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Near-zero magnetic shielding systems (MSSs) can provide basic experimental environments for extremely weak magnetic measurements. Reducing the internal magnetic field of MSS is the crucial element of high-sensitivity measurements, which is related to the shielding material flux. As an effective way to regulate the material remanence, degaussing reconstructs the magnetic balance with the geomagnetic field. However, previous research studies mainly focused on the optimization of material degaussing, with few considering the practical application scenarios of MSS. In this work, a numerical modeling method is proposed to realistically depict the balancing process, and the mapping relationship between the internal magnetic field of the MSS and the degaussing current is established. First, the magnetic field source analysis is carried out, and the internal magnetic field fluctuations of the MSS during degaussing are decomposed into multi-harmonic components. Then, the phase and amplitude changes of the hysteresis loop are simulated to predict the residual field. Thereafter, the effectiveness of the method is verified by a magnetic shielding cylinder. The experimental results indicate that the slight difference in material remanence has a negligible effect on the residual field. This work has potential application value in the research of degaussing technology. [ABSTRACT FROM AUTHOR]

The topology of the applied magnetic field is an important design aspect of Hall thrusters. For modern Hall thrusters, the magnetic field topology most often features curved lines with a concave (negative) curvature upstream of the field's peak and a convex (positive) curvature downstream. Additionally, the advent of the magnetic shielding technique has resulted in Hall thruster designs with non-conventional field topologies that exhibit high degrees of concavity upstream of the field's peak. In this article, a detailed study is carried out on the effects that the magnetic field curvature has on the plasma discharge in a 2D configuration representative of a Hall thruster's radial–azimuthal cross section. The analyses are performed for discharges of three propellants of high applied interest: xenon, krypton, and argon. For each propellant, high-fidelity electrostatic reduced-order particle-in-cell (PIC) simulations are performed with various degrees of positive and negative curvatures of the magnetic field. Corresponding 1D radial PIC simulations are also performed for xenon to compare the observations against the 2D results. Most notably, it is observed that the instability spectra in the positive-curvature cases are mostly dominated by electron cyclotron drift instability, whereas the modified two stream instability is dominant in the negative-curvature cases. The distributions of electron and ion temperatures, in particular, as well as the contribution of various mechanisms to electrons' cross-field transport show notable variations between the positive and negative curvature values. Finally, the field curvature is observed to majorly influence the ion beam divergence along the radial and azimuthal coordinates. [ABSTRACT FROM AUTHOR]

Scientists devote their time and energy to studying and developing hydrogen storage devices to address the energy crisis and climate change. Because of this, investigations are conducted to reveal the optoelectronic, structural, bader charge, electronic charge density, and hydrogen storage properties of X 2 LiAlH 6 (X = K, Mn) within the framework of density functional theory, and calculations of the structural characteristics were carried out utilizing local and nonlocal, and hybrid functionals. An additional onsite Coulomb parameter (GGA + U), which includes the Hubbard parameter, was used to apply the potential. Calculations based on the Kramer-Kroning principle were used to determine the dielectric function, refractive index, extinction coefficient, and energy loss function. The results indicate that K 2 LiAlH 6 and Mn 2 LiAlH 6 are highly suitable for hydrogen storage applications. The gravimetric ratios of hydrogen storage capacities for both investigated materials are 5.2 wt %, and 7.5 wt %, respectively. The interaction of the Mn-d, Li-s, K-s, and H-s/p orbitals was the cause of hybridization, according to the optoelectronic characteristics. Compound stability is indicated by the negative computed formation energy of the materials under investigation. The electronic charge density analysis showed a mixed-bond semiconductor with low ionicity and high covalence. In addition, the radiation shielding properties of Mn 2 LiAlH 6 and K 2 LiAlH 6 were investigated using Phy-X software, showing promising results in linear attenuation, half-value layer, and mean free path, particularly for Mn 2 LiAlH 6 due to its higher atomic number. This groundbreaking study represents a pioneering computational exploration of X 2 LiAlH 6 , offering promising advancements for future research in hydrogen storage applications. • The structural properties of X 2 LiAlH 6 were analyzed using DFT, revealing promising stability metrics. • Mn 2 LiAlH 6 shows enhanced radiation shielding due to its higher atomic number and interaction effects. • Hydrogen storage capacity for K 2 LiAlH 6 and Mn2LiAlH6 was calculated to be 5.2 wt % and 4.7 wt %, respectively. • Phy-X software simulations revealed Mn 2 LiAlH 6 's superior shielding performance against gamma rays. • Optical properties demonstrated high absorption coefficients, indicating potential for energy applications. [ABSTRACT FROM AUTHOR]

This study presents a detailed investigation into the structural, thermal, and radiation shielding properties of a new glass composition, labeled as (50-x)B 2 O 3 + 30TeO 2 + 10Bi 2 O 3 + 10CdO + x Tm 2 O 3 (where x = 0, 1, 2, 3, 4, 5 mol %). Various radiation shielding parameters such as mass attenuation coefficient, linear attenuation coefficient, half-value layer, mean free path, effective atomic number, and absorbed equivalent dose rates for neutrons were determined through experimental measurements. The study also employed theoretical calculations to assess the exposure buildup factor and effective removal cross-section for neutrons. Additionally, the SRIM program was utilized to investigate mass stopping power and projected range for proton and alpha particles. The structural characteristics of the glasses were analyzed using XRD and FT-IR, while thermal properties were examined through Differential Thermal Analysis (DTA). FTIR analysis revealed distinctive bands corresponding to Bi—O, B—O—B, and Te—O bonds. Glass transition temperatures (T g) increased with Tm 2 O 3 content, ranging from 422 °C to 444 °C. The radiation shielding properties of bismuth boro-tellurite glasses showed that a dose of 1.2025 μSv/h emitted from a fast neutron source was absorbed by 35.1574 % in pure glass and 40.0391 % in glass doped with 5 mol% Tm 2 O 3. Incorporating Tm 2 O 3 into the glass matrix significantly improved the shielding and thermal properties, thus enhancing their potential for advanced high-energy radiation absorption. This investigation contributes to a deeper understanding of how Tm 2 O 3 enhances the structural and thermal attributes of these glasses, positioning them as promising materials for radiation shielding applications. [ABSTRACT FROM AUTHOR]

The aim of the present study is to assess the shielding performance of a novel lead-free epoxide material against ionizing radiation. The effect of variation in particle size and concentration of tin oxide (SnO), which was added to epoxy resin polymer (ER), on its radiation shielding properties has been investigated in this research. Ten samples of ER samples incorporated with different concentrations (0%,20%,40%,60%) of SnO microparticles, nanoparticles, and both sizes combined were prepared and assessed. The linear attenuation coefficients (LAC) were measured experimentally through the collimated gamma-ray beam at 0.0595 MeV, 0.6617 MeV, 1.1730 MeV, and 1.330 MeV emitted from Am-241, Cs-137 and Co-60, respectively (to cover all energy range of gamma rays) for all samples with various concentrations and particle sizes of SnO. The other radiological shielding parameters such as half value layer (HVL), tenth value layer (TVL), and radiation protection efficiency (RPE) were estimated and compared for all different samples. The results prove that the increasing of the concentration and reducing the particle size of SnO leads to the enhancement of the radiation protection properties of the ER polymer. Moreover, it was observed that the incorporation of SnO micro- and nanoparticles together improves the radiation shielding properties of ER samples. Conclusively, the reinforcing of ER polymer material matrix by micro/nanoparticles of SnO as composite with enhanced radiation shielding specifications was highlighted. [ABSTRACT FROM AUTHOR]

