRD measurements. The density (ρ) of BBCEr-x grew from 3.14 to 3.32 g/cm3 when the molar addition of Er3+ ions increased from 0.0 to 2.0 mol%. The absorbance spectra of the BBCEr-x samples showed seven absorption bands related to the Er3 + electronic transitions (4f–4f). It has been evaluated the dependency of elastic moduli, including Poisson's ratio (σ), and the efficacy of shielding against incoming gamma rays on [Er2O3] mol%. The Makishima-Mackenzie theory was used to calculate the mechanical parameters. As a function of [Er2O3] mol%, the micro-hardness (H) of the Vickers increases while the ratio of the Passion decreases. The mass attenuation coefficient (MAC) has been calculated in the energy range of 0.015–15 MeV using the XCOM and Phys-X/PSD programs and has been compared with Monte Carlo simulations performed using the Geant4 code. The linear attenuation coefficient (LAC), transmission factor (TF), and fast neutron removal cross-sections (ΣR) all showed monotonic dependence on [Er2O3] mol%. With photon energies of 0.015–15 MeV, the sample BBCEr-0.0 had the lowest values of MAC, measuring 34.418–0.029 cm2/g. This result reflects the interaction between density and [Er2O3] impacts on the mechanical and radiation shielding capabilities of the synthesized glasses. The greatest MAC values were found in the BBCEr-2.0 sample, which ranged from 39.6 to 0.037 cm2/g. It was found that ΣR approximates the molar volume (Vm) and exhibits the same trending behavior. This study demonstrated that radiation shielding and mechanical properties could both be customized for indoor or outdoor scientific or industrial usage. [ABSTRACT FROM AUTHOR]

The objective of this study is to explore how the replacement of barium oxide (BaO) by bismuth oxide (Bi2O3) affects the optical, structural and gamma rays shield ability of borate glasses. To accomplish this, a series of borate-based glasses was fabricated according the chemical formula 60B2O3 + (40-x) BaO + xBi2O3, where 0 < x < 10 wt.%. X-ray diffraction confirmed that an amorphous phase was present at all fabricated glasses. Thermal analysis indicated that Bi2O3 could serve as a glass modifier for all values of x greater than zero. Furthermore, the optical absorption profile showed that the samples had a greater absorption rate as x increased within the 1–4 eV photon energy range, with only minor fluctuations beyond 4 eV. Monte Carlo simulation demonstrated that increasing the concentration of Bi2O3 led to an increased radiation-absorbing capacity, where the linear attenuation coefficient of the fabricated glasses enhanced by 26% from 74.48 to 94.17 cm−1 at gamma ray energy of 0.015 MeV. Simultaneously, the half value thickness for the fabricated glasses reduced from 3.99 to 3.73 cm, raising the Bi2O3 concentration between 0 and 10 wt.%, respectively. These results indicate that adding Bi2O3 to boron oxides can significantly improve shielding the ability of the material to against gamma rays, alter the glass samples, and potentially be cost-effective. This study could lead to faster synthesis processes for glass modifiers, with important implications for designing and producing materials to shield against harmful gamma rays in industrial and medical applications. [ABSTRACT FROM AUTHOR]

The radiation shielding properties of lead fluoroborate glasses containing 30 mol% SiO2 have been examined using Phy-X software. The mass attenuation coefficient (MAC) results demonstrated that the tetsed glasses are good attenuator against the low energy radiation, and their attenuation performance diminishes as the energy of the radiation increases. The MAC increases with the addition of PbF2, and the difference in MAC between the glasses with different PbF2 contents is significantly high at lower energy region. At high energy, the difference in MAC between the glasses is small which suggested that as the energy of the photons increases, the MAC for these glasses tend to converge. The linear attenuation coefficient (LAC) for the glasses is investigated and we found that the LAC for the glass with 49 mol% of PbF2 is 58% bigger than that of the glass with 21 mol%. We investigated the average half value layer ( HVL ¯ ) for the tested glasses when exposed to 137Cs and 60Co and the results showed that the values of HVL ¯ for 60Co are about double those for 137Cs for all glasses, which suggests that the energies emitted by 60Co in general penetrate the glass sample more deeply in comparison with the photons emitted by 137Cs. The mean free path (MFP) of the glasses against the density shows the desirable properties of PbF2, as the MFP values decrease when the density increases. [ABSTRACT FROM AUTHOR]

