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Three zinc barium-borate glasses were produced in the current work, incorporating different metal oxides (MO) (CaO, TiO 2 , and CuO) via the melt quenching technique under a 1100 °C melting temperature for 60 min. The fabricated samples' density is 4.112 g/cm3, 4.157 g/cm3, and 4.261 g/cm3 for glasses dopped with CaO, TiO 2 , and CuO, respectively. Additionally, the Makishima-Mackenzie model was employed to evaluate the effect of metal oxides on the fabricated glasses' mechanical properties. The study shows that the glasses with TiO 2 have the highest mechanical moduli and microhardness which reach 4.67 GPa. The gamma-ray shielding properties in the 0.033–2.506 MeV energy interval were estimated by applying Monte Carlo simulation. The study demonstrates that the glass samples containing CuO exhibit the highest linear attenuation coefficient (LAC) when compared to the glasses containing Ca and TiO 2 compounds. The LAC of the CuO-doped glasses varied between 28.367 cm−1 and 0.163 cm−1 when the photon energy was raised between 0.033 MeV and 2.506 MeV. Also, the study shows good shielding parameters (half-value layer, lead's equivalent thickness, and radiation protection efficiency) for the glasses doped CuO compared to glasses doped Ca and TiO 2. • Zinc barium-borate glasses were prepared for radiation shielding applications. • The gamma-ray shielding properties in the 0.033–2.506 MeV energy range were estimated. • The glass containing CuO exhibits the highest LAC when compared to other glasses. [ABSTRACT FROM AUTHOR]

In this study, we employed 3D printing technology to fabricate poly lactic acid (PLA) polymer samples infused with gadolinium oxide nanoparticles at additive rates of 10% and 20%. The objective was to explore their potential as radiation shielding aprons within the medical X-ray and thermal neutron energy spectrum. To facilitate comparisons, a PLA polymer sample with no additive was also produced. The homogeneity and well-defined structures of the PLA samples were observed using SEM and EDS analyses. Additionally, the excellent thermal stability of the proposed test samples was reported. In terms of gamma-ray shielding, there is a remarkable consistency between experiment, theory and simulation outcomes with a maximum discrepancy of approximately 5%. P-PLA-Gd20 sample exhibits attenuation capabilities against X-rays to a level that could serve as an alternative to lead. Additionally, the thermal and fast neutron attenuation effectiveness of the prepared samples were determined. A shielding effectiveness of 100% against thermal neutrons was achieved using a 10 mm sample thickness and the P-PLA-Gd20 sample. The findings consistently highlight the efficacy of the proposed polymer sample with a 20% gadolinium oxide nanoparticle additive, positioning it as a viable and promising alternative to traditional lead aprons. • A 3D printing technology is used in order to produce lead-free radiation protection apron. • SEM and EDS analyses confirmed the homogeneity and well-defined structures of the printed samples. • P-PLA-Gd20 material could be an exceptional substitute to commercial lead aprons in X-ray workrooms and medical uses. • 100% against thermal neutrons was achieved using a 1 cm sample thickness and the P-PLA-Gd20 polymer. [ABSTRACT FROM AUTHOR]

The purpose of this study was to evaluate the shielding effectiveness of a non-toxic double layer of barium sulfate and tungsten with disclosed elemental compositions against diagnostic X-rays. Three variations of the radiation shielding material were created: one mainly composed of tungsten (mW), another mainly composed of barium sulfate (mBa), and a third composed of a blend of barium sulfate and tungsten (W/Ba). The following three types of 1.0 mm protective sheets were used to compare their shielding effectiveness: a double layer with mW upstream and mBa downstream (mW→mBa); a double layer with mBa upstream and mW downstream (mBa→mW); and W/Ba. Moreover, using experimental measurements and Monte Carlo calculations, the shielding effectiveness against 110 kVp X-rays of mBa→mW (0.495 g cm−2) was compared with the corresponding values for a commercially available lead-free protective apron (0.25 mmPb equivalent) and a 0.5 mm pure lead sheet (0.567 g cm−2). The measured and calculated shielding of a mBa→mW double layer was approximately 1% more effective than that of the reverse arrangement and of the mixture. The shielding effectiveness of mBa→mW was 93.66%, which compared with values of 87.22% for the commercially available lead-free apron and 93.86% for pure lead. In conclusion, the 1.0 mm non-toxic radiation shielding sheet having a double-layered structure with barium sulfate upstream and tungsten downstream was approximately 13% lighter than a 0.5 mm thick pure lead sheet but provided an equivalent shielding effectiveness against diagnostic X-rays. • Proof of benefits with double-layered structure (BaSO 4 upstream, W downstream). • BaSO 4 –W shield 1% better than reverse, 13% lighter than 0.5 mm lead, equal protection. • Non-toxic BaSO4–W shield combines high shielding effectiveness and safety. • Promising future for x-ray shielding techniques with optimized double-layered shield. [ABSTRACT FROM AUTHOR]

The research aims to exploring the gamma-ray shielding capacities of polyacrylonitrile/chrome-filled polymer composites through a combination of experimental, theoretical and simulation methods. Additionally, employing MCNPv6 and GEANT4 simulation tools, the study evaluates the materials' performance against neutron radiation. The materials were subjected to various gamma-ray energy levels, and their shielding efficacies are analytically quantified using parameters such as Radiation Protection Efficiency (RPE), Mass Attenuation Coefficient (MAC), Linear Attenuation Coefficient (LAC), and Half-Value Layer (HVL). At various neutron energies and sample thicknesses, the numbers of transmitted neutrons were evaluated. Notably, composite P0Cr50 (not contain polyacrylonitrile and containing 50% chromium) emerges prominently, demonstrating superior radiation shielding characteristics against both gamma and neutron radiations. This attitude is attributed to its optimal chrome dispersion and density, positioning it as a promising candidate for radiation shielding applications in industrial and nuclear domains. • Composites series including Polymer/Polyacrylonitrile/Chromium were produced. • Gamma and neutron shielding capacities were evaluated. • Experimental, theoretical and simulation methods were used. • An improvement in radiation shielding was observed with increasing Cr amount. • The composite coded as P0Cr50 has the best radiation shielding. [ABSTRACT FROM AUTHOR]

Exposure to high energy radiations like X/gamma rays and neutrons is of serious concern for radiation professionals as they result in several radiation hazards. Shielding plays a prominent role in reducing the radiation exposure. Attempts are being made by several researchers to explore a novel material which can effectively absorb high energy radiations and find a best substitute for lead which is known to be heavy and toxic. In the present study, authors have attempted to synthesize a novel material and investigate the radiation shielding ability and structural properties of Bi 2 O 6 W nanomaterial. Bi 2 O 6 W nanomaterial has been synthesized for the first time using green synthesis approach in order to have environmental friendly material. SEM, XRD & FTIR techniques were used to investigate the physical & chemical structure and gamma ray spectrometer to study the gamma shielding ability of the said material. The XRD results reveal single crystal structure of the material. The mass attenuation coefficient was found to decrease with increase in photon energy due to the interaction of photons with the nanomaterial. The mass attenuation coefficient is found to be 0.127 ± 0.017, 0.142 ± 0.02, 0.106 ± 0.015,0.090 ± 0.013, 0.089 ± 0.013 and 0.094 ± 0.014 cm 2 /g for 0.276, 0.365, 0.511, 0.662, 1.173 and 1.332 MeV gamma rays respectively. The radiation protection efficiency is found to be high in lower energy range when compared to higher energy range of gamma photons. Thus, the newly synthesized nanomaterial can be used for shielding of X/Gamma radiations in the radiation environment thus proving its efficiency in low energy shielding applications like medical field. • Bi 2 O 6 W nano-composite has been synthesized for the first time using green synthesis approach. • SEM studies reveal the flake like structure of the particles. • RPE is found to be maximum in the lower energy range which is found to be equivalent to Lead–conventional shielding material. • Bi 2 O 6 W is highly efficient and environmental friendly material which absorbs gamma radiations. [ABSTRACT FROM AUTHOR]

Exposure to radiation over an extended period causes adverse effects on the human body and also impacts the environment. To mitigate the radiation effects, a protective is necessary, making the need for suitable materials crucial. Polymers, as promising materials in the present time, take centre stage in this review as the primary material for radiation shields, particularly against gamma rays. Another material is lead, which has been proven in previous studies to be effective in shielding against gamma radiation due to its advantages such as high atomic number and density. Additionally, composites made from polymers allow the production of flexible radiation shielding materials. This review provides information on the properties of polymers, basic parameters of radiation protection, radiation interaction with materials, preparation methods for polymer composites, degradation and radiation resistance of polymers, the development of polymer-lead as radiation shielding material, and the recycling of polymer composites. This overview will assist researchers conducting studies in the field of gamma radiation shielding materials. • Development of polymer-lead as flexible gamma radiation shielding. • Exploring strategies for the recycling and sustainability of polymer-lead shielding. • Investigating the development and efficiency of polymer-lead composites shield. • Advance development of ionizing radiation shields based natural polymers filled with lead. [ABSTRACT FROM AUTHOR]