In this investigation, a group of different concentrations of molybdenum trioxide-doped borate-germanate-telluride glasses have been synthesized. Four glasses with a composition formula of (35-x) B 2 O 3 -20TeO 2 -10GeO 2 -35MgO-xMoO 3 where x values vary between 5 and 20 mol % have been achieved using the melt-annealing process. X-ray diffraction for the current M1 sample was utilized to prove the glassy nature. FTIR has been measured to understand the glass structure. Many functional group and vibrational bonds were observed. The optical parameters for B 2 O 3 -TeO 2 -GeO 2 -MgO-MoO 3 glass samples were calculated based on absorption spectra recorded in the 200–1100 nm wavelength range. The optical electronegativity (χ) and optical basicity (Λ) were calculated as critical parameters that can be used to evaluate the glass structure. Physical parameters like density, molar volume (V m), packing density (V t), oxygen packing density (OPD), and oxygen molar volume (OMV) were measured and calculated. Hardness (H), Poisson ratio (σ), Fractal bond conductivity (d), and elastic moduli of M1, M2, M3, and M4 glass samples were calculated. Mass attenuation coefficients (MAC) for four synthesized glass samples were reported along with linear attenuation coefficient (LAC) as a function of photon energy. Based on the transmission factor TF %, it shows extremely low percentages at the lowest energy region, dropping to less than 1 % at 0.015 MeV up to 0.08 MeV in all samples. The radiation protection efficiency (RPE) was examined to measure the samples' capacity to attenuate ionizing radiation. [ABSTRACT FROM AUTHOR]

The aqueous solution cast method was used to create the biodegradable polymer nanocomposite (PNC) films from a blend of poly (vinyl alcohol) PVA and poly (vinyl pyrrolidone) PVP (70/30 wt %) and Fe2O3 nanoparticles (NPs). These PNC films were characterized using X-ray diffraction, scanning electron microscopy SEM, Fourier transform infrared spectroscopy FTIR, and ultraviolet-visible spectroscopy. XRD and FTIR results indicate that Fe+ 3 NPs interact with the host polymer. Optical, electrical, mechanical, and radiation shielding measurements were performed on the PNC films. From the optical measurements, the indirect optical band gap drops from 4.86 eV for the pure blend to 4.26 eV at the greatest NPs concentration. Optical limiting characterization shows that the output power of He-Ne and solid-state green laser beams is reduced from 22.98 to 3.6 mW and 6.59 to 1.4 mW, respectively, when the Fe2O3 NPs content in the blend matrix is increased to 6 wt %. The NGCal software was utilized to calculate nuclear radiation shielding properties. The findings demonstrated that when the concentration of Fe2O3 rose, the PNC films half-value layer and mean free path decreased. Mechanical measurements demonstrate that increasing the Fe2O3 content significantly improves nanocomposite films' yield and tensile strength. Tensile strength is measured at 27.03 MPa for the composite film containing 6 wt % Fe2O3, which is significantly higher than the 8.66 MPa of the pure (PVA-PVP) film. Compared to the other samples under examination, the 6 wt % Fe2O3 sample yielded the best results (based on the analyzed optical, electrical, mechanical, and radiation shielding properties). [ABSTRACT FROM AUTHOR]

Radiation shielding glass is an interesting material in the field of radiation shielding due to its remarkable features. In the present paper, we investigated the physical properties of radiation-shielding glass materials that consist of sodium oxide (Na 2 O), cerium oxide (CeO 2), and iron oxide (Fe 2 O 3) incorporated into borosilicate glasses with the formula 90SiO 2 -(70-x)B 2 O 3 + 20Na 2 O–1Fe 2 O 3 -xCeO 2 (CeFeNaBS-glasses). One of the distinguishing characteristics of this glass system is its enhanced radiation shielding capabilities. The structural studies indicated a gradual rise in glass density from 1.954 to 2.658 g/cm with further CeO 2 doping. Optical studies showed that the optical band gaps went down from 3.41 eV to 3.33 eV as the amount of CeO 2 in the CeFeNaBS-glass matrix rose. The decrease in optical band gap has been correlated with the rising basicity. Also, the increased basicity behavior induces more conversion of Ce3+ to Ce4+ ions by losing a 4f electron. Moreover, with further CeO 2 additions, the glass color changed from light brown to dark brown. The presence of Ce4+ ions with further CeO 2 additions is responsible for this color transformation. The linear and non-linear refractive indices exhibit enhanced behaviors with higher CeO 2 concentrations. We used declining basicity and polarizability behaviors to describe this behavior. The incorporation of larger CeO 2 concentrations enhances the ability to improve radiation shielding properties, as demonstrated by the increased values of the mass attenuation coefficient and half-value layer, especially in the energy ranges of soft tissues X-ray and hard tissues X-ray. Hence, the investigated CeFeNaBS-glasses exhibit enhanced transparency and radiation shielding capabilities, rendering them highly suitable for implementation in this domain. [ABSTRACT FROM AUTHOR]

This study investigates the effect of La³⁺ rare earth ions on the structural, elastic, optical, and radiation shielding features of heavy metal borate glass (B₂O₃-PbO) doped with Cr₂O₃. Density measurements and FT-IR spectra analysis revealed the role of La3+ ions as a network modifier, where successive additions of La 2 O 3 content led to a gradual increase in the density and an increase in the non-bridging oxygen content resulting from the structural transformation between the BO 4 and BO 3 units. The significant improvement in the elastic modulus and microhardness factor moduli was confirmed by calculating the change in ultrasonic velocities through the glassy system. The structural modifications induced by La³⁺ ions narrowed the band gap and increased the Urbach energy, indicating higher disorder within the glass network. The linear refractive indices increased due to increased optical basicity and electronic polarization. Optical absorption results showed that Cr⁶⁺/Cr³⁺ ions occupy octahedral/tetrahedral sites, with the tendency for Cr³⁺ cations to occupy more octahedral sites with increasing La₂O₃ content. The produced samples showed a greenish-yellow color caused by the absorption band centered at ∼415 nm associated with the electronic transition ⁴A₂g(F)→2Eg(G). The ligand field effect highlighted the significance of La³⁺ cations in increasing the crystalline field intensity surrounding Cr³⁺ cations and reducing the nephelauxetic ratio, signifying enhanced covalent character between Cr³⁺ cations and neighboring ions. Moreover, the radiation shielding capabilities of the glassy system were analyzed and compared with standard shielding materials, confirming superior shielding performance in samples with the highest La₂O₃ content. [ABSTRACT FROM AUTHOR]

