Radiation Shielding Materials Research Articles

Simulation-Based Radiation Shielding and Optical Properties of Thulium-Doped Bismuth Tellurite Glass

Lead-based radiation shielding material is currently used in industry to shield against high-penetration radiation such as gamma rays. However, lead is harmful to humans, animals, and plants. This study proposed a new composition of transparent lead-free glass. Using the melt and quench technique, thulium-doped bismuth tellurite glass with composition (TeO2)1-x (Bi2O3)x (Tm2O3)0.02 where x = 0.05, 0.10, 0.15, and 0.20 mol % was fabricated. Significantly, the glasses with Bi2O3 concentration of 5 mol % and 10 mol% have a higher density than the commercial glass containing lead indicating the fabricated glasses would perform better as a radiation shielding material. Comparing the simulated-radiation shielding properties using software Phy-X and XCom, the glass with 10 mol% of Bi2O3 performs better as radiation shielding material than 5 mol% of Bi2O3. Meanwhile, glass with 5 mol% of Bi2O3 performs better than 10 mol% of Bi2O3 in terms of optical properties. Considering both radiation shielding and optical properties, the fabricated lead-free glass can be widely used in radiation shielding applications that require transparency.

Effect of Ti, Bi, W, Zn, and Pb nanoparticles on the radiation shielding properties in transparent medium: a Monte Carlo study

Recently, researchers have tried to examine novel materials to enhance radiation shielding in hospitals and medical centers as a replacement for regular shielding materials such as lead and concrete. To assess the impact of new radiation shield materials, this study is devoted to the examining the silicon shields as well as silica and tellurium glasses containing nanoparticles and micro-particles. For this purpose, using Monte Carlo code MCNPX, the role of Ti, Bi, W, Zn, and Pb particles in silicon shields, also tellurium and silica glasses incorporating Bi2O3, ZnO, TiO2, WO3, and PbO particles in nanometer and micrometer scales with proportions of 10%, 15%, 20%, 25%, 30%, 35%, 40%, and 45% are examined. The MCNP results demonstrate a strong agreement with the XCOM data, with a relative difference less than 2.11% across all samples. The Kolmogorov-Smirnov (K-S) test has been conducted to evaluate the consistency between the simulated data and the XCOM data, with the maximum vertical deviation (Dmax) less than 0.01%. The results show the improvement of radiation protection characteristics following the particle size reduction from micrometers to nanometers in all shields. Moreover, it was observed that increasing the proportion of nanoparticles in the shields enhances the protective properties. As a result, the shields containing the smallest size and accommodating the highest number of particles exhibit the best radiation shielding properties. Finally, the tellurium glasses doped with 45% nanoparticles of WO3 demonstrated the best shielding properties.

Thermal Shielding Gd3TaO7-Based Thermal Barrier Ceramic with Ultralow NIR Transmittance.

Most thermal barrier coating materials exhibit transparent/semi-transparent properties at higher temperatures, causing the surface heat flow to directly heat the substrate with infrared radiation, which significantly reduces the thermal barrier effectiveness. Herein, composite ceramic materials composed of GdFeO3 diffusely dispersed within the Gd3TaO7 are produced. Specifically, the 0.9Gd3TaO7/0.1GdFeO3 composition demonstrates an ultra-low near-infrared (NIR) transmittance of less than 0.1% across the 400-2500nm range. The introduction of variable-valence behavior and oxygen vacancies contribute to the narrow bandgap of GdFeO3. The incorporated GdFeO3 produces extra multimode vibrations, resulting in the strong infrared emissivity of Gd3TaO7/GdFeO3 composite ceramics. Besides, the refractive index difference between Gd3TaO7 and GdFeO3 can contribute to the potential photons scattering within the composites, severely impeding the infrared radiation penetration. The upward curvature of the thermal conductivity curve of 0.9Gd3TaO7/0.1GdFeO3 at high temperature is significantly suppressed, confirming its excellent IR radiation shielding properties. Moreover, the Gd3TaO7/ GdFeO3 composite ceramic exhibits thermal suitability, with a thermal expansion coefficient (9.47-9.67 × 10-6 K-1 at 1400°C) comparable to YSZ. These combined benefits position the Gd3TaO7/ GdFeO3 composite ceramic system as a promising candidate for the development of infrared radiation shielding and high-emissivity thermal radiation materials.