Composite materials such as metal glasses or alloys combine the useful properties and compensate for the shortcomings of the constituent materials. Therefore, a composite material has improved attributes relative to its individual constituents and therefore, more functionalities. This makes alloys very attractive for radiation shielding in many extreme radiation environments. In this report, different gamma-photon interaction parameters of four SnX alloys (where, X = As, Bi, P, and Sb) were evaluated and analyzed at 0.2, 0.662, and 1.25 MeV. The mass attenuation coefficients (μ ⁄ ρ) of the materials were calculated using the XCOM. Furthermore, other parameters such as the effective atomic number (Z e f f ), electron density (N e f f ), mass energy absorption, the specific gamma constant, absorbed gamma dose rate, and buildup factors were also estimated. The values of μ ρ decreased with energy from 0.2844 cm2/g to 0.0518 cm2/g for SnP, 0.2664 cm2/g to 0.0510 cm2/g for SnAs, 0.3321 cm2/g to 0.0509 cm2/g for SnSb, and 0.7771 cm2/g to 0.0664 cm2/g for SnBi. Also, (Z e f f) S n X and (N e f f) S n X decreased with photon energy within the ranges of 33.01–41.25 and 2.66–3.32 1023 electrons/g for SnP; 41.68–44.30 and 2.59–2.76 1023 electrons/g for SnAs; 56.50–56.51 and 2.329–2.53 1023 electrons/g for SnSb; and 68.26–75.43 and 2.51–2.77 1023 electrons/g for SnBi, respectively. The exposure buildup factor of SnP, SnAs, SnSb, and SnBi at a depth of 40 mfp for 1,25 MeV photons were 27, 30, 17, and 16, respectively. Based on the computed quantities, it is clear that SnBi interact more with photons compared to the other three SnX materials. Moreover, the SnX materials can perform better than some commercial and well-known glass shields, especially at low photon energies. Being Pb-free, the SnX shields are preferable to commercial glass shields containing Pb for radiation protection purposes. • Gamma attenuation of SnX (X = As, Bi, P, and Sb) monolayers. • Radiation shielding performance is studied. • Monte Carlo simulations are employed. • SnX shields are preferable to commercial glass shields. • SnBi monolayer has a potential use in nuclear and medical applications. [ABSTRACT FROM AUTHOR]

In this investigation, a wide range of photon energy (0.15–1.5 MeV) was employed for the simulation investigation of gamma radiation protection. To carry out this study, five recently created glass systems with nominal compositions of [19 Na 2 O + 1NiO + (80- x) B 2 O 3 + x Bi 2 O 3 ] (abbreviation BNN-B) glass systems where (x = 0, 5, 10, 15, and 20 mol. %) were created via traditional melting techniques. The shielding radiation parameters, such as mass attenuation coefficient (MAC), half value layer (HVL), mean free path (MFP), and effective atomic number (Z eff) were computed using the Phy-X/PSD program. The obtained results were interpreted based on the structural and optical properties of present compositions. The interesting obtained results indicated that the shielding parameters depended on the chemical composition and photon energy, where superior enhancement of shielding properties was observed by Bi 2 O 3 addition. The MAC increased from 2.45 to 66.84 cm 2 / g when the Bi 2 O 3 content changed from 0.0 to 20%. Moreover, the HVL decreased from 0.13 cm for free Bi 2 O 3 to 0.003 cm at 20% of Bi-content at 15 Kev due to enhanced the density value and structural properties. The MFP showed that the system with a higher content of Bi 2 O 3 had a lower value of MFP at the same energy photon. The values of MFP decreased from 0.188 to 0.004 cm when the Bi-concentration increased from 0.0 to 20 mol% at 15 Kev of photon energy. Finally, the effective atomic number (Z eff) showed that the maximum Z eff was observed at 15 Kev and varied between 10.18 and 74.24 cm from 0.0 to 20% of Bi 2 O 3. The addition of Bi 2 O 3 was found to enhance and improve the shielding properties and have a satisfactory radiation shielding property of borate glass systems. Superior shielding capacity against gamma rays was achieved at the BNN-20B glass matrix. • [19 Na 2 O +1NiO+(80-x) B 2 O 3 +x Bi 2 O 3 ](x = 0, 5, 10, 15 and 20 mol. %) glasses were prepared by the melt quenching technique. • Significant enhancement into density values of the prepared samples has been achieved by Bi-addition. • The band gab (E g) decreased by increasing of Bi3+ content resulting in enhancement the electrical conductivity. • The theoretical gamma radiation properties indicate superior radiation protection of the prepared materials doped Bi 2 O 3. [ABSTRACT FROM AUTHOR]

The use of radiation-shielding materials has significantly increased with the advancement of new technologies. The present work aims to demonstrate that the nuclear shielding properties of boron-aluminosilicate glasses can be enhanced by doping with rare earth elements (REEs) such as erbium (Er) and dysprosium (Dy). Testing was performed by mixing different ratios of dopants into the glass system. This procedure was implemented on 13Al 2 O 3 –21B 2 O 3 -35.4SiO 2 -(30.6-X) Er 2 O 3 -X(Dy 2 O 3) glass, where X = 0, 15.3, 22.1, and 30.6. MCNP6.2, SRIM, PSD, ROOT software, and XCOM databases were used as tools. MCNP6.2 software and XCOM databases were used to calculate, simulate, and validate the mass attenuation cross-sections for 15 selected gamma energies ranging from 0.01 MeV to 10 MeV. On the other hand, SRIM was used to obtain information about the mass stopping power (MSP) and stopping distance, the so-called projected range (PR), for charged particles of H+1 and He+2. Likewise, the PSD was only used to obtain a fast neutron removal cross-section (FNRCS) per density value for each element. This is referred to as the macroscopic neutron cross-section for fast neutron removal in the literature. Finally, the data analysis framework ROOT was used for calculations and graphical representations. To validate this study, the radiation-shielding properties of the material were compared with the globally accepted mass attenuation coefficient database of XCOM using MCNP6.2 simulation results. The proximity between these two is promising. The accuracy of the study was determined by examining the relative error values. The results indicate a strong correlation between the database and theoretical data. Radiation shielding properties such as mass and linear attenuation coefficients (MAC and LAC), half and tenth value layers (HVL and TVL), mean free path (MFP), effective atomic number (Z eff), effective electron density (N eff), effective conductivity (C eff), and fast neutron removal cross-sections (FNRCS) against gamma rays suggested that the lowest X ratio indicated the highest protection. However, the MSP and PR values for the charged particles at most energies indicate the lowest protection with the lowest X ratio in the glass mixture. Finally, the glass shield with the lowest X ratio provided the highest neutron protection, similar to gamma rays. In summary, dysprosium and erbium doping in boron-aluminosilicate glasses can be tailored to specify different requirements for gamma-ray and particle attenuation, as well as neutron absorption. This study aims to fill a gap in the literature by providing a basis for future research on shielding materials based on doped boron-aluminosilicate glasses using high-atomic-number particles, such as REEs, as a radiation protection medium. • Doping boron aluminosilicate glasses with Er and Dy to enhance their nuclear shielding properties. • Er and Dy, as dopants, are compatible with the glass matrix by ensuring a uniform distribution with the glasses. • Aluminum offers an excellent strength-to-weight ratio, making the glass durable, while maintaining its integrity. • Silicon enhances thermal and mechanical stability by ensuring long-term performance. • The boron content enhances neutron absorption, whereas the overall glass structure contributes to gamma-ray attenuation. [ABSTRACT FROM AUTHOR]

Gamma radiation is utilized in various fields, such as food shelf-life preservation, medicine, and industry. The protection against ionizing radiation, such as gamma radiation, is a crucial matter. Ionizing radiation is harmful to both the environment and living organisms, leading to cellular mutations, organ damage, equipment malfunctions, and other adverse effects. To achieve radiation protection, shielding methods are employed. Materials that prevent bacterial growth and contamination should also be developed in all areas. In our study, glass substrates were coated using the rotational coating method. In this study, the antimicrobial and radiation protection properties of glass coatings prepared with ZnPb (50% ZnO + 50% PbO) and TiPb (50% TiO 2 + 50% PbO) ratios were investigated. For radiation protection properties, mass attenuation coefficient (MAC) values were calculated using the Geant4-GATE and XCOM simulations, and the results were compared with the experimental data. Calculations were performed at 511, 662, 1173, 1274, and 1332 keV energy levels. A colony counting method was employed to determine the antibacterial effectiveness of Pb-doped TiO 2 and ZnO. The antibacterial efficacy of Pb-doped TiO 2 and ZnO films was tested against Staphylococcus aureus (ATCC 25923) and Escherichia coli (ATCC 25922) bacteria. It was found that these films were effective only against Staphylococcus aureus bacteria. The antimicrobial efficiency of the nanocomposites was evaluated against various bacterial strains, highlighting significant inhibitory properties, particularly for TiO 2 and ZnO nanocomposites against S. aureus. This emphasizes their potential as antimicrobial agents. • Investigation of PbO-doped ZnO and TiO2 composites for gamma radiation shielding and antimicrobial properties. • Enhanced gamma radiation attenuation due to high atomic numbers of constituents. • Incorporation of PbO boosts antimicrobial efficacy, inhibiting microbial growth. • Potential applications in healthcare, nuclear power, food packaging, and water treatment. • Provides versatile solutions for radiation protection and infection control challenges. [ABSTRACT FROM AUTHOR]

Reinforced composite materials have the potential to provide lightweight, lead-free alternatives to traditional shielding materials. HfB 2 -reinforced epoxy composites were prepared with varying HfB 2 content (ranging from 10% to 60% by weight), and their effectiveness as gamma-ray and neutron shielding material was investigated. The composites exhibited enhanced performance in gamma-ray and neutron shielding efficiency with the increase in the HfB 2 content, as demonstrated by the attenuation parameters. In addition, a monotonic increase in micro-hardness of the composite with the increase of HfB 2 content was also evidenced, indicating their load-bearing improvement. This work highlights the potential of HfB 2 -reinforced epoxy composites as an alternative shielding material for nuclear applications. The findings show that HfB 2 -reinforced epoxy composites can provide both gamma-ray and neutron shielding, making them a valuable alternative for radiation protection in various fields where lightweight is desired, including radioactive material transportation and storage, nuclear medicine, nuclear power plants, and space exploration. • Epoxy composites were manufactured with HfB 2 nanoparticle contents ranging from 10% to 60% by weight. • Combining HfB2 and epoxy led to a composite with enhanced shielding for both gamma-rays and thermal neutrons. • Epoxy composites with 40 % wt of HfB 2 nanoparticles exhibited better neutron shielding than 5% borated polyethylene. • HfB 2 content increased the hardness of the composites. [ABSTRACT FROM AUTHOR]