The influence of chemical elements in the composition of optical glasses on the quantitative characteristics of their attenuation of X-ray and gamma radiation is analyzed. The method of calculating the mass coefficients of radiation attenuation (MCRA) with quantum energy ranging from 0.2 to 3.0 MeV for oxides as glass components is proposed. The chemical elements and their oxides in the glass composition, which make the main contribution to their values of the linear coefficient of radiation attenuation (LCRA) with different quantum energies, E, are identified. In the field of quantum energies ranging from 0.2 to about 1.0 MeV, oxides such as PbO, Ta2O5, Gd2O3, La2O3, BaO, Sb2O3 (due to its low concentration, its contribution to LCRA is usually negligible), CdO, Nb2O5, ZrO2, and Y2O3 have a strong effect (in decreasing order) on the LCRA values of glasses. It is shown that in the field of E values ranging from 0.2 to about 1.0 MeV, elements (or their oxides) can be very different from each other in terms of their MCRA values, and glasses of different compositions, in terms of their LCRA values, while at E > 1.0 MeV, both the first and second coefficients change approximately equally with an increase in the energy of radiation quanta. [ABSTRACT FROM AUTHOR]

Recently, there has been a surge of interest in the application of radiation-shielding materials. One promising research avenue involves using free-lead metal oxides/polymer composites, which have been studied for their radiation shielding and characterization properties. This study reinforced the dimethylpolysiloxane (silicone rubber) composites with micro- and nano-sized particles of tin oxide, cadmium oxide, and bismuth oxide as additive materials. The composites were tested with 20 and 50 weight fractions, and their attenuation coefficients were measured using a NaI(TI) detector at gamma-ray energies ranging from 59.54 to 1408.01 keV. Also, the thermal and mechanical properties of the composites were observed and compared with those of free silicone rubber. The results showed that the 50% nano metal oxide/SR composites exhibited better thermal stability and attenuation properties than the other composites, also possessing unique attributes such as lightweight composition and exceptional flexibility. Consequently, this composite material holds immense potential for safeguarding vital organs, including the eyes and gonads, during radiological diagnosis or treatment procedures. Its exceptional ability to absorb a significant portion of incident rays makes it an invaluable asset in the field of radiation protection. [ABSTRACT FROM AUTHOR]

The role of the [Na2O]/[CuO] ratio in two glass groups with a chemical formula of (50 − y/2)Na2O–yCuO–(50 − y/2) P2O5 (y = 0.0–40 mol%) coded as Line I and (50 − y)Na2O–yCuO–50P2O5 (y = 0.0–50 mol%) coded as Line II on physical and gamma-ray attenuation properties have been deeply investigated. The density (ρ) varied from 2.471 to 3.262 g/cm3 and from 2.471 to 3.113 g/cm3 for Line I and Line II glasses, respectively. The molar volume (Vm) values varied from 41.280 to 28.526 cm3/mol and from 41.280 to 35.609 cm3/mol for Line I and Line II glasses, respectively. The oxygen molar volume (OMV) reduced from 13.761 to12.972 cm3/mol and from 13.761 to 11.873 cm3/mol, while the oxygen packing density (OPD) improved from 72.674 to 77.124 and from 72.674 to 84.253 g.atom/l for Line I and Line II glasses. The mass and linear attenuation coefficients (MAC and LAC) values corresponding to the Line II glass is slightly lower than their counterpart of the Line I. The effective atomic numbers (Zeff) and electron density (Neff) for glasses in Line I was lower than that for those in Line II. Exposure (EBF) and energy absorption (EABF) buildup factors have the same trend in both glass groups. The findings support the capability to utilize the examined glasses as radiation shielding materials. [ABSTRACT FROM AUTHOR]

The widespread use of composites in an ionizing environment raises durability concerns, particularly when performance is required over a longer period, in a radiation environment. The goal of this study was to measure the attenuation coefficient for the polymer composite developed for the radiation shielding application and validate it with the well-known Monte Carlo simulation. A radiation-hardened epoxy resin was developed in the laboratory by utilizing various compositions which is capable of being employed as a shielding material in a nuclear environment. To develop a radiation-hardened layer, to some extent, raised the density of the material, using suitable fillers. Polymer stabilizers were used single or in combination. The specimens were irradiated to determine the developed material's shielding properties. The prepared composites' radiation absorption is evaluated using an absorption coefficient. Experiments with gamma radiation using an Am Be Neutron source were conducted to determine the linear absorption coefficient. Monte Carlo simulation was utilized to predict the absorption coefficient for developed composites and the results were compared with experimental data. [ABSTRACT FROM AUTHOR]

