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This research examines the effects of varying titanium oxide (TiO 2) concentrations in glass formulations, denoted as [(53-x)B 2 O 3 –7MgO–20BaF 2 –20Na 2 O-xTiO 2 ] or BMBNTix, where x varies from 0 to 8 mol% in 2 % increments, on optical properties and radiation shielding effectiveness. Using MCNP5 (MC) Monte Carlo simulations and Phy-X software, this study assesses a range of photon energies from 0.015 to 15 MeV, focusing on key radiation shielding metrics such as the linear attenuation coefficient (μ), the half-value layer (HVL), and the tenth value layer (TVL). The results reveal a clear relationship between increased TiO 2 levels in the BMBNTix glasses and improved radiation shielding performance. Notably, the linear attenuation coefficient (μ) steadily climbs from BMBNTi0 to BMBNTi8, highlighting the beneficial effect of a TiO 2 addition to the material's ability to attenuate radiation. This trend is inversely mirrored in HVL values, which decrease from 0.010 cm for BMBNTi0 to 7.646 cm for BMBNTi8, reflecting enhanced shielding efficiency over the entire studied photon energy range. The effective atomic number (Z eff) also showcases a dynamic range from 40.793 to 15.101, suggesting a complex relationship between TiO 2 content and photon interaction. Moreover, the study indicates a slight but consistent increase in the fast neutron removal cross-section (Σ R) from 0.104 cm−1 for BMBNTi0 to 0.106 cm−1 for BMBNTi8, pointing to improved neutron shielding with greater Ti and oxygen content in the glass. These insights highlight the potential of TiO 2 -enriched magnesium borate glasses as superior options for effective photon and neutron shielding, particularly in nuclear medicine, emphasizing their role in enhancing radiation safety measures. [ABSTRACT FROM AUTHOR]

As the utilization of nuclear energy continues to expand, there is a growing focus on the development of lightweight and efficient nuclear shielding composites. In this paper, novel WB X /Al (x = 1, 2, 4) composites were designed based on shielding performance. The effects of reinforcement type, volume fraction, and material thickness on the 60Co and 137Cs γ-rays, fast and thermal neutron shielding performances were simulated. The results show that WB/Al composites offer better development potential compared to WB 2 /Al or WB 4 /Al composites. Additionally, a predictive model for the γ-ray shielding effectiveness of WB/Al composites, based on the areal density of tungsten, was proposed. The fabrication process involved mechanical ball milling and spark plasma sintering to fabricate 30 vol% WB/Al composites, with optimization of ball milling time, sintering temperature, and holding time. As a result, a novel nuclear radiation protection composite with uniform composition, a relative density of 97 %, and flexural strength of 527 MPa was acquired. [ABSTRACT FROM AUTHOR]

NASA HRP considers developing radiation protection for human space flight and surface habitation as one of the critical technologies for successful deep space exploration. Although the danger of radiation exposure is recognized as a potential show-stopper for deep space exploration, and radiation effects on humans are now understood better than before, shielding strategies for different stages of space flight and habitation are still not addressed in a fully comprehensive manner. Habitats and all space structures planning and design are guided by essential requirements and constraints associated with safety, manufacturing and assembly procedures, propellant and construction costs, maintenance, crew and/or passenger satisfaction. This paper reviews radiation shielding options for space habitats and discusses their feasibility in relation to habitability needs, including the potential for outside viewing in distinct types of space habitats. Typically, radiation protection depends on the thickness of the exterior structure that consists of a pressurized shell, multilayer insulation (MLI) and any applied radiation shielding material. The mass of the external protection shell is the primary factor of radiation shielding effectiveness. Nevertheless, using materials with low atomic numbers (e.g., Boron (5), Carbon (6), and H 2 O) helps to lower secondary radiation hazards. Water, which is rich in hydrogen and has the lowest atomic number, can also be used for other mission needs. Other materials, including biomaterials, can be considered when their inclusion in the structure is possible and appropriate. The paper presents a comprehensive strategy for radiation shielding selection that includes investigation of complications associated with a type of space habitat structure, mission needs, duration, destination, and crew requirements. The approach presented in the paper aims to establish an evaluation methodology for defining the feasibility of the integration of diverse radiation shielding types into habitat structures. The paper summarizes by reviewing radiation shielding proposals with selected case studies including water, regolith, hydrogen-rich polymers, biotechnology, polyethylene/boron nitride composites, and active strategies. • Case studies of different materials and methods used for radiation shielding purposes, • Pros and cons of using referenced materials and methods in habitat architectures • Criteria for evaluation and selection of appropriate radiation protection strategy • Comparisons of radiation shielding methods by space architecture categories • Comparisons of radiation shielding methods by structural integration options [ABSTRACT FROM AUTHOR]

