Search

This study proposing an environmentally friendly and lead (Pb)-free alternative in the form of electrospun mats of Bi2O3/WO3/PVA for X-ray shielding. By varying Bi2O3 filler loading (0–20 wt%) while keeping WO3 filler constant at 10 wt%, the study examined density, thickness, and mass attenuation coefficient (µ) of the fabricated mats. X-ray attenuation was evaluated across different X-ray energy levels (16.61–25.27 keV) using X-ray fluorescence (XRF) unit. Meanwhile, the surface morphology and nanoparticle dispersion within the PVA nanofiber mat were observed through Field Emission Scanning Electron Microscope (FESEM). Results demonstrated improved X-ray attenuation with increased Bi2O3 filler loadings, except for mats containing 20 wt% Bi2O3 and 10 wt% WO3 (mat B5) due to coagulation and porosity issues. The electrospun mat with 15 wt% Bi2O3 and 10 wt% WO3 (mat B4) exhibited the highest X-ray attenuation. Thus, electrospun mat B4 is proposed as a promising candidate for environmentally friendly X-ray shielding material. [ABSTRACT FROM AUTHOR]

The following glass system 35Pb3O4- 60SiO2-(5-x) ZnO- xY2O3 (x = 0, 1, 2, 4, 5) mol.% is fabricated by the classic melt-quench method. Amorphous status was confirmed by XRD analysis techniques. Structure features were influenced by yttrium oxide doping like density(5.91 to 6.97 g/cm3), molar volume (47.39 to 41.22 cm3), oxygen packing density(17.88 to 14.99 cm3), internuclear distance and number of ions (0.69 to 3.7 × 1021). Linear and non-linear optical properties are taking place. The energy gap was found to be increased from 2.59 to 2.72 eV with supplying of yttrium ions until 5 mol.% while the index of refraction decreases from 2.55 to 2.51. The nonlinear susceptibility (χ(3)) and refractive (n2) index decrease with increased yttrium concentration and have the values 0.396 to 0.351 × 10–12 (esu), 5.85 to 5.28 × 10–12 (esu) respectively. Molar refraction (12.3 to 12.32 cm3/mol.), Metallization(0.36 to 0.362), Electronegativity (0.696 to 0.704), Transmission coefficient (0.679 to 0.682) and steepness (0.097 to 0.103) were increased while the Molar polarizability (12.03 to 10.43 Ao3), Reflection loss (0.64 to 0.638), electronic polarization (2.873 to 2.866), Optical Basicity (1.352 to 1.348) and Static, Dielectric constant decreased with introduced yttrium ions. The radiation shield protection parameters like LAC (0.702 and 0.909 cm−1), MFP (1.425 and 1.1 cm),ECS (3.41 × 10−25 and 3.56 × 10−25), ACS (1.07 × 10−23 and 1.23 × 10−25), Neff (3.48 × 1023 and 3.67 × 1023), Zeff (31.25 and 34.56), R (0.66 and 0.59) and FNRCS (0.099 and 0.123) are investigated the provided values at 0.5 MeV for ZPSY0 and ZPSY5 respectively. The results indicate that Y2O3 growing in the network of glass modifies and improves the quality of present glasses against gamma radiation and fast neutrons. The superior glass sample in the present study is ZPSY5 which has 5 mol.% of Y2O3. The ZPSY5 sample can be used as a γ shield or neutrons collide in nuclear applications. [ABSTRACT FROM AUTHOR]

With the development of society and technology, machinery and equipment have enhanced our work efficiency but have also introduced various hazards, such as electromagnetic radiation, medical, industrial, and agricultural rays. The harms these radiations inflict on human health are significant, with severe cases leading to cancer, disability, or even life-threatening situations. Therefore, effective protective measures in some fields are crucial. This paper firstly summarized the basic principles of radiation protection for different rays, then systematically introduced the widely used manufacturing methods for flexible radiation shielding materials, including weaving with metal fibers, fiber blending, silver-plated fibers, and so on. Subsequently, the paper reviewed the testing methods of radiation-protective clothing materials. Finally, it comprehensively concluded the discussions on flexible radiation shielding materials and offered a perspective on their future development trends. [ABSTRACT FROM AUTHOR]

This paper thoroughly examines lanthanum-doped lead titanate (PbLaxTi(1−0.75x)O3), a perovskite-based ceramic material, focusing on its structural properties, vibrational behavior, and radiation shielding capabilities. Using advanced techniques like X-ray diffraction (XRD), Fourier transform infrared (FTIR) spectroscopy, and transmission electron microscopy (TEM), we explore the intricate relationship between lanthanum doping levels and material properties. Additionally, we assess its radiation shielding potential through metrics. Computational approaches employing the FLUKA code help evaluate theoretical values. Our findings reveal that increasing lanthanum concentration alters crystal atom arrangement, influences vibrational patterns, and enhances radiation shielding effectiveness. Increasing lanthanum concentration resulted in a maximum 7.55% rise in the mass attenuation coefficient (MAC) at 0.059 MeV. The half-value layer (HVL) decreased by 4.68% at 1.33 MeV, and the mean free path (MFP) decreased by 5.78% at 1.41 MeV with increased lanthanum ratio. Moreover, the radiation protection efficiency (RPE) increased from 30.7779 to 32.67442% at 0.059 MeV as lanthanum content increased. These findings offer valuable insights into material characteristics and suggest potential applications in enhancing radiation shielding for medical and industrial purposes. This comprehensive analysis provides practical insights for potential applications, particularly in medical or industrial radiation protection. The data-driven approach here paves the way for future research at the intersection of data science and material science, advancing material design and understanding doped perovskite materials. [ABSTRACT FROM AUTHOR]