This research aimed to study the fabrication of X-ray shielding with a focus on sustainability and applications in the biomedical industry. Combining an epoxy composite with waste components from crab shells, eggshells, and bones, the study aimed to contribute to the advancement of eco-friendly alternative for use in medical-related scenarios. This study investigated the elemental composition of natural waste from crab, egg, and bone using X-ray fluorescence, revealing calcium as the predominant component. The findings suggested that these natural waste products could significantly contribute to developing eco-friendly and calcium-rich radiation shielding, presenting valuable insights for advancements in radiation protection technologies. Incorporating waste not only lowered radiation levels but also boosted radiation attenuation percentages. The epoxy composite, particularly with egg, showed a linear attenuation coefficient of 0.44 at 120 kVp. While lead exhibits superior shielding capabilities, the new material demonstrates promising potential. These results highlight the potential of natural waste in crab, bones, and egg for advanced radiation shielding, suggesting adaptability for diverse medical applications. Despite increased waste concentrations causing structural concerns in scanning electron microscope, the epoxy composite demonstrated significant radiation absorption and linear attenuation in escalating natural waste concentrations, suggesting adaptability for medical radiation environments. Balancing sustainability and high-performance shielding, future research should optimize these composites for practical medical applications. • Sustainable X-ray shields using waste from crab, egg, and bone in epoxy. • The high calcium content in the waste materials enhances their potential for effective radiation shielding. • Waste-epoxy composites enhance radiation protection, showing promise for medical applications. [ABSTRACT FROM AUTHOR]

In the present study, four glass samples were fabricated using ordinary melting quenching, and annealing processes. The glass composition was based on (85-x)B 2 O 3 –10Na 2 O-xPbO-5Fe 2 O 3 formula where x = 10, 20, 30 and 40 all in mol%. Additionally, Fourier transform infrared (FTIR) was utilized to investigate the structural behavior of the synthesized glasses; it shows main peaks in the regions around 693 cm−1, 703 cm−1, 913 cm−1, 1001–1060 cm−1, 1187–1211 cm−1, and 1446–1303 cm−1. Moreover, various physical, and mechanical properties were calculated based on the Makishima and Mackenzi model to study the stability of the mentioned glasses. Young modulus reduced from 95.498 to 64.877 GPa for B75Pb10 and B45Pb40, respectively. The Phy-X/PSD software was employed to analyze various radiation shielding properties, including the mass attenuation coefficient and linear attenuation coefficient (LAC). The introduction of PbO% increased density values from 3.287 g/cm³ to 5.408 g/cm³, consequently enhancing the LAC across all incident photon energies. Numerically, the LAC values at 0.015 MeV for all glass samples prepared in this study are remarkably elevated with increasing Pb mol%: 101.38 cm−1, 193.46 cm−1, 289.15 cm−1, and 289.21 cm−1 for B75Pb10, B65Pb20, B55Pb30, and B45Pb40, respectively, suggesting efficient attenuation properties for B45Pb40 than the rest of samples prepared in this work. Various parameters were derived from the LAC, including the mean free path, half-value layer, transmission factor, and radiation protection efficiency. Additionally, an investigation into the variation of the effective atomic number for the prepared samples with energy was conducted. Finally, the relationship between the Specific Dose Constant (Γ) and Photon Energy (MeV) for the prepared samples, along with an examination of the dose rate, was carried out. • Four glasses with composition of (85-x)B 2 O 3 –10Na 2 O-xPbO-5Fe 2 O 3 formula were x = 10, 20, 30 and 40 all in mol%. • The melt-quenching-annealing process was employed in the synthesis of the glass system. • FTIR spectroscopy show different peaks related to B 2 O 3. • The B45Pb40 sample shows the highest density and shielding properties. • RPE value records 81.56% for B75Pb10, 90.05% for B65Pb20, 94.69% for B55Pb30 and 97.19% for B45Pb40. [ABSTRACT FROM AUTHOR]

This study's objective is to evaluate an Al 2 O 3 –PbO–B 2 O 3 –SiO 2 –BaO glass system's radiation shielding characteristics. The composition of the glasses is 15Al 2 O 3 –25PbO–(60-x)B 2 O 3 –10SiO 2 –xBaO, with x in the 5–20 mol% range. Experimental results were used to determine the samples' linear attenuation coefficients (LAC), which were then confirmed by Phy-X program. Utilizing narrow beam transmission geometry, the experimental LAC values were determined. According to the results there was high agreement when comparing the theoretical and experimental values. The LAC values were used to calculate the prepared glasses' mass attenuation coefficients (MAC) and other relevant properties. The mean free path (MFP) values of the sample with 5 mol% BaO were 0.079, 2.549, 3.944 and 4.273 cm at 0.0595, 0.662, 1.173, and 1.332 MeV, thus demonstrating that raising the glass system's BaO enhances the prepared glasses' shielding capacity. According to radiation protection efficiency (RPE), the glasses' capacity to shield the photon is enhanced when their BaO content rises. • Study of shielding coefficients against gamma radiation for different glass. • Using the traditional melt quenching procedure. • Linear attenuation coefficient, LAC, values have been determined experimentally. • The sample APBSB-4 exhibits higher values of LAC than the other glasses. [ABSTRACT FROM AUTHOR]

The Radiation protection is of paramount importance in the planning of human exploration activities in space. The related risks must be considered with respect to two aspects: devising a proper shielding and providing answers to the requirement of an effective dosimetry evaluation in astronaut's activities. Both aspects have been considered using the Monte Carlo (MC) code MCNP 6.2 as the reference tool. As case study an application devised for the National Aeronautics and Space Administration (NASA) Artemis program has been chosen. The project aims to establish a sustainable human presence on the Moon, envisioning the realization of an outpost that will serve as a steppingstone for space exploration endeavors. A Class III shelter, in situ resource utilization (ISRU) built habitat for the Moon, has been designed through computational methods and topology optimization techniques, and analyzed in terms of radiation shielding performances and the strictly related structural behavior. The outpost must be able to withstand temperature variations, micrometeorite impacts, and the absence of a substantial atmosphere. Any solution studied to respect the constraints must devise robust and innovative materials and techniques to create habitats that have as goal the shielding from the Galactic Cosmic Rays (GCR) and from the solar flares to provide a safe and habitable environment at the time scales scheduled for the missions. Moreover, the outpost design must incorporate strategies for extracting and utilizing local resources. Overcoming such challenges will pave the way for the establishment of a sustainable human presence on the Moon and serve as a crucial leap for future space exploration missions. • Radiation protection's crucial role in space exploration planning. • Integration of radiation protection by design in lunar habitat design. • MCNP 6.2 and topology optimization coupling. • Design challenges for a sustainable lunar outpost in Artemis. • Innovative materials for shielding cosmic rays and solar flares. [ABSTRACT FROM AUTHOR]

Astronauts are exposed to a variety of unique stressors during spaceflight, including reduced gravity, isolation, and elevated radiation levels. In contrast with the terrestrial radiation environment, the space radiation environment is dominated by highly charged, energetic light and heavy ions (e.g., protons, alphas, and carbon ions) that interact with atomic electrons and nuclei, producing secondary particle spectra that challenge traditional shielding techniques. The unique radiation environment, demands on astronaut performance during space missions, and the lasting duty to protect astronauts from harm necessitate a space-specific radiation protection paradigm founded in the principles of justification, limitation, and optimization. Recent developments in space radiation protection include: (1) NASA's transition from a risk-based space permissible exposure limit to an effective dose-based limit; (2) emergence of longitudinal radiation worker studies with chronic, low dose rate exposures similar to those experienced by astronauts; (3) active pixel readout-based detectors that provides unique insight into the composition of the intravehicular space radiation environment; and (4) active shielding concepts with the potential to drastically improve upon space radiation shielding approaches that employ matter alone. These advances are contributing to closure of important knowledge gaps and will ultimately enable extended human presence in space. Despite the recent progress in space radiation protection, several important challenges must be addressed to better ensure astronaut health and safety for exploration missions to the Moon and Mars. The purpose of this article is to review current strategies to protect space explorers from harm caused by space radiation and discuss future opportunities to further enhance space radiation protection. • History of NASA's space radiation career limits is contrasted with astronaut corps demographics. • Studies of chronically exposed workers indicate potential for excess neurological disease. • Space radiation monitoring is moving to low size, weight, and power active, pixel-based dosimetry. • Computational tool development has enabled rapid analyses of active shielding configurations. • Despite progress, several challenges in space radiation protection remain to be solved. [ABSTRACT FROM AUTHOR]

This study explores the efficacy of bismuth (Bi) as an additive in X-ray radiation shielding materials, addressing the pressing need for safer and more sustainable alternatives to lead (Pb). To compile a comprehensive dataset, we systematically reviewed 25 scholarly journals sourced from authoritative platforms, including www.sciencedirect.com , www.springer.com , and www.mdpi.com. Our analysis focuses on key shielding parameters and material density values, comparing them before and after the introduction of bismuth. The results, consistent with previous research on Bismuth Oxychloride Nanoparticles (BiOCl NPs) embedded within Polydimethylsiloxane (PDMS) composites, reveal remarkable enhancements. Specifically, the incorporation of bismuth led to an impressive 80% increase in material density, a substantial 99% boost in the Linear Attenuation Coefficient (LAC), and a notable 93% rise in the Mass Attenuation Coefficient (MAC). These findings highlight the promising potential of bismuth-based materials for superior X-ray radiation shielding. Furthermore, we discuss the prospects and challenges surrounding the large-scale production and implementation of bismuth as a sustainable and effective alternative to lead in radiation shielding applications. This study contributes valuable insights into the ongoing efforts to advance radiation protection technologies while minimizing environmental and health concerns. • Evaluate the effectiveness of bismuth-based materials as shields against X-ray radiation. • The density increases by 80%, while LAC and MAC surged by 99% and 93%, respectively. • By BiOCl NPs-PDMS composites improvements in shielding properties. • Prospects and challenges for large-scale production and implementation is discussed. [ABSTRACT FROM AUTHOR]