This study evaluated the efficacy of a novel comprehensive shield designed to minimize radiation exposure (RE) to Physicians performing coronary and structural heart procedures. The Protego™ radiation shielding system (Image Diagnostics Inc., Fitchburg, Ma) is designed to provide comprehensive protection from RE and has been State certified sufficient to allow operators to perform procedures without orthopedically burdensome lead aprons. This single center two-group cohort study assessed the efficacy of this shield in a large number of cardiac procedures (coronary and structural), comparing operator RE compared to standard protection methods (personal lead apparel and "drop down" shield). The Protego™ system reduced operator RE by 99 % compared to Standard Protection. RE was significantly lower at both "Head" level by thyroid median dose 0.0 (0.0, 0,0) vs 5.7 (2.9, 8.2) μSv (p < 0.001), as well as waist dose 0.0 (0.0, 0.0) vs 10.0 (5.0, 16.6) μSv (p < 0.001). "Zero" Total RE was documented by Raysafe™ in 64 % (n = 32) of TAVR cases and 73.2 % (n = 183) of the coronary cases utilizing Protego™. In contrast, standard protection did not achieve "Zero" exposure in a single case. These dramatic differences in RE were achieved despite higher fluoroscopy times in the Protego™ arm (11.9 ± 8.6 vs 14.3 ± 12.5 min, p = 0.015). Per case procedural exposure measured by Dose Area Product was higher in the Protego™ group compared to standard protection (115.4 ± 139.2 vs 74.9 ± 69.3, p < 0.001). The Protego™ shield provides total body RE protection for operators performing both coronary and structural heart procedures. This shield allows procedural performance without the need for personal lead aprons and has potential to reduce catheterization laboratory occupational health hazards. • The catheterization laboratory predisposes to occupational health hazards. • Lead apron use underlies the prevalence of orthopedic maladies in interventionists. • Until recently, there have been few advances in catheterization laboratory protection technology. • Novel comprehensive shielding systems have been validated in early studies to provide excellent radiation protection. • Recent system refinements offer potentially even greater degrees of protection when compared to standard protection. [ABSTRACT FROM AUTHOR]

The scarcity of research on the shielding properties of spinel ferrites underscores the necessity for more rigorous investigations. Consequently, this study introduces a facile synthesis method for Co, Cu, and Sm spinel nanoferrites (referred to as CCS nanoferrites) using the citrate combustion technique. The investigation focuses on their mechanical, dielectric, and gamma-ray shielding parameters. Gamma-ray shielding features are obtained theoretically via the Phy-X database. The particle size, nature, and distribution of the present CCS nanoferrites were analyzed using HR-TEM microscopy. HR-TEM results reveal both the spherical shapes and the aggregation of nanoparticles. These observations can be attributed to the interplay of high surface energy and magnetic interactions among the components of the CCS nanoferrites. The Co 0.5 Cu 0.5 Sm 0.15 Fe 1.85 O 4 nanoferrite exhibits an optimal dielectric constant value of 4587, with an enhanced ratio of 1618% compared to the pristine CCS0 sample. Additionally, it demonstrates an optimal conductivity of 38.59 μ (Ω·m)−1, with an enhanced ratio of 1105%. Furthermore, the loss is reduced to 2.65, showing an improvement ratio of 54% compared to the pristine nanoferrite at room temperature and 50 Hz. Moreover, the longitudinal modulus, shear modulus, Young's modulus, and bulk modulus of the nanoferrite Co 0.5 Cu 0.5 Sm 0.15 Fe 1.85 O 4 were increased from 1.79 to 4.96 GPa, 0.32–0.93 GPa, 0.88–2.56 GPa, and 1.37–3.73 GPa, respectively, when compared to the pristine sample. The comparative study of half-value layers at 0.662 MeV revealed that CCS nanoferrites exhibit smaller half-value layers than common radiation shielding materials. Additionally, the study highlighted the enhanced radiation shielding performance of the nanoferrites. Concerning the dielectric, mechanical, and ionizing radiation shielding properties of the CCS spinel nanoferrites, the CCS5 (with the highest Sm content) has the optimum ionizing radiation shielding ability with the highest dielectric and mechanical parameters compared to the other samples. The implications of these findings extend to potential applications in biomedicine, radiation protection, and the optimization of electronic devices operating in radiation fields. [ABSTRACT FROM AUTHOR]

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

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

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

In the study, four novel Ni-based superalloys were produced and radiation shielding efficiencies of the alloys were investigated. Ni, Fe, Mo, Cr, Ta and W were selected for developing NiyTaxW7Cr7Fe7Mo7B7 (x = 0–20; y = 65–45%) alloys based on Ni. Phy-X/PSD code was used to calculate the attenuation parameters. Results were compared by XCom and some reported values in the literature for a meaningful evaluation. In addition, experimental results were provided based on x-ray diffraction, scanning electron microscopy, energy-dispersive spectroscopy and electron paramagnetic resonance spectroscopic techniques. It is obtained that the crystallite sizes of the alloys calculated based on the Debye Scherrer equation vary between 44.13 and 68.33 nm. The mapping images and EDS analysis indicate that the Ni3 alloy has the most homogeneous structure. There is a direct relation between the amount of Ta and the radiation protection capability of the alloys. Newly fabricated Ni-based superalloys have good shielding properties and the usability of the alloys can be recommended as effective shielding materials in radiation-related applications. [ABSTRACT FROM AUTHOR]

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

To characterize an electron beam, visible synchrotron light is often used and dedicated beamlines at synchrotron sources are becoming a more common feature as instruments and methods for the diagnostics are, along with the accelerators, further developed. At KARA (Karlsruhe Research Accelerator), such a beamline exists and is based on a typical infrared/visible-light configuration. From experience at such beamlines no significant radiation was expected (dose rates larger than 0.5 µSv h-1). This was found not to be the case and a higher dose was measured which fortunately could be shielded to an acceptable level with 0.3 mm of aluminium foil or 2.0 mm of Pyrex glass. The presence of this radiation led to further investigation by both experiment and calculation. A custom setup using a silicon drift detector for energy-dispersive spectroscopy (Ketek GmbH) and attenuation experiments showed the radiation to be predominantly copper K-shell fluorescence and is confirmed by calculation. The measurement of secondary radiation from scattering of synchrotron and other radiation, and its calculation, is important for radiation protection, and, although a lot of experience exists and methods for radiation protection are well established, changes in machine, beamlines and experiments mean a constant appraisal is needed. [ABSTRACT FROM AUTHOR]