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

Glass is a versatile material with diverse structures and technological applications depending on composition and attributes. In the present study, the optical, physical, and radiation-interaction-response parameters of 70B2O3: 10Na2O: 15PbO: (5-x)Tb2O3: xBi2O3, with x = 2, 3, 4, 1nd 5 mol% glasses prepared using the melt-and-rapidly cool method were assessed and studied. The mass attenuation coefficients ( μ / ρ ) were evaluated for 0.2, 0.662, and 1.25 MeV photons with the aid of XCOM. The density of the glass system increased from 3.61 g/cm3 to 3.70 g/cm3 as the molar ratio of Bi2O3 relative to Tb2O3 increased from 0.67 to 5. Also, the molar volume of the glasses increased from 29.958 cm3/mol to 35.973 cm3/mol for the same molar ratio increase. The refractive index of the BNPBTx glasses increased from about 2.22 to 2.5. The molar refractivity and polarizability increased with Bi2O3 content within the range of 16.98–20.69 cm3/mol and 6,74 × 10–24–8.21 × 10–24 cm3, respectively. Other estimated optical parameters showed variations in contrast to glass chemical content. The μ / ρ vary within the range 0.0566–0.4720 for BNPBT1; 0.0568–0.4898 for BNPBT2; 0.0570–0.5074 for BNPBT3; and 0.0572–0.5246 cm2/g for BNPBT4. The increase in the Bi2O3/Tb2O3 concentration ratio improved the gamma photon and neutron interaction prowess of BNPBT glasses. The investigated glasses showed better radiation shielding abilities compared to existing shielding glasses. They are thus recommended for radiation control and optical applications. [ABSTRACT FROM AUTHOR]

Rare earth elements (RRE), due to their unique magnetic, electrical, and optical properties, are an important group of elements demanded in many application areas from machine technology to the health industry. In this study, new composites were obtained by mixing Erbium oxide (Er2O3), one of the rare earth element oxides, into PCL–PEG blend, which is also an important material group, in different ratios. The characteristic functional groups of the obtained polymer blend/Er2O3 nanocomposites were determined by the ATR-IR, and as the erbium oxide ratio increased, characteristic peaks of the polymers in the blend as well as characteristic signals of the Er–O–Er bond were found. When the thermal behavior of the obtained composites was examined, it was observed that the polymer blend exhibited miscible blend properties and the melting temperature of the polymer blend increased as the Er2O3 ratio increased. In addition, it was determined that the thermal stability of the composite increased significantly. X-ray measurements of composites at room temperature support other measurement results. It was determined that the presence of Er-RRE oxide increased the crystal structure feature in the polymer blend composite. Gamma radiation shielding capabilities of polymer materials containing different erbium ratios were investigated by calculating shielding parameters such as half value layer (HVL), radiation protection efficiency (RPE), and mean free path (MFP). Cs-137 and Co-60 radioactive sources were used as gamma sources. According to the obtained measurement results, Erbium oxide increased the absorption property of the polymer composite material. [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]

Polymeric based composites have gained considerable attention as potential candidates for advanced radiation shielding applications due to their unique combination of high-density, radiation attenuation properties and improved mechanical strength. This study focuses on the comprehensive characterisation of polymeric based composites for radiation shielding applications. The objective of this study was to evaluate the physical, mechanical and microstructural properties of tungsten carbide-based epoxy resin and tungsten carbide cobalt-based epoxy resin for its efficiency in shielding against gamma-rays ranging from 0.6 up to 1.33 MeV. Polymeric composites with different weight percentages of epoxy resin (40 wt%, 35 wt%, 30 wt%, 25 wt%, 20 wt%, 15 wt% and 10 wt%) were fabricated, investigated and compared to conventional lead shield. The attenuation of the composites was performed using NaI (Tl) gamma-ray spectrometer to investigate the linear and mass attenuation coefficients, half value layer, and mean free path. High filler loadings into epoxy resin matrix (90% filler/10% epoxy) exhibited excellent gamma shielding properties. Mechanical properties, such as hardness were examined to assess the structural integrity and durability of the composites under various conditions. The fabricated composites showed a good resistance, the maximum hardness was attributed to composites with small thickness. The high loading of fillers in the epoxy matrix improved the microhardness of the composites. The distribution of the filler powder within the epoxy matrix was investigated using FESEM/EDX. The results revealed the successful incorporation of tungsten carbide and cobalt particles into the polymer matrix, leading to increased composite density and enhanced radiation attenuation. The unique combination of high-density, radiation attenuation, and improved mechanical properties positions polymeric based composites as promising candidates for radiation protection field. [ABSTRACT FROM AUTHOR]

Radiation safety and protection is a subject of major concern for all communities because of the biological damage caused by different radiation sources. Therefore, the purpose of this study is aimed to synthesize two different thin films from a newly synthesized N-Al2O3@Pb(II)-2,4-DiNA nanocomposite which was prepared by the direct chemical coupling of nano-aluminum oxide (N-Al2O3) with Pb(II)-2,4-dinitroaniline complex. The synthesized materials were characterized by FT-IR, thermogravimetric analysis (TGA), scanning electron microscope SEM, and elemental composition by energy-dispersive X-ray (EDX). The two thin films were assembled by the encapsulation of N-Al2O3@Pb(II)-2,4-DiNAnanocompositeinto hydrolyzed polyurethane and hydrolyzed polyvinyl chloride. Electron spin resonance (ESR) measurements have been used to investigate the newly prepared nanocomposite and thin films before and after gamma irradiation. Gamma spectroscopy, Phy-X software, and SRIM (stopping and range of ions in matter) Monte Carlo simulation code are aimed to apply and investigate radiation shielding efficiency of films for gamma/x-ray, protons, alpha, and thermal neutrons. The gamma shielding characteristics, mass stopping power (MSP), and range for both proton (H-ions) and alpha (He-ions) were also calculated. In addition, the SRIM code's subroutine TRIM was used to predict the damage production and atomic displacements per atom (dpa) caused by the interaction of high-energy H-ions (proton) and He-ions (alpha) with the studied samples. The data obtained the good radiation shielding effect of the prepared thin films and their possible use as radiation shielding materials for X-rays and low gamma energy. [ABSTRACT FROM AUTHOR]