In this study, TeO 2 –Tl 2 O and TeO 2 –PbO glasses with various compositions were investigated for γ-ray shielding using Phy-X and MCNPX Code. A comparative analysis of the obtained results were performed. The effective atomic number and various parameters, including the mean free path, mass attenuation coefficient, linear attenuation coefficient, and half value layer, were determined in the energy range of 0.01 MeV–15 MeV. It was found that 90TeO 2 –10Tl 2 O glass exhibit the lowest linear attenuation coefficient among the studied samples. At 60 keV, the 82TeO 2 –18Tl 2 O and 90TeO 2 –10Tl 2 O glasses had half-values of T 1/2 = 0.00094 cm and 0.00105 cm, respectively. At 100 keV, the mean free path of the examined materials is estimated to be 0.004 cm and 0.005 cm. The rise in effective atomic number was explained as a greater number of electrons available for photon interaction, which led to a lower chance of γ-ray transit through the shielding material. These results collectively underscore the potential of these glass compositions, particularly those containing thallium to be use as effective shielding materials. These materials have growing importance of effective radiation protection in various fields, including medical imaging, nuclear power, and space exploration. • Radiation shielding properties of Tl and Pb based tellurite glasses are studied. • All the shielding parameters were measured in 0.01 MeV–10 MeV energy range. • All sample shows increase in Z eff. • 90 TeO 2 -10 Tl 2 O glass exhibits the LAC among all the samples. • The studied glasses are promising candidate for the radiation shielding material. [ABSTRACT FROM AUTHOR]

Radiation protection in ultra-intense and ultra-short laser facilities is becoming increasingly important as both the number and the intensity of the laser facilities increase rapidly with the development of laser technology. Experiments show that bremsstrahlung photon dose is usually dominant in this new type of ionizing radiation source. Therefore, estimation of bremsstrahlung photon dose is essential for radiation protection in ultra-intense and ultra-short laser facilities. This paper reviews the current literature on the bremsstrahlung photon dose level obtained by experiments and photon dose estimation models. The effects of laser-target interaction experiment configuration on the photon dose are also analyzed. Experimental measurements are collected from a total of 18 ultra-intense and ultra-short laser facilities with laser intensities from 1017–1021 W cm−2 μm2. Measured normalized photon dose values are spread over six orders of magnitude from 10−5–1 mSv J−1 shot−1. The widespread range of normalized photon dose suggests that there might be some factors not considered in the photon dose estimation models. In this review, four important electron physical quantities related to the photon dose are introduced, which are hot electron energy distribution (d N e / d E e ) , characteristic temperature of electron (T h) , laser-to-electron conversion efficiency (η) , and electron divergence angle (θ). Then, four photon dose estimation models are introduced and discussed. The measurement results in the literature are compared with the predicted values of these models. Predicted values of T h , η and normalized photon dose given by the different scaling laws or dose estimation models are compared with measured data. The diagram of normalized photon dose can be roughly divided into four regions according to different target schemes, namely foil target, solid target, coated target and hybrid target scheme. This review shows that the target scheme is one of the most relevant factors that affect the bremsstrahlung photon dose level. For the radiation shielding of such ultra-intense and ultra-short laser facilities, consideration of different target schemes may help ensure radiation safety and reduce the cost. This review could provide a reference for radiation protection of the Ultra-Intense and Ultra-Short Laser facilities. • Experimental data collected from 18 ultra-intense and ultra-short laser facilities. • Dose estimation models are reviewed and analyzed. • Comparison between the measured data and estimation curves is performed. [ABSTRACT FROM AUTHOR]

Conventional gamma radiation shielding materials, such as lead and lead-based composites are heavy and hazardous to human health and the environment. This particular aspect has prompted research into alternative shielding materials. The key objective of this work is to investigate Bismuth Oxide and unsaturated polyester resin (UPR)-based polymer composite material as a radiation shielding. The investigation used a gamma spectrometer consisting of an HPGe detector and the radioactive point sources 60Co, 133Ba, and 137Cs that have energies ranging from 81 keV to 1332 keV for experimentally evaluating mass attenuation coefficient (MAC). Subsequently, the experimental results for MAC were compared with the corresponding values obtained from WinXCOM and Geant4 simulation. Our findings indicated that the mass attenuation coefficient values of experimentally investigated composites align well with the theoretical and simulated values. In addition, we examined the half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), and radiation protection efficiency (RPE) parameters. From the study, it can be inferred that lead (Pb) can be replaced by UPR+50 wt% Bi 2 O 3 composite for low-energy gamma-ray shielding applications. • Synthesis of Unsaturated Polyester Resin and Bismuth Oxide Composites. • Gamma-ray shielding analyses using experiments, WinXCOM, and Geant4. • HVL, TVL, MFP, RPE, Z eff , and N E for Unsaturated Polyester/Bi 2 O 3 Composites. • XRD, SEM, and TGA of the Unsaturated Polyester/Bi 2 O 3 Composites. • Effective radiation shielding material for low-energy gamma photons. [ABSTRACT FROM AUTHOR]

This paper investigates the indirect influence of elevated temperature on the radiation protections competence of berlinite (SiO 2 -type AlPO 4) by examining the modulations of its intrinsic tetrahedral parameters. The study focuses on the temperature-dependent changes in the crystal structure of berlinite and their influence on its radiation attenuation properties. The lattice parameter a, and c, c/a ratio, unit cell volume (V c), atomic packing factor (APF), and other factors such as the atomic arrangement, atomic interactions, and crystal defects are analyzed in relation to the MAC and LAC. The calculations are performed for berlinite AlPO 4 samples prepared at temperatures ranging from 25 °C to 631 °C. The results reveal that the LAC values of berlinite AlPO 4 are changed from 14.65 to 15.39 cm−1, indicating stable linear attenuation properties across the temperature range. The lattice parameters, V c , and APF exhibit linear relationships with the LAC values, suggesting their significance in determining the radiation attenuation capabilities. • Temperature LAC-dependence. • Linear relationship between lattice parameters and LAC. • Crystal structure modifications for improved shielding. • Role of intrinsic parameters and defects. [ABSTRACT FROM AUTHOR]

The work studies the possibility of using a polymer composite based on polytetrafluoroethylene and modified radiation shielding fillers for protection against neutron radiation in space conditions. The physico-mechanical properties of the composite are presented, as well as the simulation of the neutron radiation passage through the polymer composite is performed by the Monte Carlo method using the GEANT4 software toolkit. The polymer composite proposed has high structural properties necessary for use in the space sphere. The Vickers hardness for a load of 200 g is 12.11, the erosion wear is 0.049∙10−3 mm3/g, the density is 4232 kg/m3. The most effective thickness of the protective layer to attenuate the intensity of neutron radiation is 8 cm, to reduce the equivalent dose of 30 g/cm2. The thickness of the protective layer made of the proposed polymer composite against cosmic radiation is 35% less than that of aluminum and 77% less than that of polyethylene, which is a very important factor for using the material in spacecrafts because of extremely limited free space on board. This indicates the prospects of its use for neutron radiation shielding at high energies to achieve complete and effective protection of astronauts and spacecraft equipment. • A polymer composite for protection against neutron radiation has been studied. • The neutron impact was simulated using the GEANT4 software toolkit. • Semi-experimental irradiation of the composite with neutrons was carried out. • Composite retains high erosive wear resistance and Vickers hardness at low density. • The use of a composite will reduce the thickness of the protective layer on spacecraft. [ABSTRACT FROM AUTHOR]

This study aimed to examine the radiation shielding capabilities of four distinct germanate glass systems with compositions of TeO 2 -GeO 2 -ZnO, B 2 O 3 -GeO 2 -Eu 2 O 3 -R 2 O 3 (where R Y, La and Gd), Li 2 O–Sb 2 O 3 - GeO 2 -XO (where X = Pb, Zn, Ba, Sr and Ca) and Li 2 O-GeO 2 -PbO-Nd 2 O 3 at different photon energies ranging from 0.015 to 10 MeV respectively. The present study involved the determination of mass attenuation coefficients (MAC), effective atomic number (Z eff), and half value layer for four distinct germanate glass systems. The influence of chemical composition, sample density, and photon energy on these parameters was also discussed. The findings indicate that the substitution of TeO 2 with ZnO leads to a reduction in the values of both the mass attenuation coefficient (MAC) and the effective atomic number (Z eff) in the glasses composed of TeO 2 -GeO 2 -ZnO. Furthermore, it has been discovered that within the B 2 O 3 -GeO 2 -Eu 2 O 3 -R 2 O 3 glass system, the highest values of MAC are observed in the glass containing Gd 2 O 3. The sample that contained PbO exhibited the highest MAC and Z eff values among the Li 2 O–Sb 2 O 3 -GeO 2 -XO glass systems. Furthermore, the findings of this study indicate that the glass specimen containing CaO exhibits the least values of MAC and Z eff within the given system. The findings indicate that the values of MAC in the Li 2 O-GeO 2 -PbO-Nd 2 O 3 glass system exhibit an upward trend with the rise in Nd 2 O 3 concentration from 0 to 2 mol%. • Radiation shielding characteristics of various GeO 2 glasses have been studied. • XCOM program were studied at several photon energies between 0.015 and 10 MeV. • Gamma photons absorption capacity increases when density of the sample increases. • High density glasses promising effective radiation shielding. [ABSTRACT FROM AUTHOR]

Exploration of reinforcing alkaline oxide modifiers into the nominal composition of 40P 2 O 5 +(30‒X)CaO+XMgO+9SiO 2 +6Sr 2 F+6LiF+6BaF+2.5Ce 2 O 3 +0.5Sm 2 O 3 (where X= 0, 5, 10, 15, 20, 25 in wt%) has been performed. Oxides from the same alkaline group (CaO and MgO) have been chosen as a modifier. Glasses were made through the customary melt-quench technique. Successful glass formation was confirmed by XRD and functional group and compositional analysis via FTIR. Electronic structures of the proposed poly-component glasses are visualized by absorption spectra in the three prominent regions of the (electromagnetic) EM spectrum. Auxiliary physical, structural, and elastic properties were scrutinized for the approval of glasses as an obedient shielding material and evaluation of some other attenuating factors of EM wave by poly-component glasses in the gamma-ray region. The linear attenuation coefficient (LAC) was reported in the energy range of 0.284–1.333 MeV. The LAC results demonstrated that the interaction of the photons with the prepared specimens is high at lower photon energies and the shielding provided by the samples is relatively high when the energy level is low. The addition of MgO results in an improvement in the LAC values, and as a consequence, PS0Mg and PS25Mg had the lowest and highest LAC, respectively. The highest transmission factor values were reported for a thickness of 0.3 cm and equal to 0.87 at 0.284 MeV, 0.91 at 0.551 MeV, and 0.93 at 0.826 MeV (this is for PS0Mg sample). • Concentration dependent alkali modifiers were prepared via melt quench technique for shielding applications. • Physical, structural and elastic properties of all the prepared glasses were examined in detail. • PS25Mg glass exhibits higher LAC value, 1.333 MeV. • Radiation protection efficiency increases by increasing the wt% of MgO into the glass composition. [ABSTRACT FROM AUTHOR]