In radiation therapy, various radioprotective materials protect normal cells from the damage produced by ionizing radiation. Plant-based chemical compounds possess antioxidant properties and can scavenge free radicals produced by nuclear radiation. Determining radiation shielding parameters and understanding how nuclear radiation interacts with plant-based radioprotectors are crucial for choosing the optimal plant-based radioprotectors. In the present work, the interaction of gamma, neutron, electron, proton, and alpha particles with plant-based radioprotectives such as ferulic acid, genistein, hesperidin, lycopene, psoralidin, sesamol, troxerutin, vanillin, and zingerone has been studied. The interaction parameters such as MAC, Zeff, EBF, and EABF for gamma energy, MAF for thermal and fast neutrons, and MSP for electrons, protons, and alpha have been calculated for the plant-based radioprotectors using the software EpiXs, PyMLBUF, NGCal, ESTAR, PSTAR, and ASTAR. Results show that genistein and lycopene show high and low effective atomic numbers in the higher energy region of gamma photons, respectively. The neutron mass attenuation factor is found to be highest for lycopene and lowest for genistein for both thermal and fast neutrons. Among the selected plant-derived radioprotectives, troxerutin and lycopene are the most effective plant-based compounds for gamma and neutron radiation therapy applications. The shielding parameters of selected plant-based radioprotector materials are compared with those of some chemical radioprotectors. Besides, the shielding parameters of selected plant-based radioprotector materials are comparable to chemical radioprotectors except for lycopene. [ABSTRACT FROM AUTHOR]

A five pressured diatomite clay materials samples were produced as a mixture of diatomaceous earth mineral and sodium silicate for the purpose of this investigation. The forming pressures ranged from 22.84 MPa to 114.24 MPa, and the samples were formed under a variety of conditions. The ratio of Na2SiO3 to the total mass of the produced pressed samples was maintained at precisely 15 wt.% throughout the process. Through the process of increasing the forming pressure, the density of the pressed samples was increased by ~ 11%. For the purpose of determining how the forming pressure will affect the shielding capacity, the Monte Carlo simulation was applied. The linear attenuation of the fabricated pressed diatomite samples improves from 0.123 to 0.136 cm−1 when the forming pressure is increased from 22.84 MPa to 114.24 MPa. By increasing the pressure from 22.84 MPa to 114.24 MPa, the half-value thickness reduced from 5.63 cm to 5.09 cm, and the thickness equivalent = 1 cm of pure Pb metal decreased from 10.09 cm to 9.12 cm. It was found that elevating the forming pressure resulted in an augmentation of the fast neutron removal for the artificially manufactured pressed diatomite samples. [ABSTRACT FROM AUTHOR]

CubeSat and small satellites play a very important role in modern space exploration. Their success and diverse capabilities rely on the development of efficient and compact sub‐systems. This task is not trivial due to multiple challenges posed by their small size and mass, and the solution calls for conceptually new designs for the fabrication and integration of complex miniaturized satellite components. The importance of additive techniques in small satellite manufacturing is steadily increasing as they enable rapid, large‐scale production of sophisticated architectures, such as hollow, webbed parts with a cell‐like structure similar to animal bone, with lower mass and improved functionality. Moreover, these architectures feature higher strength, enhanced heat transfer, and efficient thermal and electromagnetic radiation shielding. When compared to traditional subtractive technologies like cutting and milling, additive manufacturing proves to be more versatile and effective in realizing architectures with an increasing intricacy of shapes, structures, and compositions. The perspective explores the suitability of 3D printing in various satellite production tasks, including the propulsion system components and satellite elements. Looking ahead, the challenges and advantages of integrating 3D printing technology into satellite production, emphasizing the need for continuous development through consolidated, proactive collaborative efforts of many devoted teams are outlined. [ABSTRACT FROM AUTHOR]

The influence of changing the concentrations of ZnO and TiO 2 on the (90-x-y)B 2 O 3 –5PbO–5BaO-xZnO-yTiO 2 , x = y = 10, 15, 20 and 25 mol% glasses have been investigated. Their density rises from 3.469 g/cm³ to 4.207 g/cm³. The elastic modulus of the glass samples increased from 50.970 to 73.195 GPa for Young modulus, 45.540–64.107 GPa for bulk modulus, 20.640–29.732 GPa for the shear modulus and 73.060–103.750 GPa for the longitudinal modulus respectively. This is referring to the effect of ZnO and TiO 2 on the structure of the glasses. The UV–Vis absorption behavior exhibits a decrease in the energy band gap values from 3.312 to 3.146 eV. The increase in cutoff wavelength in UV spectra is useful for many applications, such as UV shielding, where the objective is to effectively obstruct UV rays while preserving optimal visibility. The relation between the thickness of the glass and the transmission factor (TF) has been studied to evaluate their shielding behavior. The TF decreases with the increase in the thickness from 0.5 to 1 cm. Also, TF decreases with the addition of ZnO within the structure of the investigated samples. Therefore, it can be suggested that increasing the concentration of ZnO in glass samples is another good way to reduce TF values. [ABSTRACT FROM AUTHOR]

The transport of fission products in molten salt reactors has attracted much attention. However, few codes can completely describe the transport characteristic, though the migration of fission products in the molten salt reactor is essential to estimate the source term, decay heat, and radiation shielding. This study built a program named ThorFPMC (Thorium Fission Products Migration Code) that can handle the multi-physics transport characteristic based on the flow burnup code ThorMODEc (Thorium MOlten Salt Reactor Specific DEpletion Code). A problem-related depletion chain compression method was applied to decrease the order of the solve matrix. The matrix exponential and splitting methods were applied to solve the steady state and transient calculation, respectively. Error analysis showed that for a specific problem, the simplified depletion chain matrix index method could solve the fission products migration equation with an arbitrary time-step with high speed (s) and high precision (10−4); the splitting method could reach a precision of 10−2 level for the full fuel depletion chain, multi-nodes, and transient problems. Compared to the Strang splitting method, the perturbation splitting method has higher precision and less time consumption. In summary, the developed programmer could describe the migration effect of fission products in molten salt reactors, which provides a significant tool for the design of molten salt reactors. [ABSTRACT FROM AUTHOR]

The nuclear radiation shielding materials are having a great importance in reactor shielding, nuclear laboratories, radiation sources storage, as well as in space radiation shielding. The experimental methods are time consuming, facility dependent, as well as costly affair in order to manufacture the shielding materials. The alternative approach is to use nuclear transport codes such as GEANT, MCNP, PHITS, FLUKA for nuclear radiation shielding application. The present work is planned to study the prediction capabilities of transport code for calculation of shielding parameters using two different radiation transport codes and comparison with experimental results. The simulation measurements were carried out by Monte Carlo analysis, 241Am–Be neutron source & neutron dosimeter, and High Density Polyethylene (HDPE) were modeled using MCNP 6 and PHITS 3.22 codes. Subsequently, experimental neutron dose rates were measured after different thickness of HDPE samples using live 241Am–Be neutron source and NRF31 dosimeter. The study shows a good agreement between the experimental and simulated results which suggest that the simulation method can be used for the optimization of new shielding composites. [ABSTRACT FROM AUTHOR]

Heavy-weight concrete (HWC) is a widely adopted radiation shielding material in the nuclear industry. In this study, two kinds of high-density aggregate, namely, iron sand (IS) and steel slag coarse aggregate (SSCA), were adopted to fully replace river sand and natural coarse aggregate, respectively, producing ultra-heavy-weight concrete (UHWC) with a unit weight >3800 kg/m3, to ensure excellent radiation shielding performance. However, IS and SSCA seriously impaired the passing ability of UHWC as the cement paste could not hold the IS and SSCA as firmly as natural aggregates, owing to their high density. To overcome this, the rheology of UHWC should be optimised by partially replacing the cement with superfine silica fume (SSF) and using a suitable amount of superplasticiser (SP) to enhance the wet packing density (WPD). A total of 28 UHWC mixes with different replacement ratios of SSF and different SP dosages were tested for segregation width, flowability, L-box passing ability, unit weight and WPD. Results revealed that incorporating an appropriate quantity of SSF and SP improved the WPD of UHWC, resulting in improved segregation resistance, enhanced flowability, increased passing ability and a higher unit weight. Lastly, there is a positive correlation between flowability, passing ability and WPD. [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]