Experiments have assessed various polymer composites for radiation shielding in diverse applications. These composites are lighter and non-toxic when compared to lead (Pb), making them particularly effective in diagnostic imaging for shielding against low-energy photons. This study demonstrates the fabrication of four composites by combining a base material, specifically a high-density polyethylene (HDPE) polymer, with 10% and 20% silicon (Si) and silicon carbide (SiC), respectively. Additionally, 5% molybdenum (Mo) was incorporated into the composites as a heavy metal element. The composites obtained were fabricated into 20 disks with a uniform thickness of 2 mm each. Discs were exposed to radiation from a low-energy X-ray source (32.5–64.5 keV). The chemical and physical properties of composites were assessed. The shielding ability of samples was evaluated by determining the linear and mass attenuation coefficients (μ and μm), radiation protection efficiency (RPE), half-value layer (HVL), and mean free path (MFP). According to our findings, supplementing HDPE with additives improved the attenuation of beams. The μm values showed that composite X-ray shielding characteristics were enhanced with filler concentration for both Si and SiC. Polymer composites with micro-molecule fillers shelter X-rays better than polymers, especially at low energy. The HVL and MFB values of the filler are lower than those of the pure HDPE sample, indicating that less thickness is needed to shield at the appropriate energy. HC-20 blocked 92% of the incident beam at 32.5 keV. This study found that increasing the composite sample thickness or polymer filler percentage could shield against low-energy radiation. [ABSTRACT FROM AUTHOR]

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

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

Introduction Diagnostic radiology in the deployed military environment (in-theater diagnostic radiology) was greatly improved in the early 1990s with the addition of CT systems installed in military-grade one-sided expandable ISO-shelters. These shelters were provided with limited radiation shielding by several flexible lead curtains covering only a small portion of the shelter walls, necessitating placement of deployed CT systems at substantial distances from the field medical facility to limit exposures to personnel from secondary radiation. The newest generation deployable CT system is housed in a two-sided ISO-shelter with radiation shielding applied to the shelter walls. To ensure compliance with military and national standards for protection against ionizing radiation, we developed a simple method to calculate safe distances based on workload, frequencies of the various CT exams performed, and occupancy of controlled and uncontrolled areas. Materials and Methods Calculation of radiation air kerma rates outside a two-sided CT ISO-shelter was developed using guidance from the National Council on Radiation Protection and Measurements Report No. 147. The simplified formula included measured radiation transmission factors for the ISO-shelter wall and installed shielding, occupancy factors, fraction of all CT exams that covered the chest, abdomen, and/or pelvis, total number of CT exams per week, and shielding design goals for controlled and uncontrolled areas. The formula was modified subsequently to account for whole-body CT exams expected during armed conflict. Results Calculated safe distances revealed that the shielded two-sided CT ISO-shelter can be positioned much closer to the surgical shelters of the field medical unit than the previously unshielded one-sided CT ISO-shelter. Tables of safe distances for controlled and uncontrolled areas for the two medical support environments of disaster relief/peacekeeping and combat are provided. For example, for a controlled area at 100% occupancy when 300 CT exams per week are performed and 50% of those exams are of the chest, abdomen, and/or pelvis, the safe distance between the nearest surgical shelter and the shielded CT ISO-shelter is 2.1 m. By comparison, the safe distance for an unshielded CT ISO-shelter is 8.5 m under the same conditions. For lower occupancy factors and lower weekly workload, safe distances from the nearest surgical shelter are often negligible. Conclusions The shielding in the new deployable CT ISO-shelter substantially reduces the distance between it and the surgical shelters of the field medical unit necessary to ensure radiation safety. Safe distances depend on several factors including workload, types and frequencies of CT exams, occupancy factors, and classification of the area around the ISO-shelter, i.e. controlled and uncontrolled. [ABSTRACT FROM AUTHOR]

Introduction: Lead shields are often used to attenuate ionising radiations. However, to make lighter, recyclable and more efficient shields compared to lead, combinations of new metallic compounds together with polymer, for example, flexible polyvinyl chloride (PVC) have been developed recently. In this study, the capabilities of non‐lead radiation shields made of one or two metallic compounds and polymer were evaluated. Methods: Monte Carlo (MC)‐based BEAMnrc code was used to build a functional model based on a Philips X‐ray machine in the range of radiographic energies. The MC model was then verified by IPEM Report 78 as a standardised global reference. The MC model was then used to evaluate the efficiency of non‐lead‐based garments made of metallic compound and polymer (MCP) including BaSO4‐PVC, Bi2O3‐PVC, Sn‐PVC and W‐PVC, as well as dual‐metallic compounds and polymer (DMCP) including Bi2O3‐BaSO4‐PVC, Bi2O3‐Sn‐PVC, W‐Sn‐PVC and W‐BaSO4‐PVC. The absorbed doses were determined at the surface of a water phantom and compared directly with the doses obtained for 0.5 mm pure lead (Pb). Results: Bi2O3‐BaSO4‐PVC and W‐BaSO4‐PVC were found to be efficient shields for most of the energies. In addition to the above radiation shields, Bi2O3‐Sn‐PVC was also found to be effective for the spectrum of 60 keV. Bi2O3‐BaSO4‐PVC as a non‐lead dual metals‐PVC shield was shown to be more efficient than pure lead in diagnostic X‐ray range. Conclusion: Combination of two metals‐PVC, a low atomic number (Z) metal together with a high atomic number metal, and also single‐metal‐PVC shields were shown to be efficient enough to apply as radiation protection shields instead of lead‐based garments. [ABSTRACT FROM AUTHOR]