Radiation shielding materials based on composites play a crucial role in safeguarding nuclear-related installations, equipment, and employees from harmful radiation. With the advent of new and challenging nuclear security conditions, the development of radiation-protective materials has undergone significant changes. Thanks to the advancements in science and technology, especially in the field of nanomaterials technology, it is now possible to produce radiation protection materials that offer high all-around performance. This article discusses the current research on composite-based radiation shielding materials. It first describes the current state and distribution of radiation shielding studies worldwide. Then, it categorizes and reviews composite-based radiation protection materials, taking into account the study topic and the field's requirements. The three broad categories of composite-based radiation protection materials are polymer-based composites, metal-based composites, and fabric-based composites. Space radiation shielding materials are categorized separately (as a point of reference). The mechanical, thermal, and shielding properties of radiation protection materials are briefly discussed here. In addition, the primary research challenges are outlined along with the research methodologies that academics employ to examine properties and property change trends. Finally, a summary of the properties of the radiation protection materials discussed in the complete paper is provided, followed by an analysis of the current research gaps and potential future paths. [ABSTRACT FROM AUTHOR]

This study investigates the physical and optical properties as well as the radiation shielding capacity of polyvinyl chloride (PVC) loaded with x% of bismuth vanadate (BiVO4) (x = 0, 1, 3, and 6 wt%). As a non-toxic nanofiller, the designed materials are low-cost, flexible, and lightweight plastic to replace traditional lead, which is toxic and dense. XRD patterns and FTIR spectra demonstrated a successful fabrication and complexation of nanocomposite films. In addition, the particle size, morphology, and elemental composition of the BiVO4 nanofiller were demonstrated through the utilization of TEM, SEM, and EDX spectra. The MCNP5 simulation code assessed the gamma-ray shielding effectiveness of four PVC + x% BiVO4 nanocomposites. The obtained mass attenuation coefficient data of the developed nanocomposites were comparable to the theoretical calculation performed with Phy-X/PSD software. Moreover, the initial stage in the computation of various shielding parameters, such as half-value layer, tenth value layer, and mean free path, besides the simulation of linear attenuation coefficient. The transmission factor declines while radiation protection efficiency increases with an increase in the proportion of BiVO4 nanofiller. Further, the current investigation seeks to evaluate the thickness equivalent (Xeq), effective atomic number (Zeff), and effective electron density (Neff) values as a function of the concentration of BiVO4 in a PVC matrix. The results obtained from the parameters indicate that incorporating BiVO4 into PVC can be an effective strategy for developing sustainable and lead-free polymer nanocomposites, with potential uses in radiation shielding applications. [ABSTRACT FROM AUTHOR]

A novel material bismuth–copper–boron nanocomposite has been synthesized in the present study using the solution combustion technique. The microstructure of the compound has been studied using SEM, XRD and FTIR techniques which are used to explore the physical and chemical structure of the novel material. The optical properties are studied using a UV–visible analysis. The radiation shielding efficiency has been investigated in detail theoretically and experimentally. Several gamma shielding parameters, neutron and bremsstrahlung shielding parameters have been estimated for the novel material in the present study. The linear and mass attenuation coefficient decreases with an increase in energy whereas the tenth value layer thickness increases with an increase in energy. The radiation protection efficiency is found to be high in the lower energy range when compared to the higher energy range. Crystalline size is determined by PXRD studies which proves the crystalline nature of the novel material. The chemical structure and functional groups are determined by the FTIR analysis and energy gap is found out to be 2.87 eV from UV visible studies. The studied sample has shown good gamma shielding ability in the lower energy range. EDX spectrum confirms the presence of bismuth, boron and copper nanocomposites. In addition, the said material is found to possess good absorption ability for neutrons and bremsstrahlung radiations. [ABSTRACT FROM AUTHOR]

Radiation is now used extensively for a variety of industrial, agricultural, and radiation therapy objectives, as well as other uses, thanks to the advancement of technology. Due to the destructive effects of radiation, radiation protection is so necessary. Although lead and lead-based composites are conventional materials for radiation shielding, their toxic nature restricted the use of them as proper shields. Therefore, the shielding properties of a series of lead-free relaxor ceramics, namely (1 − x)K0.5Na0.5NbO3–xLa(Mn0.5Ni0.5)O3 ceramics are investigated in this study. In order to obtain the neutron and gamma-ray shielding characteristics, the linear attenuation coefficient (LAC, cm−1) and related parameters for (1 − x)K0.5Na0.5NbO3–xLa(Mn0.5Ni0.5)O3 (where x = 0.01, 0.05, 0.07, 0.10, 0.15, and 0.20) ceramic are estimated (abbreviated as (1 − x)KNN–xLMN)). Using FLUKA simulating code and Phy-X:PSD software, the shielding performance of neutrons and gamma rays is evaluated for wide energy ranges. Findings show that the S6 sample possesses the lowest mean free path (MFP) and half value layer (HVL), while the S1 sample owns the highest MFP and HVL. At an energy range between 0.001 and 0.1 MeV, sudden jumps are observed for Zeff and Neff graphs, which may be due to the K-edge absorption of elements such as K, Na, Nb, La, Mn, and Ni. Moreover, the fast neutron removal cross-section (FNRCS) varies between 0.060 and 0.106 cm−1 from the S1 to S6 samples. [ABSTRACT FROM AUTHOR]