This study explores the structural, radiation, and optical properties of cyclosilicates minerals (CMs), providing comprehensive analyses of molar volumes, densities, band gap values, and effective atomic numbers. The structural properties were found to be dependent on the correlations with the interatomic interactions derived from the analysis of Hirshfeld topological surfaces (HTSs) and their voids. In examining a broad energy spectrum from 0.015 to 15 MeV, the study focuses on mass attenuation coefficient (MAC) and linear mass attenuation coefficient (LAC). Results show that MAC values are the highest for the BaTi(SiO3)3 crystal, highlighting its superior γ‐ray attenuation capabilities among other CMs. The study finds that Hirshfeld volume, and surface ranged between 344.21 and 2640.98 Å3 and 388.91 and 1326.97 Å2, reveals distinct electron density distribution characteristics in CM materials. The study probes the impact of HTSs on structural (113 < Vm < 686 cm3/mol), optical (1.95 < n < 2.38), and radiation shielding (13.0 < LAC < 102.0 1/cm at E = 15.0 keV) values, demonstrating that altering the O...A (A = atom in the CM crystal) interactions align with the charge density, potentially tuning other physical values. [ABSTRACT FROM AUTHOR]

The continuous development of ionizing radiation in medical imaging and treatment, nuclear reactors, food irradiation, and other fields is accompanied by potential risks. It protects related equipment and personnel by adopting radiation shielding materials to reduce irradiation. Due to the advancement of science and technology, many high‐performance radiation protection materials have been reported. Ionizing radiation is a complex environment involving X‐ray imaging, radiation therapy, nuclear power operation, and space radiation. Irradiation energy, irradiation type, and the measurement of shielding material have essential effects on shielding efficiency. However, there has not been a general review of the preparations and properties of ionizing radiation shielding materials in the light of different matrixes in recent years. Herein, a comprehensive overview of recent advancements in radiation shielding materials, categorized into alloys, concretes, glasses and ceramics, and polymer composites, is presented. Furthermore, the synthesis methods employed for these materials and their respective radiation shielding properties are discussed. Finally, the current research gap and possible future scope of radiation shielding materials are proposed. [ABSTRACT FROM AUTHOR]

We study radiative transfer in participating binary stochastic mixtures in two dimensions (2D) by developing an accurate and efficient simulation tool. For two different sets of physical parameters, 2D benchmark results are presented, and it is found that the influence of the stochastic mixture on radiative transfer is clearly parameter-dependent. Our results confirm that previous multidimensional results obtained in different studies are basically consistent, which is interpreted in terms of the relationship between the photon mean free path lp and the system size L. Nonlinear effects, including those due to scattering and radiation–material coupling, are also discussed. To further understand the particle size effect, we employ a dimensionless parameter lp/L, from which a critical particle size can be derived. On the basis of further 2D simulations, we find that an inhomogeneous mix is obtained for lp/L > 0.1. Furthermore, 2D material temperature distributions reveal that self-shielding and particle–particle shielding of radiation occur, and are enhanced when lp/L is increased. Our work is expected to provide benchmark results to verify proposed homogenized models and/or other codes for stochastic radiative transfer in realistic physical scenarios. [ABSTRACT FROM AUTHOR]

Many oxide additives have historically been used to enhance the radiation shielding properties of glasses, yet the potential of high-entropy oxides (HEOs), which have gained popularity in material science for their unique properties, has not been explored in this context. This study is the first to investigate the radiation shielding capabilities of Zinc-Tellurite glass infused with High Entropy Oxide (HEO), specifically utilizing the novel attributes of a synthesized TiZrNbHfTa. In this study, the nuclear shielding properties of newly fabricated Zinc-Tellurite glasses doped with TiZrNbHfTaO x with a composition (25ZnO·75TeO 2)100-x. (TiZrNbHfTaO x)x (x = 0, 1, 2, 3, 4 mol%) were studied. Through the synthesis of a TiZrNbHfTa HEA and its integration into glass structure, we have developed a series of novel materials with enhanced protective properties against both gamma-ray and neutron radiation. Experimental results demonstrate that the HEO-infused glass, particularly the HEC1-4 composition, significantly surpasses traditional shielding materials in neutron attenuation, evidenced by its superior effective neutron removal cross-section. Additionally, the HEC1-4 glass demonstrates improved gamma-ray shielding capabilities, with increased mass attenuation coefficients and decreased half-value layers, indicating a higher capacity for photon interaction and absorption. It can be concluded that the incorporation of High Entropy Alloys into glass matrices not only opens a new frontier in radiation shielding materials but also provides a versatile and effective solution with considerable potential for enhancing safety measures in radiation-prone environments. [ABSTRACT FROM AUTHOR]

A novel glass system was developed using the melt-quenching technique. The primary aim was to investigate molybdenum-rich compositions (MoO 3 > Li 2 O), with the general formula (69–2x) TeO 2 –(31+x)–MoO 3 –xLi 2 O (where x = 0, 5, 10, and 15 mol%). The physical, structural, thermal, mechanical and radiation shielding properties were evaluated. The synthesized glasses were characterized through their densities, molar volumes, and oxygen packing density, which revealed that the density and molar volume decreased as the amount of Li 2 O and MoO 3 increased in the glass structure, while the oxygen packing density increased as a function of both Li 2 O and MoO 3. Raman spectroscopy was used to analyze the glass structure, which showed a superimposed reduction of all Te units due to the formation of Te–O–Mo and a coordination change from MoO 4 to MoO 6. The interplay between Li 2 O and MoO 3 has a direct effect on the thermal stability of the glass and reveals that glasses with higher MoO 3 content and lower Li 2 O content exhibit enhanced thermal stability. The mass attenuation coefficient for the synthesized systems varied from 37.07 to 32.38 cm2 g−1 at 0.015 MeV. The fast neutrons removal cross-section exhibits a range from 0.090 to 0.096 cm−1 across all samples, while the thermal neutrons cross section values lie within the interval of 1.22–8.16 cm−1. The glass sample with the highest concentration of TeO 2 showed superior values of mass attenuation, and fast neutrons removal cross-section, along with the lowest values of half value layer and mean free path. Nevertheless, the addition of MoO 3 and Li 2 O improved thermal stability and led to adequate radiation protection levels. The results indicate the significant potential of MoO 3 -rich tellurite materials for shielding against gamma-ray and neutron radiation. [ABSTRACT FROM AUTHOR]

AbstractIn the present investigation, the gamma and neutron shielding parameters of nano Pb2O3 incorporated into cement in proportions ranging from 0 to 5 wt% were determined using EpiXS and NGCal software. It was observed that the mass attenuation coefficient decreased with increasing photon energy. The introduction of higher concentrations of nano Pb2O3 into the cement resulted in a marked increase in the Pb K-edge. Cement samples enhanced with Pb2O3 content exhibited a pronounced peak in the effective atomic number in the lower energy regions. The exposure buildup factor showed a decrease in its value with increasing Pb2O3 content. Among the compositions used, pure cement with no Pb2O3 addition demonstrated a superior mass attenuation factor for both thermal and fast neutrons. A blend of 95% cement with 5% Pb2O3 emerged as the most effective gamma-ray shielding material within the tested energy range. A comparative analysis of this mix with other concrete types was conducted to evaluate its effectiveness as a shielding material. The findings suggest that this composition could benefit medical imaging and radiation therapy facilities. [ABSTRACT FROM AUTHOR]