We prepared epoxy resin composites containing Sb 2 O 3 and Al 2 O 3 for radiation shielding applications, such as in the fields of nuclear medicine and medical radiation for both occupational and public radiation protection. The linear attenuation coefficient (LAC) was measured by a collimated gamma radiation technique with the use of a NaI(Tl) scintillation crystal detector. The density of the prepared SbAl composites is determined to be between 1.31 and 1.48 g/cm3, which is higher than that of pure epoxy. We reported the impact of Al 2 O 3 on the radiation shielding performance of the prepared composites. At 0.059 MeV, we found that the linear attenuation coefficient (LAC) increases from 1.45 to 1.64 cm−1 when the Al 2 O 3 changes from 5 to 20 w.t.%. We found that at 0.059 MeV, the Al 2 O 3 has a notable impact on the LAC and on the other parameters such as the half value layer. At 0.662 MeV, we found that the Al 2 O 3 has a small influence on the LAC and HVL, where the LAC increases only from 0.0978 to 0.1071 cm−1. Moreover, the HVL at 0.662 MeV is in the range of 6.47–7.08 cm. From the HVL results, we found that epoxy resin composites that are thinner than 6 cm and include 15% Sb 2 O 3 and various quantities of Al 2 O 3 (up to 20%) are not appropriate for use in applications that demand for attenuating radiation with an energy lower than 0.662 MeV. The study's findings could be useful in optimizing shielding materials used to help protect personnel and patients in facilities using medical radiation sources, such as nuclear medicine. • We prepared epoxy resin with Sb 2 O 3 and Al 2 O 3 for radiation shielding applications. • The LAC was measured using NaI(Tl) detector. • The density of the composites is determined to be between 1.31 and 1.48 g/cm3. • The LAC at 0.059 MeV increases from 1.45 to 1.64 cm−1. • At 0.662 MeV, we found that the Al 2 O 3 has a small impact on the LAC and HVL. [ABSTRACT FROM AUTHOR]

Recently, there has been arising a severe alert regarding climate crisis all over the world. As industrial production capacities have been soaring every passing day, the primary sources of the earth's crust have been depleting like there is no tomorrow. Sustainable and greener suggestions should be followed to overcome the upcoming catastrophic climate change. With this motivation, cement material, whose influence on global warming is excessive, has been studied to be replaced by alternative material systems in different application areas, and radiation shielding applications may be regarded as one of these emerging fields. In this study, the authors were motivated to replace ordinary Portland cement (OPC) with alternative side streams (SS) that have accumulated in nature without any benefits. First, the high-quantity SS were determined and presented as follows: fly ash (FA), blast furnace slag (BFS), red mud (RM), electric arc furnace slag (EAFS), fayalite slag (FS), rice husk ash (RHA), silica fume (SF), ferrochrome slag (FS), and copper mining tailings (CMT). Each side stream's average chemical compositions were obtained, and their theoretical density values were calculated. After that, the theoretical radiation shielding properties were assessed using Phy-X/PSD software within the 0.15–15 MeV photon energy range. Some essential parameters such as linear attenuation coefficient (LAC), half-value layer (HVL), effective atomic number (Z eff), radiation protection efficiency (RPE), and build-up factors (EBF and EABF) paved the way for comparing SS with OPC material. The results for radiation protection demonstrated that high-density-oxide-containing SS like RM, FS, and EAFS could replace OPC material with a good performance. Owing to this replacement, the authors strongly believe that the future can be sustained in a more secure environment without OPC material, but with SS in radiation shielding applications. • Abandoned industrial waste substances can replace cement in radiation protection applications. • RM, FS, and EAFS possess great potential over OPC due to their high-density oxide. • Silica-containing waste substances, such as RHA or SF, are yet to be focused on to increase their potentiality. • RPE at 0.662 keV can reach up to 90% with RM and FS using an eight cm thickness. [ABSTRACT FROM AUTHOR]

Tungsten based alloy is one of the materials which has great attention and can be used as gamma-ray shields, radiation source collimator, spallation neutron source target, plasma facing materials, etc. The motivation of the study is to produce new tungsten based alloys and determine the radiation protection characteristics of the alloys that can be used for radiation related applications. In this context, five tungsten based alloys (W x Ta y Cr 10 Ni 10 Fe 10 Mo 10) were produced and the dependence of radiation shielding ability on the changes in W and Ta concentration was investigated. The photon protection parameters such as linear attenuation coefficients, mass attenuation coefficients, effective atomic number, mean free path, half-value layer, exposure and energy absorption buildup factors, effective conductivity, effective electron number, atomic and electronic cross sections, and fast neutron removal cross-sections of the alloys were determined by Phy-X/PSD code. Additionally, XRD, EPR and SEM-EDS experimental results were evaluated for the investigation of spectroscopic characteristics. The crystallite sizes of the alloys were calculated by Debye-Scherrer method depending on the XRD phases in order to perform the structural characterization. It is concluded that a relationship exists between the crystallite size and photon attenuation. It may be stated that the increase in the amount of W improves the gamma radiation protection efficiency of the alloys. It is also seen that the fast neutron attenuation feature increases proportionally with W content. It is determined that the tungsten based alloys can be used as good radiation protection materials in radiation related applications. • New W-based alloys have been produced. • Photon protection parameters of WBAs has been calculated. • Spectroscopic features have been investigated. • WBAs can be used as shielding materials for radiation related applications. [ABSTRACT FROM AUTHOR]

The search for new, non-toxic, and effective alternatives for radiation protection to lead-based materials is highly demanded in the present era. In the present research, a series of ceramic composites of barium titanate (BaTiO 3 , BTO) added with different amounts (x = 0, 5, 10, and 20 wt%) of nano spinel ferrite (Co 0.8 Ni 0.1 Mn 0.1 Fe 1.9 Ce 0.1 O 4 ; NSF) were fabricated to evaluate their shielding performance against gamma radiation. The different samples were subjected to photons with energy ranging from 0.060 to 1.333 MeV emitted from Co-60, Cs-137, and Am-241-point sources, and the intensity of photons was detected using the HPGe detector. The prepared ceramics were first characterized by the XRD diffraction technique to examine the phase and crystal structure. The analysis showed the successful formation of the desired composites. The linear attenuation coefficient (LAC) values were determined experimentally to test the shielding performance of the composites. The LAC achieves its maximum values at an energy level of 0.06 MeV (31.88, 31.98, and 32.12 cm−1 for the composites with x = 5, 10, and 20 wt%, respectively, then it decreases at 0.662 MeV to 0.459, 0.461, and 0.465 cm−1 for the same mentioned compositions. LAC results showed that the current ceramics have a reasonably strong attenuation efficiency at low energy and can block many photons. The highest radiation protection efficiency (RPE) has occurred at 0.06 MeV and it is in the order of 95%. The RPE of the composite with x = 20 wt% is slightly greater than the RPE of the other ceramic samples. The half-value layer (HVL) data demonstrated that the shielding efficiency is related to the composition of the material, where the composite with x = 20 wt% showed a lower HVL than the other composites. • Ceramic composites of barium titanate and nanospinel ferrite were synthesized. • Various radiation shielding parameters were experimentally measured and determined. • Composite with 20% nanoferrite showed the highest radiation shielding efficiency. • These composites can be effective for low-energy radiation shielding applications. [ABSTRACT FROM AUTHOR]

Different mortar samples with marble dust and Zr 2 O 3 nanoparticles were prepared. The radiation attenuation coefficients for the prepared samples were measured experimentally using HPGe detector and three radioactive point sources Co-60, Cs-137 and Am-241. We investigated the transmission factor as a function of the thickness of the mortar and we found that increasing the thickness of the specimens leads to reduce the number of photons that are able to pass through the sample, which results in an improvement in the sample's potential to attenuate radiation. The linear attenuation coefficient is determined and we reported a positive relation between the LAC and the amount of Zr 2 O 3 nanoparticles. While, we reported an inverse relation between the LAC and the energy of the radiation. From the LAC results, we found that the mortars are more effective at attenuating photons of energy<0.662 MeV. For the developed mortars, we evaluated the half value layer (HVL) and the results demonstrated that Mor-1 has the highest HVL, whilst Mor-5 has the lowest HVL. The HVL for Mor-1 is 0.963 cm at 0.060 MeV and 4.06 cm at 0.662 MeV. The HVL decreases with the incorporation of Zr 2 O 3 nanoparticles into the prepared mortar samples. The radiation protection efficiency (RPE) values at 0.060 MeV are 76.3, 81.06, 84.93, 88.06 and 90.56% for Mor-1 to Mor-5. • Newly developed mortars with marble dust and Zr 2 O 3 nanoparticles were fabricated. • TEM and EDX analysis were studied for presented mortar samples. • The radiation shielding features was discussed using an experimental technique. • The HVL decreases with the incorporation of Zr 2 O 3 NPs into the mortar samples. [ABSTRACT FROM AUTHOR]