In this research, using Geant4 Monte Carlo simulation tool, we have investigated the shielding properties of aluminum oxide, magnesium fluoride, aluminum fluoride, titanium dioxide, magnesium diboride, magnesium silicide, calcium disilicate, and Fluental in the energy range of 0.015 to 10 MeV. In this review, we have calculated and analyzed the linear attenuation coefficient (LAC) and mass attenuation coefficients (MAC), half-value layer (HVL), tenth value layer (TVL), mean free path (MFP), and effective atomic number, effective electron density, equivalent atomic number and buildup factor. In the continuation of the work, we have compared the calculated results of mass attenuation coefficient by Geant4 Monte Carlo simulation tool with the experimental results of others and with the simulation data by XMuDat code, and they have a very low relative error and are in good agreement with each other. Finally, the results obtained for the selected materials are shown in appropriate figures. [ABSTRACT FROM AUTHOR]

This study investigates the gamma radiation shielding properties of cement–ball clay matrix composites doped with micro- and nano-sized cadmium oxide (CdO) particles. The linear attenuation coefficient (LAC) was determined using a sodium iodide (NaI) detector and five radioactive point sources with energies ranging from 59.5 to 1408 keV. The LAC values obtained were compared to the XCOM database and found to be in good agreement. The composites' half-value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Zeff), equivalent atomic number (Zeq), and absorption buildup factor (EABF) were determined. The results showed that the addition of CdO particles improved the radiation-shielding behavior of the composites and increasing the weight fraction of CdO particles increased the shielding effectiveness. The results also illustrated that when nano-sized CdO particles were compared to their micro-sized counterparts, there was a significant enhancement in radiation shielding effectiveness. For instance, a composite material composed of 50% cement, 41.7% ball clay, and 3.8% nano CdO at an energy level of 0.0595 MeV exhibited a remarkable 12.2% increase in attenuation, surpassing the performance of the micro-sized sample with an equivalent concentration. Similarly, another composite consisting of 50% cement, 33.3% ball clay, and 16.7% nano CdO demonstrated a significant 15.4% increase in attenuation at the same energy level, when compared to the micro-sized sample. The study demonstrates the potential of CdO-doped cement–ball clay matrix composites for gamma radiation shielding applications. [ABSTRACT FROM AUTHOR]

Bi2O3–TeO2–CdO glasses' structural, thermal, optical, and gamma ray shielding behaviour were studied. Raman spectroscopy revealed that the glasses include BiO3, BiO6, TeO4, TeO3 units as well as CdO metal oxide clusters. The glasses lost just a small percentage of their original weight (less than 2%) on heating upto 800 °C, indicating that they can survive extreme heat without suffering any major changes to their structure or capabilities. The glass transition temperature (Tg) drops from 455 to 408 °C when Bi2O3 is added. The thermal profile of the glasses shows two exothermic peaks. As the Bi2O3 concentration in the samples rose, the indirect band gap energy dropped from 3.066 to 2.951 eV. With the use of the Phy-X program, the radiation shielding parameters have been calculated for the prepared glasses for energies ranging from 0.015 to 15 MeV. The linear attenuation coefficient (LAC) is high at 0.015 MeV (varied between 485.4 and 538.8 cm−1 for CTB4 glass, which is the glass with the largest percentage of Bi2O3, demonstrates the highest levels of LAC. The enhancement in the LAC due to the inclusion of Bi2O3 is observed in the prepared glasses. The enhancement in LAC is more pronounced at lower energies, especially below 0.03 MeV. From the effective atomic number data, increasing the amount of Bi2O3 in the glasses results in improved radiation shielding efficacy, particularly at lower energy. [ABSTRACT FROM AUTHOR]