Lead borate glass is the best radiation shielding glass when lead is in high concentration. However, it has low transparency after radiation exposure. Radiation decreases transparency due to chemical and physical changes in the glass matrix, such as creating or healing defects in the glass network. The addition of rare earth elements like cerium and dysprosium oxides to lead borate glasses can improve their transparency and durability as radiation shielding barriers. The newly manufactured glasses' optical absorption, structural, and radiation shielding properties were measured. The optical characteristics of the generated samples were examined to determine the effect of the cerium/dysprosium ratio on the structural alterations, specifically in the presence of bridging oxygen (BO) and non-bridging oxygen (NBO). Incorporating Ce3+ results in peaks at 195 nm for borate units, 225 nm for Ce3+, and a broadened peak at 393 nm due to overlapping peaks for Ce3+ and Ce4+ in the UV region. By adding Dy, multiple peaks are observed at 825, 902, 1095, 1275, and 1684 nm, corresponding to the transition from 6H15/2 ground state to 6F5/2, 6F7/2, 6F9/2, 6F11/2, and 6H11/2. The samples were also tested before and after exposure to gamma irradiation from a 60Co source at a dose of 75 kGy to assess their stability against radiation. The energy gap value during irradiation shows decreased non-bridging oxygen. The energy gap difference before and after irradiation for the M4 sample shows higher NBO to BO conversion, reducing radiation damage and improving structural stability. Furthermore, X-ray photoelectron spectroscopy was utilized to get insight into the coordination chemistry of the created glass samples. The half-value layer (HVL), radiation protection efficiency (RPE), neutron removal cross-section (FRNCS), mean free path (MFP), mass attenuation coefficients (MAC), and effective atomic numbers (Zef) of the glassy structure were calculated theoretically to assess its radiation shielding qualities. The linear attenuation coefficient order for the prepared samples was M1 > M2 > M3 > M4. The FRNCS values were 0.090, 0.083, 0.081, and 0.079 cm−1 for samples M1, M2, M3, and M4, respectively. [ABSTRACT FROM AUTHOR]

There are various types of charged particles in the space environment, which can cause different types of radiation damage to materials and devices, leading to on-orbit failures and even accidents for spacecraft. Developing lightweight and efficient radiation-shielding materials is an effective approach to improving the inherent protection of spacecraft. The protective performance of different materials against proton and electron spectra in the Earth's radiation belts is evaluated using a Geant4 simulation. Based on the simulation results, suitable hardening components were selected to design composite materials, and B4C/PEEK composites with different B4C contents were successfully prepared. The experimental results demonstrate that the simulated and experimental results for the electron, proton and neutron shielding performance of the B4C/PEEK composites are consistent. These composites exhibit excellent radiation shielding capabilities against electrons, protons and neutrons, and the radiation protection performance improves with increasing B4C content in the B4C/PEEK composite materials. [ABSTRACT FROM AUTHOR]

This review paper provides a comprehensive analysis of radiation shielding concrete, covering its properties, design, evaluation, and applications. It begins with an introduction, stating the objective and scope. The paper explores radiation shielding basics, including ionizing radiation, shielding principles, and materials used for shielding. Concrete's properties relevant to shielding, radiation attenuation mechanisms, and factors affecting its efficiency are discussed. Different types of radiation shielding concrete are examined, along with their applications. The design and formulation of shielding concrete, including mix proportions, optimization techniques, and quality control, are presented. Evaluation methods and standards are discussed. Lastly, challenges, future directions, and emerging technologies are outlined. This review paper serves as a valuable resource for professionals involved in radiation shielding. The review on radiation shielding concrete highlighted its effectiveness in attenuating ionizing radiation, emphasizing material composition, density, and thickness as key design factors. Evaluation methods, such as gamma spectroscopy and Monte Carlo simulations, are discussed, demonstrating its versatile applications in nuclear facilities, healthcare, and space exploration. [ABSTRACT FROM AUTHOR]

The design and preparation of lightweight and flexible electromagnetic interference (EMI) shielding composites with high efficiency and low reflection are critical to the electronic field. First, silver nanowires (AgNWs) were vacuum filtered on the electrospun thermoplastic polyurethane (TPU) fibrous film. Then, by combining the adhesive with the electrospun silicon carbide nanowhisker (SiCnw) @TPU composite fibrous film, the asymmetric EMI shielding composite films with high electromagnetic shielding efficiency (EMI SE) and low incident power were obtained. The lower AgNWs‐TPU layer provides the primary EMI SE, and the upper SiCnw@TPU fibrous film is used for electromagnetic wave absorption. This unique asymmetric structure, the synergistic effect of SiCnw's particular absorbing function and the excellent conductivity of the AgNWs layer make the film show high overall SE (SET = 55.18 dB). In order to improve the absorption effect of the composite film, the number of layers of SiCnw@TPU was adjusted, resulting in a final reflection coefficient value as low as 0.55. This work proposes a new strategy for developing EMI shielding composite films with high efficiency and low reflection, serving as a reference. [ABSTRACT FROM AUTHOR]

Background Purpose Methods Results Conclusion Radiography is one of the most widely used x‐ray imaging modalities. In National Council on Radiation Protection and Measurements (NCRP) Report No. 147, transmission data for radiographic systems were evaluated on those installed before 2000. For x‐ray systems (except intraoral dental) manufactured on or after June 10, 2006, the U.S. required minimum half‐value layer (HVL) was increased; for example, 2.9 (2.3) mm Al at 80 kV, where the value in parenthesis denotes the earlier requirement before the above date.To calculate the transmission of the broad x‐ray beam of modern digital radiography (DR) through shielding materials.X‐ray beam HVLs on two DR systems (Agfa DR 600, GE Revolution XR/d) were measured in 10 kV increments between 60 and 120 kV, with a calibrated ionization chamber (Radcal model 10 × 5‐60) and varying thickness of aluminum 1100 plates. Monte Carlo (Geant4) simulation was performed to calculate the transmission of broad x‐ray beams through lead, concrete, gypsum, and steel, with x‐ray HVLs matching those of the DR 600 at two beam filtrations (default, 1 mm Al plus 0.1 mm Cu added filtration). The transmission data were fitted to the Archer equation.HVLs on two DR systems with default beam filtration were consistent (median difference, 2.1%; maximum difference, 5.5%). An additional beam filtration option (1 mm Al plus 0.1 mm Cu) on the DR 600 substantially increased HVLs by 45.2%–61.2%. Transmission fitting parameters were provided for seven tube voltages (60–120 kV) at two beam filtrations.This work presents transmission data for modern DR systems, indicating increased x‐ray beam filtration compared to the primary x‐ray beam in NCRP Report No. 147. The updated transmission data can enhance structural shielding evaluations at individual tube voltages or with a workload distribution. [ABSTRACT FROM AUTHOR]