Radiation is useful but can be harmful to humans if used carelessly. Therefore, radiation protection equipment is necessary for workers. In this paper, we aim to study a cement composite with BaSO4/Bi2O3 for protection against X-rays and gamma rays. The shielding ability was measured using a diagnostic X-ray with energies of 60–120 keV and gamma rays of Cs-137, Ba-133, Co-57 and the morphology structure was determined including radiation protection properties. The results showed that Portland cement with a high concentration of BaSO4/Bi2O3 had the ability to absorb radiation from X-rays in the range of 95.54–99.87% and gamma energy in the range of 93.37–98.88%. Moreover, the composite of BaSO4/Bi2O3 induced a homogenous structure of Portland cement possibly affecting the strength of the material. In addition, Portland shielding can be designed for use in related applications in various energy ranges including ones that are environmentally friendly and suitable for the development of radiation protection in the future. [ABSTRACT FROM AUTHOR]

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

TRIPOLI-4® is a general-purpose Monte Carlo radiation transport code developed by the Service d'Études des Réacteurs et de Mathématiques Appliquées at CEA-Saclay. It uses continuous-energy nuclear data to simulate neutron, photon, electron, and positron transport in fields like radiation shielding, reactor physics, and nuclear criticality safety. To study radiation protection dosimetry in human tissues and organs, male and female adult computational phantoms from the Medical Internal Radiation Dose–Oak Ridge National Laboratory phantoms family and the International Commission on Radiological Protection (ICRP) publication 110 were recently modeled and calculated using the geometry options of TRIPOLI-4. To easily use the ICRP 110 voxel-based phantoms in different exposure scenarios, a newly developed phantom option is available in TRIPOLI-4 and its display tool T4G. This new phantom option is helpful for modeling one or more phantoms and for improving calculation performance in real irradiation environments. The 2020 published pediatric computational reference phantoms are accessible from ICRP publication 143. Male and female pediatric phantoms are also verified with the new T4G tool and TRIPOLI-4 code. This paper reports on recent works using TRIPOLI-4 on adult and pediatric computational phantoms. The modeling methods of stylized and voxel-based phantoms, the graphic displays of modeled phantoms with T4G, and the verification procedures for single-phantom and two-phantom application cases are presented. Validation for external and internal dosimetry calculations has been performed. Calculation results on organ dose S values for nuclear medicine applications are presented for single female and single male voxel phantoms using 131I and 177Lu radiation sources. Effective dose calculations for two-phantom cases using 99mTc and 18F sources are compared with traditional H*(10) calculations from nuclear medicine patient to patient caregiver. [ABSTRACT FROM AUTHOR]

Space exploration requires the use of suitable materials to protect astronauts and structures from the hazardous effects of radiation, in particular, ionizing radiation, which is ubiquitous in the hostile space environment. In this scenario, polymer-based materials and composites play a crucial role in achieving effective radiation shielding while providing low-weight and tailored mechanical properties to spacecraft components. This work provides an overview of the latest developments and challenges in polymer-based materials designed for radiation-shielding applications in space. Recent advances in terms of both experimental and numerical studies are discussed. Different approaches to enhancing the radiation-shielding performance are reported, such as integrating various types of nanofillers within polymer matrices and optimizing the materials design. Furthermore, this review explores the challenges in developing multifunctional materials that are able to provide radiation protection. By summarizing the state-of-the-art research and identifying emerging trends, this review aims to contribute to the ongoing efforts to identify polymer materials and composites that are most useful to protect human health and spacecraft performance in the harsh radiation conditions that are typically found during missions in space. [ABSTRACT FROM AUTHOR]

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

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

The radiological protection has the purpose of safeguarding the physical well-being of the user, preventing exposure to detrimental levels of ionizing radiation. This study introduces a novel, cost-effective category of lead-free elastomeric material designed for radiation shielding. The filler compounds utilized are notably lighter than conventional lead-based materials, enhancing user ergonomics during application. They comprise of a blend of barium sulfate combined or not with magnesium oxide with addition-cure liquid silicone rubber. To ensure the effectiveness of the radiation shielding, X-ray transmission measurements were performed for the different thicknesses of the materials and the results compared with Monte Carlo simulations. Additionally, the physical properties of the new materials, such as density, homogeneity, tensile strength, viscosity, and wettability, were also evaluated. The findings indicate that both materials fulfill the requirement for application in radiation protection garments. [ABSTRACT FROM AUTHOR]