The incorporation of Bi2O3 in the Bi2O3–BaO–V2O5 (BBV) glasses leads to higher density and molar volume. The average cross-link density ( n ¯ c ) increases from 4.2 to 4.8 cm−3 whereas the number of bonds per unit volume (nb) decreases from 4.974 × 1022 to 4.753 × 1022 as Bi2O3 is incorporated into the BBV glasses. The high values of elastic moduli indicate that the present glasses are resistant to any kind of the deformations when subjected to any kind of forces. The fractal bond connectivity (d) values indicate the 2D structure of the present glasses. Using Phy-X software, the radiation shielding capabilities were studied when Bi2O3 was used in place of BaO. The authors determined the linear attenuation coefficient (LAC) and discussed the change in this parameter due to the addition of Bi2O3 to the glasses. The glass with 20 mol% of Bi2O3 has the highest LAC and also has the highest effective atomic number. The minimum half value layer values was reported at 0.284 MeV and are equal to 1.220, 0.964 and 0.691 cm for the glasses with 5, 10 and 20 mol% of Bi2O3 respectively. The HVL increases with increasing energy, indicating that the samples are more efficient at shielding the low-energy radiation. At 0.347 MeV, the Zeff values are equal to 18.16, 21.09 and 26.05 for the samples with 5, 10 and 20 mol% of Bi2O3 respectively. The tenth value layer decreased with increasing density; for example, at 0.511 MeV, the layer decreased from 6.886 to 4.887 cm as the density increased from 3.6 to 4.281 g/cm3. The mean free path (MFP) was calculated and compared at 0.284 MeV. The authors found that BBV3 has the smallest MFP (0.997 cm) of the three examined glasses. [ABSTRACT FROM AUTHOR]

The study aimed to present an alternative method that is applicable to develop the perfect tissue-equivalent material that is completely tissue equivalent in all of its gamma-ray interaction properties. In this work, a Monte Carlo code has been written and simulations have been performed to achieve the gamma-ray interaction data details for the selected body tissues and tissue substitutes quoted from the ICRU Reports that are required for accurate assessment in radiotherapy, radiodiagnosis patient dosimetry and radiation protection. Accurate values of the linear attenuation coefficient for the selected absorber samples have been calculated by using simulation outputs. A comparison has been made with theoretical and experimental data that has appeared in the literature. The results presented in the tables, appear to be close to each other, which shows that the simulation procedure used in this work is suitable for use in such kinds of studies. The results reported here imply that the method presented in this study is important and reliable in providing convenient substitutes for certain treatment procedures for phantoms, radiation detectors, detector walls and tissue-equivalent proportional counters. [ABSTRACT FROM AUTHOR]

In this study, the gamma ray shielding properties of shields prepared from polyvinyl alcohol as a base material reinforced with barium sulfate nanoparticles at different reinforcement ratios (5,15,25,35,45 %) and thickness 1 cm were studied. To determine the acceptability of these shields for use in gamma ray protection, some parameters including linear attenuation coefficient (μ), mean free path (λ), and half value layer (HVL) were determined using133Ba, 22Na, 137Cs, and 60Co radioactive sources that produced gamma rays with energies of (356, 662, 1173, 1275 and 1332 KeV). The (NaI (Tl)) gamma system was employed for this purpose. The fabricated shields' effective atomic number was also determined. The findings demonstrated that as the reinforcement ratios of the nano-barium sulfate were raised, the linear attenuation coefficient and the effective atomic number of the shields inceased. The mass attenuation coefficient, mean free path and the half value layer decreased as the nano-barium sulfate reinforcement ratios increased. [ABSTRACT FROM AUTHOR]

In this paper, shielding characteristics of three concrete samples with different B4C, Fe3O4, and BaSO4 contents were examined by determining their theoretical and experimental mass attenuation coefficients at photon energies of 15 MeV The mass attenuation coefficients pm were theoretically calculated using the chemical compositions of samples with the XCOM program. Then the linear attenuation coefficients p were calculated by knowing thevalues. Elekta Axesse accelerator was used to experimentally determine the linear attenuation coefficients p of samples with various impurities. The p value of 0.4699 cm-1, 0.6072 cm-1, and 0.7194 cm-1 was obtained for the blank sample, sample with magnetite, and sample with barite, respectively, at 15 MeV The results were compared with coefficients obtained by XCOM and indicated a good agreement between the two methods. The linear attenuation coefficient was evaluated to calculate the half- and tenth-value layers. Compared to conventional concrete, the linear attenuation coefficient for concrete with the highest barite content increased by 53.1 %, and the thickness of the half-attenuation layer decreased by 34.7 %. Such a sample can be used as a building material for medical centers and nuclear power plants. [ABSTRACT FROM AUTHOR]