Energy‐efficient building materials are eye‐catching for reducing indoor energy consumption via eliminating electromagnetic interference and pollution, controlling the thermal transfer, and promoting sunlight harvesting and providing a comfortable living environment. To realize broadband microwave shielding, the elaborate control of microstructures has showed great potential and research direction. By composition regulation and structure design with various dimension, the synergistic effects including conductive networks, interfacial polarization, magnetic coupling, dipole polarization, and dielectric‐magnetic synergy, can significantly improve electromagnetic (EM) shielding capacity. Thermal management including thermal conversion, thermal storage, thermal radiation, and thermal conduction has enormous potential in enhancing the sustainability and energy efficiency for future buildings. Smart windows are able to switch optical transmittance and colors, which is contributed to saving building energy. Herein, in this review, the recent progress of broadband shielding, thermal management, and smart window in the field of energy‐efficient buildings is summarized, from the aspects of materials, mechanisms, and scenarios. Further, the main bottlenecks and problems are discussed, and potential research opportunities are further highlighted. [ABSTRACT FROM AUTHOR]

Melanogenesis, a natural responsive mechanism of human skin to harmful radiation, is a self-triggered defensive neural activity safeguarding the body from radiation exposure in advance. With the increasing significance of radiation shielding in diverse medical health care and wearable applications, a biomimetic neuromorphic optoelectronic system with adaptive radiation shielding capability is often needed. Here, we demonstrate a transparent and flexible metal oxide-based photovoltaic neuromorphic defensive system. By using a monolithically integrated ultraflexible optoelectronic circuitry and electrochromic device, seamless neural processing for ultraviolet (UV) radiation shielding including history-based sensing, memorizing, risk recognition, and blocking can be realized with piling the entire signal chain into the flexible devices. The UV shielding capability of the system can be evaluated as autonomous blocking up to 97% of UV radiation from 5 to 90 watts per square meter in less than 16.9 seconds, demonstrating autonomously modulated sensitivity and response time corresponding to UV environmental conditions and supplied bias. [ABSTRACT FROM AUTHOR]

AbstractThe ability to easily transport microreactors is a major selling point for deploying microreactors to remote areas. However, this creates a unique shielding challenge, especially when the microreactor is being shipped after irradiation. A traditional reactor configuration utilizes a separate biological shield and pressure vessel to meet radiological shielding and pressure needs. The limited space available for transportable microreactors for both shielding and pressure vessels requires a revised assessment of separating out the biological shield and pressure vessel. To address these concerns, we examine a nuclear-grade sandwich composite (NGSC) that combines the reactor pressure vessel and biological shielding functions into a single component. Through a series of optimization problems for both transportation and operational use cases, the NGSC is able to minimize dose, minimize the vessel cost, and ensure that weight requirements are met for transportation. Initial results show that using a tungsten-tetraboride cermet in the first two layers of a six-layer NGSC provides adequate shielding for both use cases. These results show promise that an NGSC has enough overlap between operational and transportation cases to help reduce the design space for future analysis and assessment. [ABSTRACT FROM AUTHOR]

A novel polymeric composite was created using polyethylene polymers as the primary component, supplemented with varying weight proportions of micro-sized basalt rock powder. Basalt was incorporated into the base material at concentrations ranging from 20 to 40% by weight. The homogenous distributions of the basalt powder within the epoxy layers were affirmed using the scanning electron microscope (SEM) as well as the FTIR spectra for the fabricated composites were analyzed. The gamma-ray shielding properties for the fabricated composites were examined using the narrow beam transmission method on NaI (Tl) detector. The linear attenuation coefficient measurement shows an enhancement in the linear attenuation coefficient from 0.134 to 0.156 cm−1 by raising the basalt powder ratio from 0 to 40 wt%. These results were associated with an enhancement in the radiation shielding properties of the fabricated composites from 12.6 to 14.2% and the lead equivalent thickness reduced from 9.3to 8 cm by raising the basalt powder concentration from 0 to 40 wt%, respectively. Based on the findings, incorporating micro-sized basalt powder into the epoxy resin improves the gamma-ray shielding capabilities of the produced composites in comparison to various polymers documented in prior studies, especially E-B40. In terms of radiation protection, it can be inferred that E-B40 shows promising potential as a shielding material for gamma rays with low energy, offering increased protection with reduced thickness. [ABSTRACT FROM AUTHOR]

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

In this study, we evaluated the effect of different Bi2O3 contents (45–60 mass %) on the radiation protection ability, mechanical properties, and physical properties of glass samples composed of Bi2O3-SiO2-B2O3-ZnO-Al2O3. To assess these properties, we utilized the Monte Carlo based code MCNPX 2.6.0 and the Phy-X PSD program. We calculated various mechanical and physical values, including the elastic modulus, Poisson's ratio (σ), and Fractal Bond Connectivity. The radiation shielding properties of various glass compositions were investigated for a range of photon energies including 0.284, 0.347, 0.511, 0.662, 0.826, and 1.173 MeV. The study found that glass compositions with minimal mole fraction of B2O3 exhibited higher density, Equivalent Atomic Number (Zeq), Effective Atomic Number (Zeff), Molar Oxygen Volume, and lower Half Value Layer (HVL), Tenth Value Layer (TVL), Mean Free Path (MFP), and Oxygen Packing Density. Based on these findings, it can be concluded that the glass composition containing 60Bi is the most effective γ-ray attenuator and is recommended as the best glass for this purpose. [ABSTRACT FROM AUTHOR]

This study investigates the gamma-ray attenuation capabilities of ABS polymer reinforced with nano-sized yttrium particles. The analysis focuses on three key parameters: mass attenuation coefficient, half-value layer, and radiation protection efficiency. Utilizing a sol–gel process for polymer molding, various test samples were prepared and subjected to scanning electron microscopy (SEM) for surface structure examination. Then, experimental, theoretical, and simulation approaches are used to obtain gamma-ray shielding parameters. The base and additive materials are chosen as ABS polymer and yttrium nanoparticles, respectively, and the results revealed a consistent enhancement in gamma-ray attenuation characteristics with the incorporation of yttrium nanoparticles. These findings offer valuable perspectives for advancing the development of sophisticated radiation shielding materials, presenting potential applications across diverse fields including medical imaging, industrial processes, and nuclear technologies. [ABSTRACT FROM AUTHOR]

Gamma‐ray, fast neutron and charged particle shielding characteristics of Praseodymium (Pr3+) activated glasses with composition 10ZnF2‐(10‐x)SrO‐15Li2O‐65H3BO3‐xPr2O3(where x = 0.1, 0.5, 1.0, 1.5, and 2.0) are investigated. For this, the radiation shielding parameters are estimated by using Photon Shielding and Dosimetry (Phy‐X/PSD), Interaction of Proton, Alpha, Gamma rays, Electrons, and X‐rays with matter (PAGEX), Stopping Powers and Ranges for Electrons (ESTAR), and The Stopping and Range of Ions in Matter (SRIM) codes. Furthermore, the results are compared comprehensively and comparatively. The glasses with increasing Pr3+ content exhibited higher shielding potential. It can be said that the ZFLHBPr2.0 sample could be used as a shielding material in various applied fields. Additionally, the effect of Pr composition on structural transitions and time‐dependent volume‐collapse of this new family of borate glass doped with Pr is analyzed by molecular dynamics study (MD) based density functional tight binding method. The simulation results show that the addition of Pr led to the cubic‐orthorhombic transformation of simulation cell at determined temperature and 1 atm pressure. Also, a sudden decrease in volume are observed within a short time at 8% Pr composition (x = 2.0) atmospheric pressure. This result provides a strong connection between Pr composition and volume change with time and at constant low pressure. [ABSTRACT FROM AUTHOR]