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

Using the powder metallurgy, TiO 2 -doped TV screen glass ceramic samples were prepared with TiO 2 concentrations of 0 (S-TV), 10 (S-TV/Ti10), and 20 (S-TV/Ti20) wt%. The TV screen glass was collected from a damaged TV's CRT. The fabricated materials were investigated for their physical, structural, and radiation-shielding attributes. The chemical composition of the prepared glasses was analysed with the aid of the X-ray fluorescence (XRF) method. The crystalline phase and microstructure of the glass ceramics were studied through the X-ray diffraction (XRD) method and scanning electron microscope (SEM), respectively. The density and Vickers hardness of the sample were determined by the Archimedes method and a micro hardness tester, respectively. The absorption parameters of electrons, protons, alpha particles, carbon ions, fast neutrons, and thermal neutron were calculated from various software and analytic expressions. The XRD spectra of the samples showed the presence of distinct crystalline peaks associated with TiO 2 , SiO 2 , and Ba 2 SiO 4. The SEM images revealed that crystalline structures nucleated and increased with coarser crystalline grains when the amount of TiO 2 was increased. The densities of the glass ceramics were 2.525, 2.546, and 2.285 g/cm3 for the S-TV, S-TV/Ti10, and S-TV/Ti20 samples, respectively while the corresponding Vickers hardness values were 495, 540, and 578 HV. The projected range of electrons, protons, alpha particles, and heavy carbon ions were within the limits 2.78–32182.18 μm, 0.215–1400 μm, 0.154–130.54 μm, and 0.053–14.10 μm in S-TV, 2.76–31991.36 μm, 0.205–1320 μm, 0.147–122.05 μm, and 0.049–13.11 μm in S-TV/Ti10, and 2.84–32824.95 μm, 0.212–1360 μm, 0.151–125.55 μm, and 0.051–13.45 μm in S-TV/Ti20, respectively. Among the three samples, S-TV was the best thermal neutron absorber, while S-TV/Ti10 is most effective in slowing down fast neutrons. The optimum TiO 2 doping content for enhancing the charged particle and fast neutron moderating abilities of TV screens is 10 wt%. [ABSTRACT FROM AUTHOR]

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

In radiology, radiation shielding is important for protection especially with diagnostic radiation, such as diagnostic X-ray, because radiation exposure can damage cellular DNA. Currently, lead is the most common radiation shielding but it poses environmental hazards due to its toxicity. This research aims to study a non-lead radiation shielding and to evaluate its effectiveness of radiation protection. We studied radiation absorption properties from primary and secondary radiations from shielding composed of silicone rubber and BaSO4 and Bi2O3 in different proportions. The results showed that the shielding material at 70% BaSO4 and Bi2O3 has the ability to reduce radiation doses from 120 kVp X-rays and has absorption properties of 90.19, 94.87% in primary and 92.72, 97.48% in secondary radiation. In addition, the silicone rubber shielding materials mixed with BaSO4 and Bi2O3 are environment-friendly, flexible and have great shielding performance in reducing diagnostic X-ray exposure. [ABSTRACT FROM AUTHOR]

Passive radiation shielding alone cannot provide adequate protection for astronauts on long-term, deep-space missions. High atomic number and energy (HZE) ions, and/or their secondaries, can penetrate any realistic mass shielding for long-term deep-space missions and cause damage to cells via direct energy deposition and/or through the production of secondary particles and fragmented nuclei. Active shielding, or the use of electromagnetic fields to deflect or stop incoming ions before reaching the spacecraft, has gained substantial attention over the last decade as a way to augment passive shielding. Recently, a mathematical relationship between a dimensionless scaling parameter characterizing the active shield and the incoming ion and a protected area formed on a downstream detector due to the deflection of HZE ions by the applied field was validated in Earth-based laboratory conditions. In the present work, the mathematical formulation is extended to relate electrostatic shielding efficacy with the ability to deflect positively charged ions with parameters relevant to space applications. Additionally, a modified scaling parameter is formulated to characterize the shielding efficacy of a "family" of electrostatic active shielding configurations for reducing flux density for a space-relevant isotropic source of energetic protons. The results of this study demonstrate a strong correlation among dimensionless scaling parameters and shielding efficacy metrics for space radiation-relevant HZE ions in beam and isotropic angular distributions. Furthermore, it establishes a framework for optimizing design of three-dimensional electrostatic shielding configurations to improve space radiation protection for astronauts on exploration-class missions. [ABSTRACT FROM AUTHOR]

Ionizing radiation is becoming increasingly prevalent in various applications on Earth and in space. This study evaluates the radiation shielding performance of five quaternary glass systems with different chemical compositions of 60SiO 2 -35Pb 3 O 4 -(5-x)ZnO-xWO 3 (0 ≤ x ≤ 5 mol%) using theoretical software and Monte Carlo simulations. The study calculates various shielding parameters, including attenuation coefficients, mean free path, half value layer, tenth value layer, effective atomic number, electron density, and build-up factors, for the photon energy range of 1 keV to 100 GeV. PZSW3 and PZSW5 show comparable attenuation coefficients at low and high energy levels, which are higher than the other selected samples. Additionally, PZSW5 has a neutron removal cross-section of 0.120 cm−1, slightly less than PZSW4's 0.122 cm−1 and greater than the other three samples. On average, PZSW5 (60SiO 2 -35Pb 3 O 4 -5WO 3) exhibits greater radiation attenuation than other samples and most of the compared 19 samples in terms of shielding parameters. The study also analyzes the trajectories of 10 5 photons in the system and finds that PZSW5 has the most effective radiation protection capability among the glass composites studied. [ABSTRACT FROM AUTHOR]