Lead shielding materials are standard for radiation protection to limit exposure for patients and health care workers. However, lead is both heavy and highly toxic. The benefits of non-lead products are becoming and interesting because they offer the benefits of being cheaper, lighter and non-toxicity. This study has explored the radiation shielding efficacy of bismuth oxide (Bi2O3) loaded into the epoxy-resin for a Technetium-99m (99mTc) and Iodine-131 (131I) radiopharmaceutical container. Gamma ray attenuation parameters of the samples were investigated and compared with original lead shielding. The results showed that linear attenuation coefficient and percentage attenuation are increased with increasing filler loading. In contrast, the half-value layer values were decreased when more Bi2O3 was added. The 50 wt% Bi2O3 provided the best gamma ray attenuation efficacy with attenuations of 99.99% and 99.87% at gamma ray energy 140 and 364 keV, respectively. In comparison to lead, the 50 wt% Bi2O3 presented a slightly different attenuation of about 1.64%, while the heaviness was halved. Therefore, we hypothesize that Bi2O3 loaded into the epoxy-resin has gamma ray shielding potential for containing 99mTc and 131I radiopharmaceuticals while both reducing cost and weight. [ABSTRACT FROM AUTHOR]

This study aimed to develop a mortar composite with improved gamma ray shielding properties using WO3 and Bi2O3 nanoparticles, as well as granite residue as a partial replacement of sand. The physical properties and effects of sand substitution and nanoparticle addition on the mortar composite were analyzed. TEM analysis confirmed the size of Bi2O3 and WO3 NPs to be 40 ± 5 nm and 35 ± 2 nm, respectively. SEM images showed that increasing the percentage of granite residues and nanoparticles improved the homogeneity of the mixture and decreased the percentage of voids. TGA analysis indicated that the thermal properties of the material improved with the increase in nanoparticles, without decreasing the material weight at higher temperatures. The linear attenuation coefficients were reported and we found that the LAC value at 0.06 MeV increases by a factor of 2.47 when adding Bi2O3, while it is enhanced by a factor of 1.12 at 0.662 MeV. From the LAC data, the incorporation of Bi2O3 nanoparticles can greatly affect the LAC at low energies, and still have a small but noticeable effect at higher energies. The addition of Bi2O3 nanoparticles into the mortars led to a decrease in the half value layer, resulting in excellent shielding properties against gamma rays. The mean free path of the mortars was found to increase with increasing photon energy, but the addition of Bi2O3 led to a decrease in MFP and better attenuation, making the CGN-20 mortar the most ideal in terms of shielding ability among the prepared mortars. Our findings on the improved gamma ray shielding properties of the developed mortar composite have promising implications for radiation shielding applications and granite waste recycling. [ABSTRACT FROM AUTHOR]

We developed new composites for photons shielding applications. The composite were prepared with epoxy resin, red clay and bismuth oxide nanoparticles (Bi2O3 NPs). In order to establish which ratio of red clay to Bi2O3 NPs provides the best shielding capabilities, several different ratios of red clay to Bi2O3 NPs were tested. The transmission factor (TF) was calculated for two different thicknesses of each sample. From the TF data, we found that epoxy resin materials have a high attenuation capacity at low energy. For ERB-10 sample (40%Epoxy + 50% Red clay + 10% Bi2O3 NPs), the TF values are 52.3% and 14.3% for thicknesses of 0.5 and 1.5 cm (at 0.06 MeV). The composite which contains the maximum amount of Bi2O3 nanoparticles (40%Epoxy + 50% Red clay + 10% Bi2O3 NPs, coded as ERB-30) has lower TF than the other composites. The TF data demonstrated that ERB-30 is capable of producing more effective attenuation from gamma rays. We also determined the linear attenuation coefficient (LAC) for the prepared composites and we found that the LAC increases for a given energy in proportion to the Bi2O3 NPs ratio. For the ERB-0 (free Bi2O3 NPs), the LAC at 0.662 MeV is 0.143 cm−1, and it increases to 0.805 cm−1 when 10% of Bi2O3 NPs is added to the epoxy resin composite. The half value layer (HVL) results showed that the thickness necessary to shield that photons to its half intensity can be significantly lowered by increasing the weight fraction of the Bi2O3 NPs in the epoxy resin composite from 0 to 30%. The HVL for ERB-20 and ERB-30 were compared with other materials such as (Epoxy as a matrix material and Al2O3, Fe2O3, MgO and ZrO2 as filler oxides in the matrix at 0.662 MeV. The HVL values for ERB-20 and ERB-30 are 4.385 and 3.988 cm and this is lower than all the selected epoxy polymers. [ABSTRACT FROM AUTHOR]