Radiation is important in dental science as it is used in both diagnostic and also in treatment issues. The teeth are every single day exposed to a significant amount of wear due to remaining hard particles from food and tooth brushing or even due to the contact with the other teeth. Dental restorations are widely used to correct the damage caused by this wear. In this study, it is aimed to determine the radiation shielding properties of the dosimetric materials which are namely hydroxyapatite (HAP) and urethane di(meth)acrylates (UDMAs). The linear attenuation coefficients of dosimetric materials were calculated using GAMOS (Geant4-based Architecture for Medicine-Oriented Simulations) Monte Carlo simulation code. The obtained results were also compared with the calculation done using XCOM. The mean free path (mfp), half value length (HVL), and tenth value length (TVL) have also been obtained. The highest LAC value was obtained for S2 sample for 511, 662, 835, 1173, 1275, and 1332 keV energies (0.170, 0.149, 0.133, 0.112, 0.108, and 0.105 cm−1, respectively) and the lowest LAC values were obtained for S3 sample for 511, 662, 835, 1173, 1275, and 1332 keV gamma energies (0.102, 0.091, 0.082, 0.069, 0.066, and 0.065 cm−1, respectively). [ABSTRACT FROM AUTHOR]

Radiation is an important phenomenon, and it is related to different fields and thus its hazardous effect should be minimized. Radiation protection and radiation dosimetry are developed in order to determine radiation limit values to minimize this hazardous effect. Thus, with other time and distance methods for radiation protection, shielding is the most important way in this purpose. Lead and lead-based materials have been conventional materials for radiation shielding and nowadays alternative materials have been started to be developed and used. For example besides different materials composite materials are under study as alternative to lead and lead-based materials. In this work, the radiation shielding parameters of four different types of hydroxyapatite (HAP) composite and the effect of ZnO on the radiation shielding properties of HAP have been investigated. The materials are selected as (100 − x)HAP + xZnO composite, where x = 0, 1, 4, and 7.5 wt%. The simulations were done to obtain mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), mean free path (mfp), half value length (HVL), tenth value length (TVL), Atomic cross section (ACS), electronic cross section (ECS), effective atomic number (Zeff), Effective electron density (Neff), effective conductivity (Ceff) and fast neutron removal cross section (FNRCS) using Phy-X/PSD code. It was found in study that addiation of ZnO into HAP composite improved gamma radiation shielding properties. It was also seen this effect for neutron shielding properties. [ABSTRACT FROM AUTHOR]

The use of lead as a radiation shield is becoming unpopular due to toxicity concern. Glasses are promising alternatives for eliminating this problem. This study is thus aimed at ascertaining the shielding efficacy of a newly developed glass system against gamma-ray, charged particle, fast, and thermal neutrons. The radiation shielding parameters of the novel PPZLC glass system were theoretically calculated and analysed. The chemical structure of the PPZLC glasses is 65P2O5–10Pb3O4–5ZnO–(20–x)Li2CO3–xCuO where x = 0, 0.4, 0.8 and 1.0 mol% represents PPZLC1, PPZLC2, PPZLC3 and PPZLC4 glasses respectively. The gamma-ray mass attenuation coefficient MAC of the glasses for 0.1–10 MeV photons was calculated by FLUKA simulation and XCOM software. Calculated MAC values varied from 2.025 to 0.031, 2.027 to 0.032, 2.029 to 0.032 and 2.027 to 0.032 cm2/g in the order of PPZLC1-4. Analysis of other photon shielding parameters such as half value layer and mean free path showed that the increase in the concentration of CuO improved the shielding ability of the glasses against photons. Similarly, the trend of projected range of electrons, protons, α-particles and carbon ions showed the absorption capacity of charged particles in the glasses increased from PPZLC1-4. Furthermore, the fast neutron removal cross section increased considerably from 0.1006 to 0.1038 cm−1 for CuO molar concentration increase of 0–1.0 mol%. However, the reduction in the molar concentration of Li2CO3 led to the decline of absorption and total cross section for thermal neutrons in the glasses. Comparing the photon and neutron absorbing capacity of the PPZLC1-4 glasses with common shielding materials, it was observed that the present glasses have potential to function well in radiation absorbing or collimating applications. They can thus be recommended for use as radiation shields in medical and industrial application of photons coupled with fast neutrons, storage for radioactive materials and other related functions. [ABSTRACT FROM AUTHOR]

Glass systems such as Tb2O3-La2O3-P2O5 (TLP-system) exhibit both transparency of visible light and remarkable attenuation of ionizing radiation. In this research article, the TLP-system was explored for potential shielding application against nuclear radiation in various technological facilities. Monte Carlo method is applied by using Geant4 packages to assess the radiation shielding performance of the TLP-system. The validation of the simulation outcomes is achieved by the theoretical calculations. The obtained findings showed that the maximum attenuation coefficients (MACs) of the TLP-system are observed at 0.284 MeV, while the minimum MACs were noticed at 1.275 MeV. At 0.284 MeV photon energy, TLP-A glass with 5 mol% of Tb2O3 has the maximum effective atomic number (Zeff) with worth of 18.3229, whereas the TLP-E glass with 25 mol% Tb2O3 has the maximum Zeff with worth of 21.0558. Moreover, the radiation protection efficiency (RPE) values of the TLP-system decrease with photon energy and increment as the Tb2O3 content increases. [ABSTRACT FROM AUTHOR]