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

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

This study aims to investigate the impact of CeO2 content and particle size on the radiation shielding abilities of polydimethylsiloxane, also known as silicon rubber (SR). We prepared different SR samples with 10, 30, and 50% of micro and nano CeO2 and we measured the linear attenuation coefficient (LAC) for these samples. We found that the LAC of the SR increases by increasing the CeO2 and all prepared SR samples had higher LACs than the pure SR. We examined the effect of the size of the particles on the LAC and the results demonstrated that the LAC for nano CeO2 is higher than that of micro CeO2. We investigated the half value layer (HVL) for the prepared SR samples and the results revealed that the SR with 10% micro CeO2 had a greater HVL than the SR with 10% nano CeO2. The HVL results demonstrated that the SR containing nanoparticles had higher attenuation effectiveness than the SR with micro CeO2. We also prepared SR samples containing CeO2 in both sizes (i.e., micro and nano) and we found that the HVL of the SR containing both sizes was lower than the HVL of the SR with nano CeO2. The radiation protection efficiency (RPE) at 0.059 MeV for the SR with 10% micro and nano CeO2 was 94.2 and 95.6%, respectively, while the RPE of SR containing both sizes (5% micro CeO2 + 5% micro CeO2) was 96.1% at the same energy. The RPE results also indicated that the attenuation ability was improved when utilizing the micro and nano CeO2 as opposed to the micro CeO2 or nano CeO2 at 0.662, 1.173, and 1.333 MeV. [ABSTRACT FROM AUTHOR]

We examine four systems with different chemical compositions Pb-50Sn-0.5CuO, Pb-50Zn-0.5CuOx, Sn-50Bi-0.5CuO and Sn-50Zn-0.5CuO prepared by the melt-spun technique. To obtain the morphological features of the prepared alloys, a scanning electron microscope, SEM, was utilized. The prepared samples were analyzed by using an analytical XRD tool to verify the lattice distortion, different identification phases and crystallite size for the examined alloys. The mechanical investigations including basic parameters such as microhardness, elastic moduli, ultimate tensile strength and toughness were analyzed using the Vickers microhardness technique and tensile test machine. The results showed that Pb-free alloys doped with CuO NPs had proper mechanical properties and shielding capability for as-prepared systems. It may be due to refined microstructures that could obstruct the dislocation movement. The radiation shielding parameters of as-prepared alloys are studied at photon energies of 0.511, 0.662 and 1.275 MeV. The lead-free alloys' doped CuO NPs can be superior shielding material than those of lead alloys. Therefore, the results indicated that the lead-free alloy compositions doped with CuO nanoparticles are recommended to exhibit maximum shielding efficiency. Hence, the Sn-50Bi-0.5CuO and Sn-50Zn-CuO alloys had excellent potential and could be applied as radiation shielding materials. [ABSTRACT FROM AUTHOR]

Lately, high-density glass systems have attracted the utmost attention of the scientific community for radiation protection purposes. With this motivation, the present study aims at preparing the boro-tellurite (BT) glass systems with (5 + x)B 2 O 3 + (95-x)TeO 2 where x equals 0, 5, 10, and 15 mol%. For synthesizing the glass series coded B5T95 to B20T80, the traditional melting technique via a lift furnace was carried out. After that, the synthesized samples were thoroughly explored by evaluating physical, structural, thermal, and radiation protection aspects for revealing the differences in the parameters. According to the physical property findings, it was evident that the samples from B5T95 to B20T80 had density values of 5.4751, 5.3214, 5.1711, and 4.9982 g cm−3, respectively. In addition to physical properties, the presence of an amorphous structure was visible in each glass series from B5T95 to B20T80 samples with regard to the XRD patterns. Furthermore, FT-IR spectra clearly revealed the existence of different bond types, including B–O, B–O–B, Te–O, Te–O–Te, and O–Te–O. On the other hand, glass transition temperatures for B5T95, B10T90, B15T85, and B20T80 glasses were found to be 322, 336, 334, and 341 °C, respectively, according to the typical DSC curves. Besides that, the crystalline phase (α-TeO 2) in sample B20T80 was directly developed from the glass during heat treatment. Lastly, the impact of B 2 O 3 on the BT glass systems' radiation shielding efficiency was evaluated using Phy-X/PSD software, and the findings were compared with the alternative ones. All in all, the authors strongly agree that the findings are very critical for enhancing radiation shielding glass systems. [ABSTRACT FROM AUTHOR]

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

Solar cells in superstrate arrangement need a protective cover glass as one of its main components. The effectiveness of these cells is determined by the cover glass's low weight, radiation resistance, optical clarity, and structural integrity. Damage to the cell covers brought on by exposure to UV irradiation and energetic radiation is thought to be the root cause of the ongoing issue of a reduction in the amount of electricity that can be generated by solar panels installed on spacecraft. Lead-free glasses made of xBi2O3–(40 − x)CaO-60P2O5 (x = 5, 10, 15, 20, 25, and 30 mol%) were created using the usual approach of melting at a high temperature. The amorphous nature of the glass samples was confirmed using X-ray diffraction. At energies of 81, 238, 356, 662, 911, 1173, 1332, and 2614 keV, the impact of various chemical compositions on gamma shielding in a phospho-bismuth glass structure was measured. The evaluation of gamma shielding revealed that the results of the mass attenuation coefficient of glasses increase as the Bi2O3 content increases but decrease as the photon energy increases. As a result of the study conducted on the radiation-deflecting properties of ternary glass, a lead-free low-melting phosphate glass that exhibited outstanding overall performance was developed, and the optimal composition of a glass sample was identified. The 60P2O5–30Bi2O3–10CaO glass combination is a viable option for use in radiation shielding that does not include lead. [ABSTRACT FROM AUTHOR]