Novel high temperature tritium blanket designs for confined spaces in spherical tokamak fusion reactors

Tritium self-sufficiency is one of the fundamental challenges for commercially viable deuterium–tritium nuclear fusion power stations. The combination of key high temperature radiation shielding materials that possess dense, high neutron absorption cross-section, and moderation properties, and tritium breeding materials could involve interesting design spaces for the central column challenge in spherical tokamaks. Potential tungsten alloys can be used for two functions: radiation shielding and structural material, providing a new design space window for spherical tokamak central column breeding space. In this paper, we present two novel high temperature concepts for the inboard side of the breeder blanket in a confined space, such as a spherical tokamak. A tungsten–rhenium–hafnium-carbide lithium-based design was found to offer the best TBR given a parameter optimisation based on shielding and thermal requirements. A silicon-carbide lead-lithium breeder design was also investigated. The highest TBR was found to be 0.135 in a 3D neutronics calculation with a W-24.5Re-2HfC (structural and shielding, wt%), Li (90% Li-6 enriched breeder), and tungsten pentaboride (W2B5) (shielding) option. Although this TBR is lower than unity, it will contribute to the reactor’s global TBR.

Development of and study of boro-tellurite glasses for optical and radiation shielding applications

A new group of boro-tellurite glasses (BCa20, BCa17, BCa14, BCa11) was fabricated using the melt quench method for potential radiation shielding and optical applications. The mechanical, optical, and radiation shielding properties were studied with varying oxide compositions. A decrease in B2O3 and CaO content, with increasing TeO2, led to a reduction in elastic modulus and bulk modulus (from 69.638 to 61.331 GPa), as well as a decrease in packing density (0.673 to 0.636). The optical band gap also gradually reduced (from 3.637 to 3.504 eV), while Urbach energy increased (from 0.293 to 0.354 eV). Optical basicity increased, and optical electronegativity decreased, indicating a shift toward ionic bonding and reduced glass stability. Radiation shielding performance improved with the addition of TeO2, as confirmed by the linear attenuation coefficient (LAC) results using Phy-X software. These findings suggest potential for these glasses in radiation shielding and optical material applications.

Remarkable improvement in radiation shielding efficiency, thermal insulation performance and compressive strength of rigid polyurethane foam composites by synergetic effect of PbO and colemanite fillers

Developing radiation shielding materials is a critical phenomenon for protecting people and the environment with the increment in usage of nuclear technology in today's world. With this sense, PbO/colemanite-filled rigid polyurethane foams were fabricated by one-shut free rise method, and their performances were investigated via the advanced characterization techniques such as ATR-FTIR, SEM-EDS, TGA as well as thermal conductivity, universal mechanical and radiation shielding tests. The characteristic properties of the samples were evaluated in detail depending on the variation in the filler contents. The ATR-FTIR analysis illustrated that RPUF matrices exhibited good compatibility with the fillers by forming the secondary chemical bonds. Furthermore, SEM analysis revealed that the samples with low PbO/colemanite fillers exhibited fairly uniform and regular cellular morphology with anisotropic elliptical apparition thanks to synergetic catalytic effect of the filler particles, whereas, at high content, some local distortions with slightly chaotic appearance were observed accompanied by viewing the little ruptures and bursts in cell face and collapsed in cell plateau borders. TGA measurement indicated that the inclusion of the fillers into RPUF got worse the samples with comparison of neat RPUF due to the reduction in crosslinking density of the foam. Remarkable improvement (about 25 %) was also obtained in thermal insulation performance at the foam composites containing the fillers due to highly augmentation in number of closed cells and presence of more immobile CO2 gas inside the cells. Furthermore, high inclusion of the fillers in RPUF matrix improved compressive strength of the foams by nearly 15 % by enhancing the bending moment and rigidity of RPUF matrices via contributing to the overall stress dispersion. According to linear and mass attenuation coefficients results, the foam composites displayed excellent X-ray radiation shielding performance with increasing of PbO/colemanite content thanks to the density increment and presence of the atoms with high atomic number. Furthermore, at low photon energy levels, better shielding against X-ray radiation was obtained, while vice versa at high energy levels.

Tungsten-Doped Borosilicate Glasses for Radiation Shielding

In this study, a series of glasses in the 25 Na2O- 15 B2O3- (60-x)SiO2- xWO3 system (with x up to 2 mol%) was developed by a melt-quench route. To evaluate their potential applications as novel lead-free transparent shielding materials in nuclear medicine, the impact of tungsten trioxide (WO3) addition on glass formation, structure, properties, and radiation shielding effectiveness of the produced glasses was also investigated. The glass forming ability was found to be restricted, and high-transparency homogeneous bulk glasses containing WO3 up to 1.5 mol% could only be achieved, as verified by XRD measurements. FTIR spectroscopy revealed the network modifications caused by the incorporation of various WO3 concentrations into the glass system. This was further supported by thermal and mechanical investigation, which demonstrated that increasing WO3 content increased both glass transition temperature (Tg) and Vickers hardness (Hv) values. The increases in Tg and Hv could be attributed to tungsten's participation in the formation of new strong W-O connections. Furthermore, the radiation shielding performance of the glasses, such as the half-value layer (HVL), the mean free path (MFP) and the lead equivalent thickness (LEV), as determined by means of a NaI(Tl) scintillation detector in a narrow beam geometry setup using 137Cs, 133Ba and 57Co as the radiation sources, were compared to that of commercial lead glass and found to be improved with higher WO3 content. The findings provide sufficient data to indicate that our tungsten-doped borosilicate glasses, especially the sample containing 1.5 mol% WO3, could be potential candidates for alternative lead-free, high-transparency radiation shielding materials in nuclear medicine applications.