This study provides insight into B 2 O 3 –SiO 2 –CaO–Bi 2 O 3 glasses where novel results for the effects of WO 3 content on its structural and optical properties have been demonstrated. Thus, provides useful data for developing new glasses for optical and electromagnetic shielding applications. The effect of WO 3 content on the structural and optical properties of B 2 O 3 –SiO 2 –CaO–Bi 2 O 3 glasses was investigated along with radiation shielding features which have been calculated by XCOM program. BSCB/W-00, BSCB/W-2.5, BSCB/W-5.0, BSCB/W-7.5, BSCB/W-10, BSCB/W-15, and BSCB/W-20 refer to seven samples of bismuth borosilicate glass system doped with 0.0, 2.5, 5, 7.5, 10, 15, and 20% of WO 3 , respectively, synthesized using the melt quenching technique. The density of the glasses decreased with increasing WO 3 content due to the replacement of Bi 2 O 3 with lower-density WO 3. It was found that the absorption coefficient decreased with increasing WO 3 content up to 10 wt%, but showed an opposite trend for samples with higher WO 3 content. The optical band gap and the transition type were affected as the WO 3 content increased. The electromagnetic wave decay or skin depth was also calculated. Overall, the shielding effectiveness of investigated samples BSCB/W-00, BSCB/W-2.5, BSCB/W-5.0, BSCB/W-7.5, BSCB/W-10, BSCB/W-15, and BSCB/W-20 has reduced with the enlargement of the WO 3 concentration. BSCB/W-00, out of all the samples tested, has the highest shielding efficiency. • WO 3 -doped BSCB glasses show novel optical/structural traits. • WO 3 addition alters properties, enhancing optics/radiation shielding use. • Glasses display polycrystalline or amorphous structures based on WO 3 level. • Tunable band gap properties make them apt for optoelectronics. • Study aids in developing tailored glasses for radiation protection. [ABSTRACT FROM AUTHOR]

In this study, absorption and shielding parameters such as mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), radiation protection efficiency (RPE), total atomic cross-section (σ t,a), molecular cross-section (σ t,m), electronic cross sections (σ t,e), effective atomic number (Z eff), effective electron density (N eff), molar extinction coefficient (ε), K-shell jump ratio (r K) and jump factor (J K) have been investigated experimentally around the K edge for Ba(ClO 4) 2.3H 2 O using EDXRF technique and the X-ray attenuation method. Initially, the targets used as secondary sources were excited by γ-rays of 59.54 keV energy emitted from a 5 Ci 241Am annular primary radioactive source. Then, HPGe detector with a resolution of 182 eV at 5.9 keV was used to count K X-rays emitted from these secondary source targets and absorbed by Ba(ClO 4) 2.3H 2 O. The experimental results obtained for various secondary photon energies were compared with the theoretical results obtained from programs such as WinXCOM, FFAST and Phy-X/PSD, and it was concluded that these experimental and theoretical results were quite compatible. • The absorption and shielding parameters are determined for Ba(ClO 4) 2.3H 2 O around K edge using experimental and theoretical methods. • The mass attenuation coefficients decrease up to the K absorption edge energy and increase sharply after near the absorption edge. • The transition geometry is used to absorb x-rays emitted from the secondary source by the target. • EDXRF results are in good agreement with WinXCOM, FFAST, and Phy-X/PSD results. [ABSTRACT FROM AUTHOR]

Radiation shielding parameters of oxidized compounds of some selected rare earth elements were determined. These parameters are mass absorption coefficient, effective atomic number, electron density, half-value layer, tenth value layer, and mean free path values. A variable energy x-ray (VEX) source was used as an exciter in the system, where these basic parameters will be determined. An experimental setup was prepared in attenuation geometry. Experimentally measured and theoretically calculated mass attenuation values of the target materials were used to calculate radiation protection parameters. As can be seen from previous works, the WinXCOM program efficiently calculates theoretical atomic cross-sections and mass absorption coefficients. As a result of the search for alternatives to this software, ParShield and Phy-X programs have emerged at different times. In this study, the validity of ParShield and Phy-X programs produced as other options to the WinXCOM program were tested, and the results were found to be entirely satisfactory. • The radiation shielding parameters are commonly used in nuclear power plants and healthcare organizations. • The radiation shielding parameters have been determined experimentally and theoretically. • The energy range's width provides a large work area. • Our present experimental values are in good agreement with theoretical values. [ABSTRACT FROM AUTHOR]

The present work aims to develop new epoxy-based composites with halloysite, basalt, PbO, CuO, and Bi 2 O 3 fillers. The role of the utilized fillers in the structural properties of the fabricated composites was studied using the Fourier transform infrared spectrometer and scanning electron microscope. Additionally, the role of utilized fillers in reducing the equivalent dose rates from Co-60 and Cs-137 isotopes were experimentally examined where the equivalent dose rate values ranged between 1.95 μSv/h–1.36 μSv/h (for E@PbO), 1.88 μSv/h–1.31 μSv/h (for E@Bi 2 O 3 composite), 1.97 μSv/h–1.43 μSv/h (for E@CuO composite), 1.96 μSv/h–1.46 μSv/h (for E@Halloysite composite), and between 1.94 μSv/h–1.47 μSv/h (for E@ Basalt composite), raising the composites' thickness between 1.0 and 4.65 cm, at gamma-ray energy of 0.662 MeV. Based on the examined equivalent dose rate, the shielding parameters of the fabricated composites were evaluated where the radiation protection efficiency f reaches 36.4%, 33.2%, 31.8%, 38.8%, and 31.3% for epoxy resin reinforced by 25 wt% of PbO, CuO, halloysite, Bi 2 O 3 , and basalt, respectively, at gamma-ray energy of 0.662 MeV. The observed outcomes demonstrated that the radiation shielding parameters of low-cost epoxy resin with natural fillers (halloysite and basalt) are marginally inferior to those of CuO, PbO, and Bi 2 O 3 fillers. These results support the feasibility of creating shielding polymer composites using natural fillers rather than expensive and hazardous heavy-weight fillers. • Five epoxy doped heavy metals and natural materials were fabricated. • Epoxy reinforced by heavy metal oxides has D c o m p o s i t e varied between 27 and 30%. • Epoxy doped by natural fillers has D c o m p o s i t e varied between 24 and 25%. • Epoxy reinforced by natural fillers is more feasible than hazardous heavy metal oxides. [ABSTRACT FROM AUTHOR]

This study reports a novel shielding material against high energy electron beam, where bismuth oxide (Bi 2 O 3) and multiwalled carbon nanotube (MWCNT) nanoparticles added in a polymer matrix can solid electron beam radiation several times more efficient than aluminum with the same areal density. The polymer nanocomposites were prepared by dispersing nanoparticles in polydimethylsiloxane (PDMS) with a simple one-step fabrication process, in five areal densities (0.5, 1, 1.5, 3, and 5 g/cm2). All the samples were irradiated by 9, 12, 16, and 20 MeV electron beam. The prepared PDMS/CNT/BiO (CNT and BiO are the shorten name of fillers for coding the samples) showed better electron shielding ability than aluminum (Al) for any areal density. The weight advantageous of nanocomposite over aluminum was calculated up to 36 wt% for same attenuation efficiency. The thermal stability of nanocomposites up to 415 °C, as well as the tensile strength of up to 4.7 MPa, exhibited the high potential of developed samples for high energy electron beam shielding in medical and aerospace applications. PDMS polymer nanocomposites were fabricated for energetic electron radiation protection application. After characterization of samples for thermal and mechanical properties, they were tested for electron shielding performance. Based on the results, the nanocomposites can reach a weight advantage of up to 36 % when comparing to aluminum. [Display omitted] • PDMS polymer nanocomposites can be applied to shield electron radiation. • The nanocomposites can reach up to 36% weight reduction comparing to aluminum (Al). • Nanocomposites show higher attenuation efficiency than Al at all areal densities. [ABSTRACT FROM AUTHOR]

The statistical fitting of existing data is an efficient method for calculating the gamma-ray buildup factors. However, the existing Geometric Progression (GP) fitting formula requires the interpolation of five parameters: a , b , c , d , and X k. GP fitting formula also considers three factors: photon energy, shielding material and shielding in the interpolation process, leading to the complex calculations of buildup factor. On the other hand, the large and bloated parameter library also brings inconvenience to the application of GP formula in radiation calculation code. This paper proposes a regression method for calculating gamma-ray buildup factors based on Extra-Trees (ET). The training set is obtained from the exposure buildup factors of the ANS standard database to establish the ET with superior performance for buildup factor. The ET model can reproduce the data of exposure buildup factor in ANS without deviation. For materials not considered in ANS, the buildup factors calculated by ET model are consistent with the results calculated by GP fitting formula. The performance in time consumption is also satisfactory. The method proposed in this paper has the potential to replace GP fitting formula and be used in situations where the buildup factor needs to be calculated, such as design, shielding calculation and analysis of gamma-rays. • This work presents a regression method for calculating gamma-rays buildup factors based on Extra-Trees (ET). • Establish the Extra-Trees model with superior performance for buildup factors using ANS standard database as training set. • The buildup factors calculated using ET model are highly consistent with the ANS data and GP formula results. • The proposed method is highly efficient and simple to implement. [ABSTRACT FROM AUTHOR]

This repot aims to probe the physical, mechanical and radiation-protecting properties of a series of glasses with a chemical composition of yZrO 2 +(24.5-y)CaO+24.5Na 2 O+ 6P 2 O 5 +45B 2 O 3 (0.5

Chest X-ray imaging is the most common X-ray imaging method for diagnosing coronavirus disease. The thyroid gland is one of the most radiation-sensitive organs of the body, particularly in infants and children. Therefore, it must be protected during chest X-ray imaging. Yet, because it has benefits and drawbacks, using a thyroid shield as protection during chest X-ray imaging is still up for debate.Therefore, this study aims to clarify the need for using a protective thyroid shield during chest X-ray imaging. This study was performed using different dosimeters (silica beads as a thermoluminescent dosimeter and an optically stimulated luminance dosimeter) embedded in an adult male ATOM dosimetric phantom. The phantom was irradiated using a portable X-ray machine with and without thyroid shielding. The dosimeter readings indicated that a thyroid shield reduced the radiation dose to the thyroid gland by 69% ± 18% without degrading the obtained radiograph. The use of a protective thyroid shield during chest X-ray imaging is recommended because its benefits outweigh the risks. • The effectiveness of radiation shield on dose reduction was studied. • TLD and OSL dosimeters were used. • In use of a thyroid shield doses to the thyroid were reduced by 69% ± 18%. • Thyroid shields do not affect the quality of the obtained radiograph. [ABSTRACT FROM AUTHOR]