Background: 177Lu prostate-specific membrane antigen (PSMA) therapy prolongs survival for some prostate cancer patients. To adopt this technique, institutions may need to evaluate the suitability of existing infrastructure. Purpose: Develop a methodology to determine whether existing facilities can accommodate a 177Lu-PSMA therapy program. Methods: Room suitability is defined by both the ability to accommodate 177LuPSMA therapy workflow and to provide appropriate radiation shielding. Two methods of shielding calculation were performed: (1) National Council on Radiation Protection and Measurements report 151 (NCRP-151), with workload defined in terms of the activity of 177Lu administered, and (2) using the RadPro shielding calculator. This methodology was applied to 131I therapy, PET-CT uptake, PET-SPECT injection, and orthovoltage therapy rooms. Results: 131I therapy rooms were found to meet both shielding and workflow requirements. The shielding was found to be adequate for orthovoltage and PET-SPECT facilities, neglecting patient transit between external washrooms. The workflow was the limiting factor for these rooms due to the requirement of dedicated washrooms that shield the patient and contain possible contamination. The PET-CT facility did not meet either criteria. The NCRP-151 method generally predicted a higher dose rate on the other side of shielding than did the RadPro calculator. The dose rate on the other side of concrete shielding as predicted by the NCRP-151 method increased relative to the dose rate predicted by the RadPro calculator as shielding thickness increased. For lead shielding, the dose rate predicted by the NCRP-151 method decreased relative to the result predicted by the RadPro calculator with increasing material thickness. Conclusions: 131I therapy, PET-CT uptake, PET-SPECT injection, and orthovoltage therapy rooms were considered. The 131I treatment rooms were the best candidate for 177Lu-PSMA therapy, due to their shielding and capability to accommodate the necessary workflow. [ABSTRACT FROM AUTHOR]

The shielding and spectroscopic properties of Pr + 3 and Pr3+/Ho3+-codoped tellurite glass were investigated. The intensity parameters (Ω2 = 3.24-, Ω4 = 1.64-, Ω6 = 1.10 × 10−20 cm2) as well as the radiative lifetimes of 3F4 + 5S2 and 5I6 excited states of Ho3+ ions were equal to 301 μs and 3.0 μs, respectively. The former value appears to be much higher than that obtained from the lifetime measurement, indicating the presence of various energy transfer processes. The NIR spectrum of Pr3+/Ho3+-co-doped tellurite glass is dominated by strong Ho3+: 5I6 emission at around 1200 nm, being the result of the energy transfer from Pr3+ to Ho3+ ions. The shielding effectiveness of the prepared glasses showed good performance against high-energy photons. These findings suggest that the prepared glasses could be used in laser technology such as photodynamic therapy (PDT) treatment procedures and as shielding for radiation protection. [ABSTRACT FROM AUTHOR]

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

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

Radiation protection in radiology is important because radiation may cause harm to the human body. The equipment for radiation protection is essential to ensure safe operations. Currently, there is widespread research on lead-free radiation shielding material. The aim of this research was to study lead-free material containing epoxy and iodine contrast media that was easy to form, low in cost, and environmentally friendly. The results showed that 2-cm material thickness with a concentration of 20% iodine had the greatest properties of radiation attenuate in the peak potential applied at technique 60–120 kVp, but the structure and strength of the shielding materials were decreased in accordance with increasing concentrations of iodine contrast media. It can be concluded that the lead-free epoxy radiation-shielding materials are able to absorb radiation at energy levels of 60–120 kVp. However, with improvement on homogeneity in the future, it could be used as a refractory shielding material in the radiology department. [ABSTRACT FROM AUTHOR]

Because of the increased use of ionizing radiation, radiation management and security procedures are now regarded a standard part of many therapeutic and specialist fields. The focus of this work is on the radiation security features of Novel Oxide Glass (PZBKTANEr). The unique glass assembly is 40P2O5-30ZnO-20BaF2-3.8K2TeO3-1.2Al2O3-5Nb2O5-3Er2O3 in mol percent (test code PZBKTANEr). For the suggested oxide glass, several radiation shielding characteristics have been investigated for a specific energy range of ionizing radiation. The linear and mass attenuation coefficients, mean free path, half-value layer, total nuclear and electronic cross-sections, and fast neutron expulsion cross-section are among the radiation shielding properties. Furthermore, the unique fabricated glass (PZBKTANEr) was compared to commonly used radiation protection compositions, such as RS-253 G18, RS-360, RS-520, Chromite, Ferrite, Magnetite, and Barite glass, as well as RS-253 G18, RS-360, RS-520, Chromite, Ferrite, Magnetite, and Barite glass. Also, we studied the structure of fabrication by using Raman spectra. The findings suggest that the new oxide glass might be used in a broad variety of ionizing radiation applications for protection in both therapeutic and industrial applications. [ABSTRACT FROM AUTHOR]

The correct and effective design of the spaces where radiotherapy applications are made with the linear accelerator device in the context of radiation shielding is extremely important to be protected from the harms of radiation to human health. In this study, it is aimed to examine the architectural design elements for radiation shielding of the spaces in the context of "spatial design, building materials and details". In the scope of the research, it has been seen that these factors should be considered and evaluated in an integrated manner for the design of the relevant spaces. It has been concluded that the options combining the high shielding potential with the structural systems which can be solved economically should be preferred in the design process. In this context, in the architectural design process of the spaces where the LINAC device producing high-energy radiation is located; It has been shown that it is possible to produce designs within the framework of optimal and shielding integrity with measures for radiation protection. [ABSTRACT FROM AUTHOR]