Sodium borosilicate glasses of the composition 47SiO2–13B2O3–20Na2O–(20–x)CaO–xMgO: x = 0, 5, 10, 15, and 20 mol% named as Mg0, Mg5, Mg10, Mg15, and Mg20, respectively, have been synthesized via melt quenching method. The effect of combined ionic substitutions on composition, physical, linear optical, and photon shielding properties was investigated. The density was decreased from 2.6236 to 2.5155 g cm−3, while the molar volume was decreased from 23.2133 to 22.957 cm3 mol−1 for Mg0 to Mg20. The oxygen packing density and field strength were enhanced with increasing Mg2+ ion content. Therefore, the glass structure's rigidity was supported by the decrease in internuclear distance and polaron radius values with increased dopant ion concentration. The optical energy gap was increased from 3.24 to 3.35 eV, and the refractive index from 2.335 to 2.309 for Mg0 to Mg15 glasses. The linear attenuation coefficient of the proposed Mg0-Mg20 glasses obeys the trend (Mg20)LAC < (Mg15)LAC < (Mg10)LAC < (Mg5)LAC < (Mg0)LAC, while the mean free path obeys the trend (Mg0)MFP < (Mg5)MFP < (Mg10)MFP < (Mg15)MFP < (Mg20)MFP. The half value layer (HVL) of Mg0 ranged from 0.034 to 12.546 cm, while Mg20 ranged from 0.061 to 13.714 cm at 0.015 and 15 MeV. The transmission factor was found 43.713% and 75.864% at 5-cm glass thickness and increased to reach 85.35267% and 95.07127% at 1-cm glass thickness at 1 MeV and 15 MeV, respectively. The suggested glasses can be applied in optical devices and radiation protection applications. [ABSTRACT FROM AUTHOR]

The glass system 42.5P2O5–42.5B2O3–( 15 - x ) Li2O– x MoO3 x = (0 , 2.5 , 5.10 and 15 ), was fabricated using a melt-quenching technique. Optical features are examined depending on measuring the absorption and transmission of the prepared glasses. The energy gap ( E opt ), increases from 2.23 to 2.49 e.V. Urbach ( E u ), decreases from 0.513 to 0.5 e.V. Basicity, polarizability, electronegativity, and some physical constants are determined. The temperature of the glass transition Tg, increases from 493 to 532 °C, the temperature of onset glass crystallization Tc increases from 493 to 532 °C and the temperature of the crystallization Tp increases from 606 to 636 °C. Radiation shielding properties have been examined by Phy-X / PSD. The impact of adding MoO3 to the glasses on their shielding ability was investigated. The lower value of the (MFP) sample has been detected at a higher MoO3 concentration and it is good radiation attenuation glasses. For radiation protection applications, the investigational glasses had superior characteristics. [ABSTRACT FROM AUTHOR]

In the current study, 10PbO-xSrO-(90-x)B2O3 (x is between 20 and 45 mol% with a step of 5 mol%) glasses with SrO inserted in various proportions were surveyed in terms of nuclear shielding qualities. Gamma- ray shielding features of the glasses encoded BPS1-BPS6 were investigated in the energy range of 0.015–15 MeV. The mass attenuation coefficients (MAC) of BPS glasses were composed via GEANT4 simulation codes and the accuracy of the outcomes was checked by WinXCOM software. The MAC values of BPS1 and BPS6 glasses were obtained between 14.934–0.024 g/cm2 and 19.047–0.029 g/cm2 in the energy range of 0.015–15 MeV. Further, other essential parameters, MFP, Zeff, Zeq, EABF, and EBF were derived from the MAC values for the same energies. It was noted that the MFP values of the BPS6 glass are higher than some commercial glasses and ordinary concrete at chosen energy intervals. According to the results achieved, EBF, EABF, and MFP values decline as the percentage of SrO in the BPS glasses increases. The highest Zeff was achieved by BPS6 (with 45% SrO), while the lowest Zeff was obtained by BPS1 (with 20% SrO). Finally, fast neutron removal cross-sections (ΣR), Mass Stopping Power (MSP), and Projected Range (PR) values were computed to investigate the fast neutron, proton and alpha shielding properties of SrO added BPS glasses. It is seen that the ΣR values of BPS glasses vary in the range of 0.126 cm−1–0.117 cm−1. The addition of SrO in the glass leads to reduce the ranges of charged and uncharged particles. According to the outcomes achieved, BPS6 glass with 45% SrO additives can be regarded as an effective radiation shield used in many technological disciplines. [ABSTRACT FROM AUTHOR]

Ionizing radiations are hazardous in the long run if exposed to a limit higher than the permissible limit (20 mSv/year). It can cause serious health issues like cancer, cardiac disease, cataract, damage to central nervous system, and other acute radiation syndromes. With an increase in the application of ionizing radiations in different fields like medicinal industries, therapeutic treatment, diagnostic imaging, food preservation, research centers, etc., the need for shielding material has also become crucial. Conventionally metallic lead, concrete, and the composite of lead with other heavy metals are used for radiation shielding. Although their shielding properties are quite good, they are either toxic, heavy, corrosive, or have weak thermal or mechanical stability. Therefore new radiation shielding materials obviating these drawbacks are in demand. Lead-free metal-polymer composites which are fabricated by incorporating high Z metal compounds in the polymer matrix are found to be a better alternative as radiation shielding materials, due to their light weight, flexibility, nontoxicity, noncorrosiveness, and good mechanical properties. This review article focuses on the studies carried out in the area of the development of polymer composite materials with a variety of high Z metal compounds and polymers for shielding ionizing radiations. The existing gap and future direction of work are also presented here. [ABSTRACT FROM AUTHOR]