Researchers have recently been working on development of alternative shielding material to be used in radiation shielding purpose. The radiation shielding parameters are expressed by the linear attenuation coefficient (LAC), mean free path (mfp), effective atomic number (Zeff), effective electron density (Neff), and exposure buildup factor (EBF). This is because of hazardous effect of radiation on human cell. In this study, the parameters for shielding materials for gamma rays have been calculated for four different composites where different rates of Fe2O3 were used. The effect of Fe2O3 on the all parameters was also obtained. It was found that the Fe2O3 rate is important on the radiation shielding properties of selected composite materials. [ABSTRACT FROM AUTHOR]

A set of glasses of composition, (ZnO)0.3-(V2O5)0.6 − x-(B2O3)0.1-(MnO)x, where x = 0.05 to 2, was synthesized by melt quenching method. The powder XRD studies revealed nanocrystalline phase of the samples. Room temperature density is found to increase and molar volume to decrease with MnO concentration. Conductivity of the glasses has been measured for the temperature range 303–523 K. The conduction mechanism at high temperature is found to be consistent with Mott's small polaron hopping and Greaves variable range hopping at low temperature. Gamma ray shielding characteristics were evaluated using Phy-X/PSD software for the energy range 0.005–15 MeV. Mass attenuation coefficient (MAC) and linear attenuation coefficient (LAC) were found to be maximum at 0.005 MeV for all the samples. Observed variations of all the shielding characteristics showed evidence for photoelectric dominance at low energy and pair production at high energy levels. Half value layer (HVL), tenth value layer (TVL) and mean free path (MFP) increased with an increase in energy. MFP decreased with an increase of MnO content. Electron density (Neff) decreased with an increase of energy. Equivalent atomic number (Zeq) of the samples is found to be higher than the marbles of different colours and black granite. These results indicate that the present glasses are the suitable candidates for nuclear radiation (gamma rays) shielding at lower energy. [ABSTRACT FROM AUTHOR]

In this study, the shielding capabilities of glasses made of B2O3 − Bi2O3 − SrO − Nd2O3 have been investigated for use in radiation protection applications. Therefore, to simulate the mass attenuation coefficient for the glass samples A, B, C, D, E, and F, we utilized the Monte Carlo simulation Geant4 code. The findings of the simulated mass attenuation (µm) were compared with those that the EpiXS software had theoretically predicted for photon energies between 30 and 2000 KeV. The simulated µm findings and the EpiXS received data were found to be in good agreement. Based on the simulated µm, it was possible to determine the linear attenuation coefficients (µ), effective atomic number (Zeff), effective electron density (Neff), half-value layer Δ0.5, and mean free path (MFP). With an increase in photon energy and a rise in the (mol percent) proportion of Nd2O3, the µm value fell. Due to its greater values of the linear attenuation coefficient, effective atomic number, and lower values of Δ0.5 and MFP, it is discovered that the F glass with 5.7 (mol. percent) concentration of Nd2O3 has superior gamma-ray shielding effectiveness. Additionally, the effectiveness of the chosen glasses in neutron shielding was assessed in this paper. The Monte Carlo simulation Geant4 code was used to determine the effective removal cross-section R (cm−1). As a result of having the highest effective removal cross-section and the lowest HVL at energy 0.5 MeV, it is determined that the F Glass with a 47.2 (mol. percent) concentration of B2O3 and 5.7 (mol. percent) concentration of Nd2O3 has higher neutron shielding qualities than the other glass samples that were chosen. [ABSTRACT FROM AUTHOR]