Abstract This work investigated the gamma-ray shielding, cure characteristics, physical, and mechanical properties of ethylene propylene diene monomer (EPDM) rubber composites with additions of metal oxides (either iron (II, III) oxide; Fe 3 O 4 , tungsten (III) oxide; W 2 O 3 or bismuth (III) oxide; Bi 2 O 3) for potential use as flexible, durable, and lead-free gamma-ray shielding materials. The results showed that increases in the metal oxide contents from 0 to 100, 300, and 500 phr (parts per hundred of rubber), respectively, improved the gamma-ray shielding properties of the EPDM rubber composites with the highest gamma attenuation in 500-phr Bi 2 O 3. The results also showed initial decreases in the cure times at a 100-phr metal oxide content but subsequently increased at higher contents (300 phr and 500 phr). Furthermore, while tensile modulus at 100% elongation and hardness (Shore A) kept increasing with increasing metal oxide contents, tensile strength and elongation at break behaved differently as they initially increased at 100 phr but later decreased at 300 phr and 500 phr. In addition, after the accelerated-weathering studies, the tensile modulus at 100% elongation and tensile strength of the EPDM rubber composites increased but the elongation at break and hardness (Shore A) decreased. In summary, the overall properties suggested that these developed metal oxide/EPDM rubber composites could be effectively used to replace lead-containing materials as durable gamma-ray shielding materials. Highlights • Metal oxide/EPDM rubber composites were developed as gamma-ray shielding materials. • Bi 2 O 3 /EPDM rubber composites had the highest gamma-ray shielding properties. • 500-phr Bi 2 O 3 /EPDM rubber composites had higher μ m than pure Pb sheets. • Bi 2 O 3 /EPDM composites could replace commercial lead-containing shielding materials. [ABSTRACT FROM AUTHOR]

This paper presents the gamma shielding performance of Poly lactic acid (PLA) composites doped with 4%, 8%, 12%, and 16% Gd 2 O 3 to investigate the impact of dopant amount on gamma shielding with an energy of 241Am (59.5 keV), 133Ba (81.0, 276.4, 302.9, 356.0, 383.9 keV), 22Na (511.0,1274.5 keV), 137Cs (661.7 keV), and 60Co (1173.2, 1332.5 keV) sources. To characterize the radiation shielding properties of the samples, mass attenuation coefficient (μ/ρ), linear attenuation coefficient (μ), half-value layer (HVL), tenth-value layer (TVL), and effective atomic number (Z eff) parameters were calculated and compared with the values computed by WinXCOM software. It is revealed that theoretical and experimental results are in agreement and the radiation protection efficiency was enhanced with the increase of the dopant amount. Radiation effects on the structure and thermal stability of the samples were also studied by Attenuated total Reflectance-Fourier transform infrared spectroscopy (ATR-FTIR) measurements and thermogravimetric analysis (TGA) and differential scanning calorimetry (DSC). The spectroscopy results showed a remarkable decrease in the absorbance value of the composites after gamma irradiation. • PLA/Gd2O3 polymer composites with different percentages were prepared. • The radiation attenuation properties of these polymer composites were investigated. • Shielding properties of Gd2O3 (%16) is better than the other samples. • The absorbance signals in the ATR-IR spectra decreased after gamma irradiation. • It was observed that Gd2O3 improved the shape memory property of nanocomposites. [ABSTRACT FROM AUTHOR]

In this paper radiation shielding characteristics of tellurium glasses materials for radiation protection have been studied. The effect of different TiO 2 contents in 75TeO 2 -Na 2 O-(20-x) BaO-xTiO 2 (x = 0, 5, 10 and 15) glass samples are investigated on the shielding behavior, acoustic and physical parameters. However, some structural properties such as Molar Volume, Oxygen Molar Volume and Oxygen Packing Density are studied by using the Phy-X/PSD program and Monte Carlo simulations (with GEANT4 and MCNPX2.6.0 codes) in the photon energies of 0.284, 0.347, 0.511, 0.662, 0.826, and 1.173 MeV. The total trends of calculated LAC values in all four alloy glasses show that they are inversely proportional to the photon energy. It shows the abnormal behavior of Linear Attenuation Coefficient value at one point in low energies (sudden leapfrog peak between 0.3 MeV and 0.4 MeV) are shown by derived results by PhyX/PSD and GEANT4, which can be described by tellurium k-edge (in about 0.032 MeV). Finally, it can be informed that by increasing photon energy TNB-Ti15 sample has the best quality in radiation properties and a good choice for radiation protecting in various purposes such as medicine fields. • The radiation, of TeO 2 -Na 2 O-BaO-TiO 2 glass system are investigated. • Also, structural, mechanical, and acoustic features are investigated. • The effect of different TiO 2 and BaO concentrations on properties are illustrated. • We use the Phy-X/PSD and MCNP and GEANT4 toolkit and some theoretical models. [ABSTRACT FROM AUTHOR]

In the quest to probe the potential of (40-x)B 2 O 3 –39SiO 2 –(20+x)Bi 2 O 3 –1Dy 2 O 3 (BSBD1 –BSBD4) glasses, their interaction parameter with multispectral radiation is calculated, analyzed and presented in this report. The FLUKA code was used to simulate photons, charged particles (electrons, protons, α-particle, and carbon ions), and slow neutron cross sections of the glasses. In addition, the fissile and thermal neutron attenuation cross sections were evaluated through analytic expressions. The mass attenuation coefficient of the BSBD glasses varied from 0.0364 cm2/g to 68.9445 cm2/g for BSBD1, 0.0382 cm2/g to 80.1942 cm2/g for BSBD2, 0.0392 cm2/g to 87.5237 cm2/g for BSBD3, and 0.04001 cm2/g to 92.6780 cm2/g for BSBD4. Other photon attenuation parameters showed that the BSBD4 glass is the best photon attenuator. The range and stopping power of the charged particles also revealed that charged particle attenuation depends strongly on the density and Bi 2 O 3 quantity. The neutron absorbing/shielding ability of the glasses showed a contrasting trend compared to photons and charged particles. While BSBD2 was the best fast neutron absorber, BSBD1 on the other hand, showed greater resilience to thermal and slow neutrons. Based on the analyzed data analyzed in this study, the BSBD glasses showed great potential for radiation protection ability. • Radiation shielding and nuclear safety of BSBD glass system is reported. • Monte Carlo simulations are carried out. • A good agreement between the theory and the simulation. • BSBD1 is superior shielding system against thermal neutrons. • BSBD2 is superior shielding system against fast neutrons. [ABSTRACT FROM AUTHOR]

Radiation interaction parameters are important for exploring the technological relevance of materials in radiation environments. In this research paper, gamma-ray shielding efficacy of GeO 2 +B 2 O 3 +P 2 O 5 +ZnO magneto-optical glasses doped with Tb3+ and coded as GBPZT1-6 for Tb3+ doping concentrations ranging from 20 to 45 mol%, with a 5-mol% increment was investigated using theoretical and Monte Carlo simulation methods. The PHITS code and the Phy-X/PSD software was used to compute the mass attenuation coefficient (MAC) and other interaction quantities of the glasses for 0.015–15 MeV photons. Both methods' MAC data agree to within 2.90% of each other. At 0.015 MeV, the value of MAC is 59.9674 cm2/g, 64.1777 cm2/g, 67.6697 cm2/g, 70.6128 cm2/g, 73.1271 cm2/g and 75.2998 cm2/g for GBPZT1, GBPZT2, GBPZT3, GBPZT4, GBPZT5 and GBPZT6, respectively. The linear attenuation coefficients of the GBPZT glasses changed from 0.1340 to 247.5640 cm−1, 0.1490 to 286.8040 cm−1, 0.1650 to 326.6350 cm−1, 0.1790 to 365.7810 cm−1, 0.1990 to 413.9290 cm−1, and 0.2190 to 463.9450 cm−1 for GBPZT1, GBPZT2, GBPZT3, GBPZT4, GBPZT5, and GBPZT6. Comparatively, the photon attenuation abilities increase linearly as the density and Tb 2 O 3 content of the glass system increased. Hence, GBPZT6 has the highest mass and linear attenuation coefficients, while GBPZT1 has the least. The BPZT glasses have better photon absorbing capacities compared to ordinary concrete and some other conventional shielding materials, thus making them attractive choice in radiation protection functions. • Radiation shielding capacity of germinate glasses is estimated. • Monte Carlo simulations are carried out. • A good agreement between the theory and the simulation. • GBPZT6 glass system has a potential use in nuclear applications. [ABSTRACT FROM AUTHOR]

The present study aims to avoid contaminating the environment with some chemical compounds produced as a washing product after zirconium mineral digestion. Then, using the Na 2 SiO 2 obtained from the digestion process and other chemicals, two useful composites were created. These composites are glass powders doped by less than 12% Lead dinitrate (Pb(NO₃)₂). The structure and elemental chemical composition of the fabricated composites were investigated using the XRD diffractometer and energy-dispersive X-ray spectroscopy (EDX). The γ-photon shielding capacity of the synthesis's composites was simulated using the Monte Carlo simulation code. According to the findings of the simulation, at a -ray energy of 0.033 MeV, the linear attenuation coefficient is 8.81 and 5.55 cm−1 for the synthesized composite materials with Pb concentration of 7.59 and 11.65 wt%. Additionally, the linear attenuation coefficient values at 1408 MeV for the synthesized composite materials were reduced to 0.142 cm−1 and 0.123 cm−1. • Two glass powder composites were synthesized based on the Na2SiO2 produced. • The XRD and EDX were used to discover the structure of the fabricated composites. • The γ-ray shielding capacity was evaluated using the Monte Carlo simulation. • The γ-ray shielding capacities were enhanced with enrichment of the lead dinitrate. [ABSTRACT FROM AUTHOR]