Evaluation of the mechanical and shielding features is performed for glasses with the composition xBi2O3-(80-x) TeO2-10GeO2-10B2O3 with different concentrations x = 40, 50, 60, and 65 mol%. The mechanical parameters are summarized utilizing the Makishima-Mackenzie model. The elastic moduli such as Young, bulk, shear, and longitudinal are computed. The obtained results depict the elastic moduli affected by the replacement TeO2 with Bi2O3 content. The maximum values of elastic moduli are 61.822, 40.706, 24.790, and 73.761 for Young, bulk, shear, and longitudinal, respectively, of the inspected glasses utilizing the Monte Carlo simulation code (MCNP-5). The mass attenuation coefficient (μρ) and the half-value thickness (HVT) were also calculated. The shielding ability is tested by comparing the mean free path of the studied glasses with the commercial glasses. Likewise, the accumulation of photons inside the glass's material is determined using the BXCOM program. Finally, it can deduce the discussed fabricated glasses are suitable to apply in diverse applications of radiation protection. [ABSTRACT FROM AUTHOR]

The primary aim of this investigation is to synthesize a novel glass system with a composition (35+x) PbO-5TeO2-20Bi2O3-(20-x) MgO-20B2O3 (where x=0, 5, 10, 15, and 20 mol%) by melt quenching method. The confirmation of the amorphous behavior and the presence of the various vibration modes and stretching modes have been analyzed using the XRD and FTIR techniques, respectively. The radiation shielding parameters of these glasses were reported using MCNP5 simulation. The effects of PbO on the MCNP5 parameters were investigated in detail. The mass attenuation coefficient (MAC) was simulated via MCNP5 code, and it was found that the MAC values from MCNP5 all follow the same trend as the XCOM data. The similarity means that the two simulations strongly agree with each other. The linear attenuation coefficient (LAC) was calculated for all the glasses. The glass sample with 55 mol% of the PbO has the greatest LAC at any energy, such as 0.317 at 10 MeV, the lowest investigated energy. From the LAC values, other parameters such as transmission factor (TF), lead equivalent thickness (dlead), and half-value layer (HVL) were reported. The results for the TF of the glasses revealed that the glass systems become more effective as their thickness increases. Glass sample with 35 mol % of the PbO recorded the highest TF at all energies due to its lack of PbO content, such as 15.533% for a thickness of 1 cm and 6.122% for 1.5-cm thickness at 0.3 MeV. The radiation protection efficiency (RPE) was also determined, and we found that the glasses with the greater PbO content and least MgO content have the highest RPE. Therefore, based on the RPE values, glasses with the greater PbO are the most effective radiation shield from the investigated glasses. [ABSTRACT FROM AUTHOR]

Structural, thermal, radiation shielding efficiency, and buildup factors of the successfully synthesized (100-x) (0.5V2O5–0.5P2O5) (xB2O3): x = 0 (VPB0), 2 (VPB2), 4 (VPB4), 6 (VPB6), 8 (VPB8) mol % glasses have been investigated. Scanning electron microscope (SEM), EDX, Raman spectroscopy, and differential scanning calorimetry (DSC) thermograms measurements of the proposed glasses have been used to perform the mentioned aims. Indeed, radiation protection quantities like linear reduction (μ), and transmission factors (TF), radiation protection efficiency (RPE), and buildup factors (EBF and EABF) have been evaluated via Phy-X/PSD software. The SEM and EDX spectra measurements proved that the structure of the proposed glasses is amorphous. Raman spectroscopy revealed that in VPB8 glass structure, the different phosphate units were formed and thus (PO3)− groups decreased. Thermal stabilities varied between 168 °C (VPB0) and 199 °C (VPB4). The maximum values for the (μ) at 0.015 MeV, where they changed between 45.689 and 42.992 cm−1 for the investigated glasses VPB0–VPB8, respectively, and followed the trend: (μ)VPB0 > (μ)VPB2 > (μ) VPB4 > (μ)VPB6 > (μ)VPB8. The (TF) was linearly increased with the progressing of the photon energy, while the (RPE) has a totally opposite trend with the (TF). The values of the EBF and EABF increased with the increase in the B2O3 substitution ratio, where the lowest and highest buildup factors were obtained at 0 and 8 mol% B2O3 for VPB0 and VPB8, respectively. VPB8 is also found as an effective material to shield the fast neutrons, and its effective removal cross section (ERCSFN) ∑R is found equal 0.0324 (cm2 g−1). [ABSTRACT FROM AUTHOR]

The current paper studied the (95-y)P2O5–yBi2O3–5Nb2O5 glass systems where y = 10, 12.5, 15, and 17.5 mol% using EPICS2017 data library to understand the radiation shielding characteristics. The investigated glass systems, PNbBi1 to PNbBi4, were evaluated in terms of linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), and effective atomic numbers (Zeff) at the energy levels of 20, 40, 60, 80, and 100 keV. According to the theoretical computations, Bi2O3 ensured to improve LAC parameter in all photon energies; hence, PNbBi4 can be regarded as the best. Further, we reported that a nearly 14% increase in glass density leads to improve MAC parameters against ascending photon energies. PNbBi4 can be regarded as the lowest thickness ensuring sample at all photon energies amongst the other samples with respect to HVL and TVL parameters. Moreover, inserting Bi2O3 provided lower MFP thicknesses which in turn develops better radiation shielding characteristics. We found out that Zeff shows an increasing trend as the Bi2O3 increases, but displays a decreasing trend as the photon energy increases. Additionally, a comparison of shielding properties using the EpiXS and Phy-X/PSD has been evaluated. It was figured out that there is a good agreement observed between the results of each library. The results in most energies were found to be in good agreement with low (< 1%) relative differences. Overall, the authors concluded that the Bi2O3-reinforced PNb series can be utilized in X-ray shielding applications with satisfactory performance. [ABSTRACT FROM AUTHOR]