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

Glass samples were synthesized according to 10Li2O + 20CuO + xBi2O3 + (70 − x)B2O3, where x = 0, 10, 20, 30, 40 mol% by the melt-quenching method. The ability of the prepared glass to protect against gamma rays and neutrons was examined experimentally and theoretically. The mass attenuation coefficient (MAC) was calculated experimentally at energies of 0.662, 1.173, and 1.333 MeV using 137Cs and 60Co sources. The obtained results were compared with the theoretical ones using a Phy-x/PSD software program version 0.1.0.0. It was found that the experimental and theoretical results are very agreed upon. Moreover, other nuclear radiation shielding parameters were evaluated. The results showed that the addition of bismuth oxide leads to an improvement in the ability of the composite glass to attenuate gamma rays by increasing the values of MAC and Zeff, while it led to a decrease in the HVL and MFP, as well as the EBF and EABF. The results also showed that the addition of copper oxide led to an improvement in the ability of the present glass to slow down fast neutrons. Sample BiS40 showed the best result for gamma ray attenuation and sample BiS10 gave the best result for fast neutron removal cross section. The results were compared with some materials used for gamma ray shielding and fast neutron removal cross section, and it was concluded that samples Bi40 and BiS10 outperformed all commercial materials. [ABSTRACT FROM AUTHOR]

The use of radiation is mandatory in modern life, but the harms of radiation cannot be avoided. To minimize the effect of radiation, protection is required for the safety of the environment and human life. Hence, inventing a better shield than a conventional shielding material is the priority of researchers. Due to this reason, this current research deals with an innovative shielding material named EKZ samples having a composition of (epoxy resin (90–40) wt %-kaolin clay (10–25) wt %-ZnO-nano particles (0–35) wt %). The numerous compositional variations of (epoxy resin, kaolin clay, and ZnO-nano particles on the prepared EKZ samples varied the density of the samples from 1.24 to 1.95 g/cm3. The radiation shielding parameter of linear attenuation coefficient (LAC), half value layer (HVL), tenth value layer (TVL), and radiation protection efficiency (RPE) were measured to evaluate the radiation diffusion efficiency of newly made EKZ samples. These radiation shielding parameters were measured with the help of the HPGe detector utilizing the three-point sources (Am-241, Cs-137, and Co-60). The obtained results exposed that the value of linear attenuation coefficient (LAC) and radiation protection efficiency (RPE) was maximum, yet the value of half value layer (HVL), and tenth value layer (TVL), were minimum due to the greater amount of kaolin clay and ZnO-nanoparticles, whereas the amount of epoxy resin was lesser. In addition, it has been clear that as-prepared EKZ samples are suitable for low-dose shielding applications as well as EKZ-35 showed a better shielding ability. [ABSTRACT FROM AUTHOR]

High energy FRagment Separator (HFRS), an essential part of High Intensity heavy-ion Accelerator Facility (HIAF), is used to produce, separate and identify the Radioactive Ions Beams (RIBs). The target area in the pre-separator of HFRS can produce very strong secondary radiation, which seriously threatens the radiation safety of the environment, public and personnel. In this work, the FLUKA code is used to complete the radiation shielding calculation and design of the target area. Firstly, the secondary radiation produced by 25 different typical beam–target combinations are compared. The parameter of 78Kr in fast extraction mode is determined as the basis for the radiation shielding design based on its strongest secondary radiation. Then, the secondary neutron spectrum and the induced radioactivity of the production target and the beam dump are analyzed. The results show that the maximum neutron energy is close to 3 GeV, and special attention should be paid to high-energy neutrons in shielding design, as well as the maximum residual dose rates on the surface of the production target and the beam dump are 3.93 × 107 μ Sv/h and 9.58 × 107 μ Sv/h, respectively, after one month of continuous irradiation. Furthermore, the radiation shielding design is completed using the Q235 steel compact shielding together with the ordinary concrete and sand soil, based on the Monte Carlo simulations and the relevant dose limits. Finally, the radiation effects under this shielding scheme are analyzed. The results show that the shielding design meets the relevant design goals and can provide reliable radiation protection for the environment, public and personnel. [ABSTRACT FROM AUTHOR]

In this paper, a novel nuclear shielding material capable of shielding neutrons and gamma rays, WB-reinforced Al (WB/Al) composites, was prepared by spark plasma sintering (SPS) process. The microstructure of the composites was characterized, and the effects of WB content, heat treatment and matrix type on the properties of the composites were discussed. The results demonstrate that the WB particles are uniformly dispersed in the aluminum matrix and formed a good binding interface with the matrix. WAl 12 as an interfacial reaction product is identified, and segregation of Si and Mg elements at the reinforcement/matrix interface occurs. The mechanical properties of the WB/Al composites are sensitive to the WB content. The hardness, elastic modulus and bending strength of the composites increase monotonously as the WB volume fraction increasing, up to 234%, 107% and 91.6% higher respectively than those of the monolithic 6061Al. However, the tensile strength reaches a peak point when the volume fraction is 20%. The effects of T6 treatment and matrix type are not pronounced, especially for the composites with high WB content. The thermal neutron and gamma ray shielding properties of the composites both increase with the increase of material thickness and WB content. The WB/Al composites developed in this work show good application prospects in the field of nuclear radiation protection, due to their good mechanical properties and well neutron and gamma-ray shielding performance. [ABSTRACT FROM AUTHOR]