This study looks at the synthesis of innovative PEO/PVA/SrTiO3/NiO nanocomposites for piezoelectric sensors and gamma shielding applications that are low weight, elastic, affordable and have good gamma ray attenuation coefficients. The impact of SrTiO3/NiO on the structural characteristics of the PEO/PVA mixture is investigated. The polymer mixture PEO/PVA received additions of SrTiO3/NiO at concentrations of (0, 1, 2, 3 and 4) weight percent by the casting method. On the top surface of the films PEO/PVA/SrTiO3/NiO NCs, scanning electron microscopy reveals several randomly distributed aggregates or fragments that are consistent and coherent. An optical microscope image collection reveals that the blend's additive distribution of NPs was homogenous. Gamma ray shielding application results show that the attenuation coefficient of PVA/PEO/SrTiO3/NiO NCs is increased by increasing concentration of SrTiO3/NiO nanoparticles. Radiation protection is another application for it. The pressure sensor application findings of NCs show that, when the applied pressure rises, electrical capacitance (Cp) increase. [ABSTRACT FROM AUTHOR]

We study the theoretical and simulated shielding properties of 69P2O5–10Gd2O3–10BaO–10ZnO–1Er2O3 and 69P2O5–10GdF3–10BaO–10ZnO-1Er2O3 glasses. We exploit advanced simulation (MCNPX) and Phy-X, an online Photon Shielding and Dosimetry software, in the 0.001–15 MeV energy range, to calculate the linear attenuation coefficient and mass attenuation coefficients of the samples. The obtained mass attenuation coefficient is then used to calculate the critical radiation shielding characteristics, such as the half-value layer, mean free path, tenth value layer, and effective atomic number. The calculated LAC values range from 108.759 to 0.097 and from 84.124 to 0.087 cm−1 while HVL values range from 0.006 to 7.164 and from 0.008 to 8.013 cm, and MFP values vary from 0.009 to 10.335 and from 0.012 to 11.561 cm for ZBaOEr and ZBaFEr, respectively, with energy ranging from 0.015 to 15 MeV. We find that the results obtained from MCNPX and Phy-X are consistent with each other, based on the computed relative difference. The glass sample containing Gd2O3 exhibits better shielding properties than the one with GdF3, over the entire energy range. Our examined glass samples are thick enough to substantially lessen the intensity of incident X-rays and gamma rays. [ABSTRACT FROM AUTHOR]

The study of radiation shielding properties for a material is an important part of research in scientific world. It is expressed in terms of the linear linear coefficients (LAC) which can also be used to obtain some other parameters. The gamma shielding properties of glass with addition of boron oxides in different amounts were studied, thereby obtaining linear attenuation coefficients (LAC), mean free path (mfp), Exposure Buildup factor (EBF) which were calculated using Phy-X/PSD code. It was found that increasing boron oxide content of 0, 2, 4, 6, 8 (w %) in glass increased the gamma attenuation coefficients. [ABSTRACT FROM AUTHOR]

In this investigation, the photons shielding factors for tungsten tellurite glasses with the yWO3–(90 − y)TeO2–10Na2O (y = 05, 10, 15 and 20 mol%), were reported. The penetration and attenuation factors for this system at various energies were reported using the Phy-X/PSD program. With increasing energy, it is observed that the linear attenuation coefficient (LAC) values, which range from 1.087–0.234 cm−1 (for TWN1) to 1.354–0.248 cm−1 (for TWN4), decrease exponentially. The LAC values were found to increase with the addition of WO3 from 1.087 to 1.354 cm−1 at 0.245 MeV and from 0.515 to 0.586 cm−1 at 0.444 MeV. Additionally, the greater potential for photon interactions at higher WO3 concentrations was indicated by the findings of the effective atomic number (Zeff) calculation. According to the obtained results, the maximal Zeff occurred at 0.284 MeV, which is equivalent to 32.53 for TWN1 and 36.89 for TWN4. The half value layer (HVL) for the samples under consideration between 0.245 and 1.458 MeV has been determined using the Phy-X/PSD. The HVL results demonstrated that at 0.284 MeV, more gamma rays are shielded whereas the potential of photon shielding decreases as energy increases. The tenth value layer (TVL) increased with rising energy and decreased with rising WO3 concentrations. TVL for TWN4 is the lowest (1.701 cm at 0.245 MeV and 9.284 cm at 1.458 MeV). [ABSTRACT FROM AUTHOR]