A sequence of Sm3+-incorporated calcium telluro-fluoroborate glasses by changing the modifier oxide was prepared via the melt-quenching method. The physical, structural, and gamma radiation shielding properties are investigated. XRD spectra confirmed the glassy state. The glasses' compactness was explored via the structural features like the boron-boron separation, oxygen molar volume, and oxygen packing density. Mechanical and optical properties such as Poisson's ratio, optical electronegativity, optical basicity, two-photon absorption (TPA) coefficient, and ionic and covalent characters were evaluated and discussed per modifier concentration. The photon attenuation attributes of the glasses were computed by means of the MCNP-5 code. The mass attenuation coefficient (MAC) was simulated in the energy region of 0.015–15 MeV. The highest MAC achieved at gamma energy 0.015 MeV increased from 25.004 to 33.165 cm2g−1 with increasing the CaO ratios between 0 and 40 wt%. Besides, several attenuation factors, such as the mean free path and the radiation protection efficiency, were evaluated connected with the MAC's simulated values. The study showed that the fabricated glasses' radiation protection efficiency at 0.5 MeV increased from 33.39 to 39.31, increasing the CaO content from 0 to 40 mol%. [ABSTRACT FROM AUTHOR]

This study explored the zinc-boro-vanadate (ZBV) glass reinforced with Ag2O to show radiation shielding competencies. A glass system with composition 20ZnO-55B2O3-(25-x)V2O5-xAg2O, where x ranges from 0 to 10 with the steps of 2.5 mol%, was designed. Some physical and optical calculations were employed to figure out glass density (ρglass), molar volume (Vm), oxygen molar volume (OMV), oxygen packing density (OPD), refractive index (n), dielectric constant (ϵ), and metalization criterion (M) for the glass system of ZBV0 to ZBV10. According to the findings, one can specify that the increasing content of Ag2O enhanced both the physical and optical features of the ZBV series. The glass density was increased from 3.3150 to 3.6930 g/cm3, while the refractive index was raised from 3.0693 to 3.1216 with the insertion ratio of Ag2O from 0 to 10 mol%. The ZBV10 sample having the maximum Ag2O of 10 mol% ensured to improve physical and optical properties. The shielding properties of the examined glass samples were investigated to evaluate their ability for radiation protection purposes. The Monte Carlo N-Particle Transport Code 5 (MCNP-5) was utilized to assess the projected gamma photons' average track length on the investigated glass samples. Then, the linear attenuation coefficient (LAC), half-value layer (HVL), transmission factor (TF), and radiation protection efficiency (RPE) were calculated based on the simulated gamma photons' average track length. The obtained results showed that the highest LAC values increased from 71.999 to 91.979 cm−1. Moreover, the thicker HVL decreased from 9.869 to 9.332 cm−1, increasing the Ag2O insertion ratio between 0 and 10 mol%, respectively. The mentioned data confirmed that substitution of the V2O5 by the Ag2O enhance the gamma-ray shielding capacity of the explored series of glass. [ABSTRACT FROM AUTHOR]

This study investigated lead concentrations in the hairs of radiographers working in the radiological departments of general hospitals that used lead shielding for radiation protection. We collected scalp hair samples from 32 radiographers working in four radiology departments with lead shielding and 18 administration personnel in the same hospitals without lead shielding. Samples were analyzed for lead concentrations by inductively coupled plasma mass spectrometry. As a result, lead concentrations in the hairs of the radiological technologists were significantly higher than those in the administration staffs (0.72 ± 0.51 vs. 0.19 ± 0.27 μg/g, P < 0.001). The hair lead concentrations were positively and significantly associated with environmental lead concentrations (r = 0.6, P = 0.001), but not associated with age, working duration, and gender distribution. [ABSTRACT FROM AUTHOR]

As an excellent tool, neutron generators have been used widely in prompt gamma-ray neutron activation analysis (PGNAA) technology. In this work, a new PGNAA laboratory was proposed to equip a D–T neutron generator. For safety reasons, radiation shielding of the laboratory was designed, and its protection efficiency was validated by using MCNP simulations and experiments. The results show that the proposed shielding can meet the radiation protection set by the International Commission on Radiological Protection and the Chinese government. [ABSTRACT FROM AUTHOR]

This paper investigates the radiation shielding properties, such as linear and mass attenuation coefficients, half and tenth value layers, effective atomic number and electron density, and radiation protection efficiency as a function of photon energy, of a new composite, PbI2-doped polyester. The mentioned polyester composite was prepared with different proportions of lead(II) iodide (5% increments between 5 and 20%) so that impact of the dopant amount on radiation shielding could be properly analyzed. The prepared composites were tested in 22 different energies in the energy range of 59.5–1408.0 keV with the use of HPGe detector and eight radioactive point sources. The obtained results were further validated by comparing the results of XCOM computer program, and negligible discrepancies were observed. It was observed that PbI2 (20%) composite is more effective gamma radiation shielding material than other produced composites. In light of this information, it can be said that the shielding efficiency increases with increasing lead(II) iodide amount. [ABSTRACT FROM AUTHOR]