Novel Glass system with a formula of xBaO.(30− x).Na 2 O.70B 2 O 3 (0 ≤x ≤ 30 mol%) have been prepared and examined. The BNaBa x -glass structure was used to estimate the influence of BaO addition on the density and molar volume. There is a linear increase in density with increasing BaO concentration. The molar volume varies oppositely. Furthermore, the impact of barium oxide on the gamma and neutron radiation shielding capacities of xBaO.(30− x).Na 2 O–70B 2 O 3 glasses have been investigated for radiation shielding applications. The μm: coefficient of mass attenuation for BNaBa-0, BNaBa-5, BNaBa-10, BNaBa-15, BNaBa-20, BNaBa-25, and BNaBa-30 glass samples were simulated using the Monte Carlo simulation FLUKA algorithm, in photon energy ranged 0.015MeV–15MeV, the resulting μ m simulated results were compared with the Phy-X/PSD platform. The T 1/2 : half-value layer, λ: mean free path, Z eff : effective atomic number, EBF: exposure, and EABF: energy absorption buildup factors of the BNaBa x -glass samples have been estimated. The results presented that a BNaBa-30-glass with a 30-mol.% concentration of BaO has the best gamma and neutron shielding capabilities than the other investigated BNaBa x -glass samples. • Gamma and neutron shielding properties of BaO–Na 2 O–B 2 O 3 have been studied. • The results were simulated at 0.015–15 MeV and compared with Phy-X/PSD values. • The BNaBa-30 has the best effectiveness shielding against gamma photons. • The results are useful in radiation protection of applications. [ABSTRACT FROM AUTHOR]

Present work is focused on experimentally exploring the radiation shielding and sensing properties of europium (Eu) doped bismo (Bi)-phosphate (P) glasses with different metal oxide (Cu O, Zn O, Sr O, Ba O, Pb O) contributions. Samples were synthesized via melt quenching method and glassy nature was verified using XRD characterization. Different radiation shielding and sensing parameters such as mass attenuation coefficient (μ m), optimum thickness range (x opt), effective atomic number (Z eff), electron density (N e), mean free path (mfp), half value layer (HVL) and tenth value layer (TVL) were obtained theoretically as preliminary data for preparing sample of required thickness. A special geometric setup consisting of Gammarad5, lead collimators and γ rays sources of Na22, Cs137 and Co60 were used to measure these parameters. Both, theoretical and experimental findings show good agreement within percentage deviation of ±4%. The μ m value tends to decrease with the increase in photon energy as well as with the replacement of lower atomic number metal oxide (MO) by comparatively higher atomic number MO in the glass system. The Z eff , N e and radiation protection efficiency (RPE) of the samples follow similar trend. Whereas thickness normalizing parameters (TNPs) viz HVL, mfp and TVL follows inverse trend. Among the synthesized glass samples, EuBiPPb possess highest values of density (4.76 g/cc), μ m , Z eff , N e and RPE with least thickness requirements. The work has been extended to compute and analyze exposure buildup factor (EBF) and energy absorption buildup factor (EABF) parameters too. The present results show significant potential of glass samples in shielding and sensing applications. • Synthesized Eu doped bi smo p hosphate glasses with Cu O/ Zn O/ Sr O/ Ba O/ Pb O. • Glassy nature of synthesized samples was verified using XRD characterization. • Radiation shielding/sensing properties were verified experimentally. • Both, theoretical and experimental findings show good agreement within ±4%. • EuBiPPb got higher values of ρ, μ m , Z eff , N e , RPE with least TNPs. [ABSTRACT FROM AUTHOR]

Novel shielding materials for photons based on silicon resin and WO 3 , PbO, and Bi 2 O 3 Micro and Nano-particles were designed and their mass attenuation coefficients were calculated using Monte Carlo (MC) method. Using lattice cards in MCNPX code, micro and nanoparticles with sizes of 100 nm and 1 µm was designed inside a silicon resin matrix. Narrow beam geometry was simulated to calculate the attenuation coefficients of samples against mono-energetic beams of Co 60 (1.17 and 1.33 MeV), Cs 137 (663.8 KeV), and Ba 133 (355.9 KeV). The shielding samples made of nanoparticles had higher mass attenuation coefficients, up to 17% relative to those made of microparticles. The superiority of nano-shields relative to micro-shields was dependent on the filler concentration and the energy of photons. PbO, and Bi 2 O 3 nanoparticles showed higher attenuation compared to WO 3 nanoparticles in studied energies. Fabrication of novel shielding materials using PbO, and Bi 2 O 3 nanoparticles is recommended for application in radiation protection against photon beams. [ABSTRACT FROM AUTHOR]

Following the rapid growing per capita income, a major portion of Bangladeshi dwellers is upgrading their non-brick houses by rod-cement-concrete materials and simultaneously curious to decorate the houses using luxurious marble stones. Present study was undertaken to investigate the gamma-ray attenuation co-efficient of decorative marble materials leading to their suitability as shielding of ionizing radiation. A number of commercial grades decorative marble stones were collected from home and abroad following their large-scale uses. A well-shielded HPGe γ-ray spectrometer combined with associated electronics was used to evaluate the mass attenuation coefficients of the studied materials for high energy photons. Some allied parameters such as half-value layer and radiation protection efficacy of the investigated marbles were calculated. The results showed that among the studied samples, the marble ‘Carrara’ imported from Italy is suitable to be used as radiation shielding material. [ABSTRACT FROM AUTHOR]

The probability of a photon interacting in a particular way with a given material, per unit path length, is usually called the linear attenuation coefficient (μ), and it is of great importance in radiation shielding. Plates of barite concrete with different thickness were fabricated in order to determining their mass attenuation coefficients at different energies. The plates were irradiated with ISO X-ray beams (N60, N80, N110 and N150), generated by Pantak HF320 X-ray equipment, at the IPEN laboratory. The mass attenuation coefficients of barite concrete have been measured using X-ray attenuation for different thicknesses of barite concrete qualities of the ISO. The attenuator material issued from different regions of Brazil. The experimental procedure in this research was validated by comparison between the experimental measurements of mass attenuation coefficients and coefficients determined by the same atomic composition, using as a tool to XCOM. The highest value of (μ/ρ) found experimentally was in the energy of 48 keV, in ISO 60 N quality, being 1.32(±0.49) for purple barite; 1.47(±0.41) for white barite and 1.75(±0.41) for cream barite. The determination of the chemical composition of the barite samples was of fundamental importance for the characterization of these materials. It can be seen that both calculated and measured data for the linear attenuation coefficients increase with the increasing materials density, as it is expected. It can be concluded that the photon attenuation coefficients depends on the photon energy and the materials density is the main contribution to the photon attenuation coefficients, which is important for radiation shielding. [ABSTRACT FROM AUTHOR]

Radiation has many beneficial applications, particularly in healthcare and medicine. However, due to its hazards and adverse effects on human health, it is important to investigate materials for radiation shielding and protection purposes. In the present work, the electronic cross-sections, atomic cross-section, transfer cross-sections, Compton mass attenuation coefficients, and mass-energy transfer coefficients of 83 Bi209, 74 W184, 50 Sn119, ZnS, and CaCO 3 have been investigated using γ-ray energies ranging from 0.5 MeV to 18 MeV, by application of the Klein-Nishina formula. The results show that the electronic, atomic, and energy transfer cross-sections decrease with increasing γ-ray energy. The mass attenuation coefficients were observed to increase as the Z/A ratio increased. The mass energy-transfer coefficients decreased with an increasing Z/A ratio The Z/A ratio is an essential characteristic of a shielding material because it affects the scatter and absorption of γ-ray energy after a collision with an atom. The materials are found to be very suitable for radiation shielding and protection purpose. The investigated elements and compounds can also be used as lead alternative materials, to avoid environmental toxicity. • Klein-Nishina characterization of Bi-209, W-184, Sn-119, ZnS, and CaCO3. • Investigation of the interaction cross-sections. • Study of the Compton coefficients as a function of photon energies. • Radiation shielding and protection abilities of the investigated materials. • Environmental safety and alternative materials to replace lead. [ABSTRACT FROM AUTHOR]

In the current investigation, the gamma radiation shielding abilities, structure, and thermal and optical properties of Polylactic acid PLA have been tried to be developed by introducing tungsten trioxide WO 3. PLA/WO 3 composites were fabricated by a solution mixing method at different weights percent (1%, 3%, 5%, and 7%). SEM indicates the good dispersion of WO 3 in the PLA matrix, and the X-ray diffraction (XRD) pattern displays the existence of recognizable peaks for PLA and WO 3. The thermal properties were investigated by thermo-gravimetric analysis (TGA), which enhances the thermal stability of the PLA/WO 3 composites more than pure PLA. The transmittance decreases with increasing the WO 3 content in the PLA matrix while the absorption and extinction coefficients α and k as well as the refractive index, rise with the increase of the WO 3 content in the PLA matrix. The radiation shielding parameters have been experimentally reported. The equipment used in the experiment consisted of a NaI detector as well as a variety of radioactive point sources that released photons with energy of 80, 238, 356, 662, 1173, 1333, and 2164 keV, respectively. Examining the linear attenuation coefficient (μ), the half-value layer (T 0.5), and the radiation protection effectiveness of the PLA/WO 3 composites was done in order to investigate the gamma radiation shielding capabilities of the materials (RPE). Pure PLA (free WO 3) was found to have the lowest μ values, and it was discovered that increasing the WO 3 content led to an improvement in the photon attenuation competency of the present epoxy. The T 0.5 lengths of the PLA/WO 3 composites were lowered when WO 3 was added. This verified that adding WO 3 increases the radiation absorption capabilities of the PLA/WO 3 composites. The four different energies were tested. Based on the findings, it is possible to draw the conclusion that non-toxic, naturally occurring composites that are low in cost and have a high WO 3 content could play an important part in enhancing the gamma-ray shielding capabilities of PLA/WO 3 composites for low-energy radiation applications, which can used as protective cover for solar cell against harm radiation. • Thermal, optical, and gamma attenuation of polylactic acid tungsten were studied. • 7WO 3 has the best effectiveness shielding against gamma photons. • The results are useful in many applications, including radiation protection. [ABSTRACT FROM AUTHOR]