Polymers play an essential role in both industry and medical fields due to their diverse and adaptable properties. In this work, prepared crosslinking polyethylene (XLPE) samples with hydrophilic bentonite nanoclay fillers (H2Al2O6Si) at concentrations of 0, 1, 2.5, 4, and 5 wt% enhance their flame-retardant and radiation shielding efficiency. The research investigated flame retardancy and thermal stability parameters. The XLPE/H2Al2O6Si nanocomposite polymer sheets were exposed to a collimated beam of fast neutrons using an Am/Be neutron source (5 Ci) and to gamma radiation using a 137Cs point source (5 μCi) to assess their radiation shielding properties. The study found that uniform dispersion of nanoclay particles enhanced the thermal properties of the composite, forming a char layer that acted as a barrier, slowing thermal decomposition and reducing the heat release rate. Limiting oxygen index (LOI) increased from 28% to 34%, and burning rate improved with higher nanoclay concentrations. Additionally, absorption and optical band gap calculations decreased with increasing filler concentrations. Radiation attenuation capabilities increased by approximately 40% for neutrons and 30% for gamma radiation compared to pure XLPE. The study concluded that incorporating nanoclay fillers into XLPE enhances its shielding capabilities and improves flame resistance properties, making the prepared samples suitable for various industrial applications. [ABSTRACT FROM AUTHOR]

In response to the limitations of current transparent window materials in γ-ray shielding scenarios, herein, high-lead equivalent (0.865 mmpb) Yb 2 Hf 2 O 7 transparent ceramics (YbHO-TCs) were prepared via a solid-state reaction and vacuum sintering. The fabricated YbHO-TC shows high transparency, where the in-line transmittance up to 78.9 % at 1200 nm, which is extremely close to their theoretical limit (79 %). Additionally, the linear absorption coefficient of YbHO-TC for γ-rays is 0.482, approximately twice that of the state-of-the-art lead glass materials widely employed in radiation-shielding windows. Remarkably, YbHO-TC displayed no discoloration, and its in-line transmittance exhibited little change even when exposed to a radiation dose as high as 800 kGy. The innovative developed YbHO-TC integrates high transparency and high-lead equivalent properties, not only rending them highly promising for deployment as γ-rays shielding windows but also inspiring the controllable design of high-performance optical windows tailored for use in radiation shielding applications. [ABSTRACT FROM AUTHOR]

The structural, mechanical and radiation shielding properties of (69-x)B 2 O 3 -20TeO 2 -10Al 2 O 3 -1HfO 2 -xPr 6 O 11 (where x = 0, 0.25, 0.5, 0.75, 1 mol %) glass system were investigated. This study introduces a novel approach by incorporating Pr 6 O 11 into glass composition, highlighting its unique contributions to enhancing elastic properties, fracture toughness, hardness, and radiation shielding abilities. Experimental measurements were conducted within the energy range of 59.54–661.62 keV and theoretical calculations are made for MAC values. The presence of Pr 6 O 11 was noted to positively influence the gamma shielding capabilities. At 59.54 keV, the addition of 0.25 mol% Pr 6 O 11 increased the mass attenuation coefficient of the glass by 2.9 %, and the addition of 1 mol% Pr 6 O 11 increased it by 29.8 %. The addition of 0.25 mol% Pr 6 O 11 increased the fast neutron removal cross section of the glass by 4.4 %. Also, it is observed that the glass with 1 mol% Pr 6 O 11 is the best shielding material against alpha and proton particles. A significant enhancement of 24.36 % in the fracture toughness value was observed, increasing from 1.059 to 1.317 MPa m1/2 at 1 mol% Pr 6 O 11. Experimental hardness values increased from 3.374 to 3.985 GPa, resulting in an improvement of 18.11 % at 1 mol% Pr 6 O 11. The thermal stability (ΔT, °C) value demonstrated a notable increase from 85 to 106, indicating a significant 24.7 % improvement at 0.25 mol% Pr 6 O 11. [ABSTRACT FROM AUTHOR]

With the wide use of radioactive materials, it is important to look for locally available and inexpensive materials to serve as efficient absorbers, suitable for shielding against radiation hazards. Due to its widespread availability and affordability, natural bentonitic shale is a viable option for use as a nuclear shielding material. In this study, natural bentonitic samples were cut into cylindrical pellets of varying thicknesses. The chemical composition of the natural bentonitic shale samples was determined through the use of X-Ray Fluorescence (XRF) spectroscopy. The linear and mass attenuation coefficients of bentonitic samples were evaluated using a NaI(Tl) scintillation detector at 662 keV energy of 137Cs, as well as at 1,173 keV and 1,332 keV energies of 60Co, gamma-ray sources. The experimental results indicated that bentonitic samples B3 and M2 exhibited superior shielding parameters compared to other bentonitic samples, attributable to their elevated densities. These two samples are distinguished by a high CaO content and a low AL2O3 content. Furthermore, the Half Value Layer (HVL), Tenth Value Layer (TVL), and mean free path thicknesses were calculated at these energies using linear attenuation coefficients. The theoretical mass attenuation coefficient, calculated with the assistance of the XCOM program and experimental estimates, was found to be in good agreement with the theoretical value. [ABSTRACT FROM AUTHOR]

Fluoroboro tellurite glasses containing La2O3 with nominal composition of 43B2O3 + 33TeO2 + (12−x)BaF2 + 12Na2O + xLa2O3x = 0 (La0.0), 0.5 (La0.5), 1 (La1.0), 2 (La2.0), and 3 (La3.0) mol% were fabricated using the melt quenching technique. The effects of La3+ ion content inclusion in the prepared glass matrices, including the structural, physical, and optical properties and γ-ray protection efficacy, were then explored. The amorphous state of the La-glasses was verified by the broad and diffuse dispersion of all XRD patterns at low angles. As La2O3 additives were added from 0 to 3 mol%, the density (ρ) increased from 3.6243 g/cm3 to3.8743 g/cm3 and the molar volume (Vm) decreased from 30.6488 cm3/mol to 29.8364 cm3/mol. Lanthanum ion concentrations (NLa) increased from 0 for La0.0 glasses to 312.1103 × 1020 cm−3 for La3.0 glasses. The polar radius decreased from 0 Å to 3.7813 Å, whereas the ligand field strength between La ions and their surroundings increased from 0 Å−2 to 18.1839 Å−2. Values of optical gap (Eg) varied from 3.07 eV to 2.82 eV. The values of linear refractive index (n0) varied from 2.383 to 2.443, whereas values of nonlinear refractive index (n2) changed from 5.16 × 10−11 esu to 6.40 × 10−11 esu for La0.0 and La3.0 glass specimens. Mass (MAC) and linear (LAC) attenuation coefficients were lowest in La0.0 glasses and highest in La3.0 glasses. The trend of the mean free path (MFP) of La-glasses was inverse to that of the LAC and MAC. The order of the MFP trend, which indicates the influence of La2O3 in the glass matrix, was typically (MFP)La0.0 > (MFP)La0.5 > (MFP)La1.0 > (MFP)La2.0 > (MFP)La3.0. Results show that the recommended glasses appear to be promising materials for various optical devices and radiation protection applications. [ABSTRACT FROM AUTHOR]