In this paper, five barium borate glasses in the chemical composition of 40 SiO 2 – 10 B 2 O 3 –xBaO–(45-x)CaO–yZnO–zMgO (where x = 0 , 10 , 20 , 30 , and 35 mol y = z = 6 mol % ) have been reported for radiation protection applications. Mass attenuation coefficient ( μ / ρ ) was obtained in the photon energy range of 356 keV–2.51 MeV using PHITS code for the proposed glasses. The μ / ρ values generated by PHITS code were verified by using both of FLUKA code and XCOM program. The μ / ρ values were then applied to derive effective atomic number ( Z eff ), mean free path (MFP), and half value layer (HVL) for all the glasses involved. Additionally, the fast neutron removal cross sections were calculated for each glass. The results reveal that gamma-shielding properties evolve upon adding BaO content in the glasses. It is found that SBC-B35 glass has superior shielding capacity against gamma rays and fast neutrons as compared with different conventional shielding materials and commercial glasses. [ABSTRACT FROM AUTHOR]

This paper examines the utility of some newly developed tellurite-based glasses in the form of (100 - x - y) TeO 2 - x TiO 2 - y ZnO , where (x, y)=(5,10), (5,30), (10,10), (10,15), (15,5), and (15,10) mol % for potential use in radiation protection applications. Mass attenuation coefficient (μ / ρ) which is an essential parameter to study the radiation shielding properties was obtained for each proposed glass using GEANT4 toolkit for photon energies 1 keV–10 MeV. The simulation values were compared with the theoretical ones calculated by WinXCOM program. The obtained μ / ρ results were then utilized to calculate all the other important radiation shielding parameters such as mean free path, effective atomic number (Z eff) , and half-value layer for the glasses involved. Additionally, neutrons shielding properties in the terms of removal cross section were computed for each glass. The results reveal that the proposed glasses show the best shielding features against both gamma-ray and neutrons as compared with some commercial glasses, concretes, and HMO glasses. TeO 2 - TiO 2 - ZnO glasses would be useful for various radiation protection applications, especially those related to exposure control. [ABSTRACT FROM AUTHOR]

In this paper, we have reported 65 B 2 O 3 – 12.5 TeO 2 – 12.5 Bi 2 O 3 – 5 Na 2 O – 5 NdCl 3 and 67 TeO 2 – 20 WO 3 – 10 Li 2 O – 3 PrO 11 glasses to serve in radiation protection applications. Mass attenuation coefficient ( μ / ρ ) of the proposed glasses was obtained in the photon energy range of 0.015–15 MeV using GEANT4 Monte Carlo simulation. The simulation results were compared with those calculated by WinXCOM program. The correlation factor ( R 2 ) between the simulation and the theoretical values was found to be close to one referring to the high accuracy of the present results. Other essential radiation shielding parameters such as the effective atomic number ( Z eff ), half-value layer, and neutron removal cross section ( ∑ R ) were calculated for the proposed glass samples. Additionally, G-P method was used to generate exposure buildup factor and energy absorption buildup factor for each proposed glass in the photon energy range of 0.015–15 MeV up to penetration path of 40 mfp. Radiation shielding competence of our glasses was compared with conventional shielding materials, other rare earth glasses, and newly developed HMO glasses. The results reveal that our proposed glass coded as TWLP shows promising shielding competence against both gamma rays and neutrons. [ABSTRACT FROM AUTHOR]

In the present study five samples of special rubber-lead were fabricated each of them consists of lead and rubber with different weight ratios. The fabrication was carried out through the process of mixing under compression pressure. Gamma-ray transmission method was employed to determine the linear attenuation coefficient for narrow collimated mono-energetic beams of gamma-rays emitted from Am 0.059, Eu 0.13 and Cs 0.662 MeV. The linear attenuation coefficient of standard rubber-lead shield was also experimentally determined. The percentage of lead in standard rubber-lead shield was determined through the calibration curve or by a simple computer program written in MATLAB. All prepared samples are characterized as flexible and gives a good homogeneity. samples no. 4 & 5 offers the best performance as a radiation protection shields. The results showed an inverse proportionality between the linear attenuation coefficient μ, and μ has a direct proportionality with mixing ratios (sample density). The results showed an inverse proportional between the half value layers and the average linear attenuation coefficients of the various samples. [ABSTRACT FROM AUTHOR]

Glass gained much attention to be utilized in various applications, for this reason different kinds of glass compositions was the subject of investigation. In this work, we successfully fabricated a series of tellurite–germanate glasses with a composition of (70-x)TeO2–10GeO2–10ZnO–10Li2O–xBi2O3, where x = 0, 5, 10 and 15 (all in mol%). Ordinary melt-quenching was used to synthesize the mentioned glass series with 975 °C as a melting temperature for 30 min and 300 °C for annealing to release the internal stress. To study the structural properties of these glasses, X-ray diffraction (XRD) was used to confirm the glassy structure of these glasses. Regarding that, XRD profiles were recorded in ranges between 10° and 80° for all samples. Moreover, FTIR was employed to study the functional groups of all elements, which were used in the composition with the range of 4000–400 cm−1. Optical absorption was used to investigate the cutoff wavelength and optical band gap. Optical absorption was measured at the range of 200–800 nm. The variation of the attenuation properties for the tested tellurite–germanate glasses has been investigated using WinXcom software for photon energy ranges between 0.015 and 15 MeV. The examined attenuation properties include linear and mass attenuation coefficients, half value layer and mean free path, and effective atomic number of the radiation shielding glass. The present results suggest the utilization of the new prepared glass samples in radiation shielding applications. [ABSTRACT FROM AUTHOR]