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This study investigates the X‐ray shielding properties and mechanical properties of barium sulfate (BaSO4) composites based on a biodegradable matrix composed of glycerol and starch. In addition, tannic acid (TA) is used for surface modification of the BaSO4. Increasing the amount of BaSO4 is necessary to improve the composite's X‐ray shielding properties; however, as the amount of BaSO4 increases, the composite becomes harder. The purpose of this research is to prepare a flexible X‐ray‐shielding composite even when a large amount of filler is added. TA easily coats the BaSO4 surface, and its presence is confirmed by Fourier transform infrared spectroscopy and thermogravimetric analysis. Elongation of the composites composed of glycerol, starch, and BaSO4 is increased by 50% because of the formation of hydrogen bonds between the hydroxyl groups of glycerol and starch and those of TA. Consequently, the fracture behavior changed from brittle fracture to ductile fracture. However, the X‐ray shielding properties are not changed by the surface modification with TA. The use of glycerol, starch, and BaSO4 is a new approach to the development of biodegradable radiation shielding materials. In addition, as a surface‐modification agent, TA is environmentally friendly. All of the composites are prepared from natural materials. [ABSTRACT FROM AUTHOR]

This study investigates the individual and combined effects of enhancing the radiation shielding properties of waste concrete using the optimal mix design of two waste material powders of different compositions. Marble (MD) and granite (GD) waste dust were individually utilized as partial replacements for cement at a replacement ratio of 6%. Furthermore, two additional mixes were prepared by incorporating 1% by cement weight of nano alumina (NA) to enhance the microstructure of the studied waste concrete. The MGA-concrete was analyzed using X-ray Fluorescence, Energy dispersive X-ray, X-ray diffraction analysis, transmission electron microscopy, and scanning electron microscope techniques. The radiation shielding assets of the examined Concrete samples, such as the linear attenuation coefficient (μ), half value layer (H1/2), tenth value layer (T1/10), and fast neutron removal cross-section were evaluated using the MCS5 Monte Carlo simulation algorithm and Phy-X software. The results showed that the linear attenuation for the GMN-concretes' order is CO < MD < GD < NA < MD + NA < GD + NA. The GD + Na concrete sample presents the best neutron performance. The studied GMN-concrete samples provide the best protection against γ-rays and fast neutrons. Lastly, the excellent performance of the mixes of waste Granite, Marble, and Nano-Alumina on ordinary would pave the way for their employment as radiation shielding in various nuclear and medical facilities. [ABSTRACT FROM AUTHOR]

This paper studies, structurally analyzes, evaluates the morphology, and assesses the gamma-ray and neutron attenuation properties of a composite material composed of M-type hexaferrite BaFe 12 O 19 (BF) doped with three additional compounds: Bi 2 O 3 , V 2 O 5 , and Ce 2 O 3. X-ray diffraction revealed that the structure of BF can be indexed to a hexagonal structure, BF/Bi 2 O 3 to a tetragonal structure, BF/V 2 O 5 to a cubic structure, and BF/Ce 2 O 3 to a trigonal structure. These results were refined using PROFEX software. The Crystallite size of the nano-powders was determined by X-ray line broadening using the Williamson-Hall method. Morphology evaluations illustrated that HR-TEM images for BF, BF/Bi 2 O 3 , BF/V 2 O 5 , and BF/Ce 2 O 3 reveal high crystallinity with a polycrystalline nature. Various attenuation measurements, using the FLUKA Monte Carlo code, aimed to determine the efficacy of these dopants into m-type hexaferrite BF as potential materials for radiation shielding applications. Doping with Bi 2 O 3 into hexaferrite BF markedly enhances its attenuation properties, demonstrating superior Linear Attenuation Coefficient (LAC) values across a broad energy spectrum from 0.16 to 10 MeV. The Mass Attenuation Coefficient (MAC) analysis revealed a pivotal energy threshold at 0.3 MeV. Below this energy, BF presented the highest MAC values. Conversely, for energies equal to or greater than 0.3 MeV, BF exhibited the highest MAC values, affirming its superior gamma photon shielding efficacy. The study of the Half Value Layer (Δ 0.5) and Mean Free Path (MFP) provided additional evidence of the superior shielding performance of BF/Bi 2 O 3. The Δ 0.5 values ranged between 0.128 to 1.240 cm for BF, 0.162 to 1.430 cm for BF/V 2 O 5 , 0.163 to 1.390 cm for BF/Ce 2 O 3 , and 0.162 to 1.210 cm for BF/Bi 2 O 3 , indicating that BF/Bi 2 O 3 requires a thinner layer to halve the gamma-ray intensity, particularly at higher energies. The MFP values further support the improved shielding ability of BF/Bi 2 O 3 , with measurements showing that gamma photons travel the shortest distance before interacting with the material, thereby reducing the potential for radiation exposure. [ABSTRACT FROM AUTHOR]

This study investigates the influence of La 2 O 3 addition on the structural, physical, and radiation shielding properties of basalt-based glasses. Incorporating varying concentrations of La 2 O 3 (0, 10, 20, 30 wt%) into basalt glasses, we aimed to evaluate the potential of La 2 O 3 in enhancing the material's effectiveness against gamma radiation. Utilizing Ba-133 point radioactive source and Ultra Ge detector, we measured the attenuation parameters in different photon energies (81, 160, 223, 276, 302, 356, and 383 keV). The glasses exhibited an amorphous structure, as confirmed by XRD analysis, with density values ranging from 2.72 to 3.305 g/cm³, increasing with La 2 O 3 content. The microstructural analysis indicated that La3+ ions predominantly integrate into the glass matrix, enhancing the structural integrity without forming separate phase regions. Our findings demonstrate a significant improvement in radiation protection parameters, including mass attenuation coefficients and half-value layers, with higher La 2 O 3 concentrations. These outcomes were also supported by the data obtained for Z eff and EBF values of G1-G4 glasses. The mechanical properties of the glasses were also investigated with the Makishima-Mackenzie model and it was observed that the elastic moduli were also affected by the addition of La 2 O 3. The enhancements observed with La 2 O 3 additions suggest promising avenues for developing advanced shielding materials, combining the inherent advantages of basalt glasses with the high atomic weight and electron density of lanthanum compounds. [ABSTRACT FROM AUTHOR]

To study non-traditional glass materials, this investigation created four glass samples composed of (70-x)B 2 O 3 –20TeO 2 -10GeO 2 -xMgO, where x represents the percentage of MgO with values of 20, 25, 30, and 35 mol%. Glasses with high transparency were produced via the accepted melt quenching and annealing method. The samples underwent X-ray diffraction analysis to confirm their glassy structure. Fourier transform infrared spectroscopy was utilized to examine the glass network's various structural groups. The measuring methodology and theoretical calculations were used to calculate a range of physical and mechanical parameters. The cut-off wavelength, as well as the direct and indirect bandgap, and other optical characteristics of the S1–S4 samples were observed using optical absorption. The work utilized Phy-X to acquire the ionizing absorption parameters. The paper demonstrates various glasses' radiation shielding properties, including the effective atomic number, half- and tenth-value layers, linear attenuation coefficient, mass attenuation coefficient, and mean free path. [ABSTRACT FROM AUTHOR]