Effect of ruthenium addition on gamma radiation interaction properties of UDIMET* 720Li alloy

The effect of doping of ruthenium (Ru) on the gamma radiation shielding properties of the nickel-base superalloy UDIMET*720Li (or briefly U720Li) was investigated in this study. The U720Li alloy is widely used commercially, and three new U720Li alloys formed by adding Ru, from 1%, 3% and 6% wt., were selected for the study. The investigation of the examined U720Li alloys to reveal the gamma radiation interaction properties will be extremely useful for the applications that they are used. To evaluate the usability of any material for various purposes in different radiation applications, it is an invaluable advantage to use various radiation-matter interaction parameters measured for in-question material. These parameters hand over remarkable knowledge about the capacity to be radiation shielding material or protection ability against radiation of that material. The radiation-matter interaction parameters; linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), mean free path (MFP), half-value layer (HVL), ten-value layer (TVL), effective atomic and electron number (Zeff and Neff) and effective conductivity (Ceff) were computed using software called Phy-X/PSD for present U720Li–Ru alloys in the energy range from 0.015 to 15 MeV. Then, the obtained radiation-matter interaction parameters are comparatively discussed to evaluate the effect of Ru addition on the gamma radiation shielding capacities of the studied U720Li–Ru alloys. It has been understood that the doping of Ru has favorable effects on the radiation shielding abilities of U720Li alloys.

Study on the mechanical properties and gamma/neutron radiation shielding performance of SnBi/B4C composite materials

The development of multifunctional shielding materials has become a hot research topic with the increasing requirements for radiation protection materials in terms of performance, weight and non-toxicity. In this study, non-toxic SnBi/B4C composites with different B4C contents (0, 3, 6, 9, 12 and 15 wt%) were successfully prepared by powder metallurgy, and their mass attenuation coefficients, half-value layers, mean free paths, effective atomic numbers, and 0.025 eV thermal neutron shielding performance. The results show that B4C plays a key role in regulating the mechanical properties and thermal neutron shielding properties of SnBi/B4C composites. When the B4C content was 9 wt% (S3), the integrated mechanical properties of the composites were optimal, and the yield strength, tensile strength, and microhardness were enhanced by 31 %, 32 %, and 129 %, respectively, compared with those of the samples without B4C. The radiation shielding effect is remarkable, the gamma-ray shielding performance in the energy range of 0.03–0.08 MeV is better than that of Pb. Meanwhile, the S3 sample with only 3 mm thickness can shield 99.7 % of thermal neutrons, while the shielding rate of the S0 sample without B4C is only 5.2 %. Comprehensive analyses show that the SnBi/B4C composites are superior in terms of environmental protection, mechanical properties, gamma-ray and thermal neutron shielding, with lighter weight and safer use. This finding provides a theoretical basis for the selection of efficient, non-toxic and diverse radiation shielding materials for medical and other special environments.

Recycling E-waste CRT glass in sustainable geopolymer concrete for radiation shielding applications

Waste cathode ray tube (CRT) glass, enriched with heavy metal of Pb, is classified as hazardous waste and needs to be disposed of harmlessly. This study recycles waste CRT glass as heavy aggregate in sustainable geopolymer concretes (GCs) to enhance its γ-ray shielding performance. It also comprehensively evaluates its macro-performances, microstructure, and environmental and economic impacts. The results demonstrate that the compressive strength of GCs decreases with the dosage of CRT glass. The generation of geopolymer gel is hindered by excessive CRT glass. Besides, the compatibility between CRT glass and the geopolymer matrix is poor. Both factors influence the strength development of CRT glass-incorporated GCs. The compressive strength of GCs with 50 % CRT glass aggregate exceeds 30 MPa, meeting the requirements for building materials. Due to the increase in the density and the introduction of heavy nuclei Pb, the γ-ray shielding performance of GCs is 9 % higher than that of normal concrete. In terms of economic and environmental benefits, this approach realizes the value-added recycling of CRT glass, avoiding the disposal cost of CRT glass. Besides, due to the utilization of sustainable geopolymer as cementitious materials, the carbon footprint of designed CRT glass-enhanced radiation shielding GCs is even 34 % lower than that of normal concrete. This study highlights the advantages of geopolymer and CRT glass in developing sustainable radiation shielding materials for nuclear technology and medicine fields.

Fabrication and characterization of rubcrete-iron composite for mixed radiation shielding

Mixed radiation environments need unique shielding materials that can effectively attenuate photons and neutrons simultaneously. Most ordinary shielding materials can only shield one form of radiation effectively. In this work, a novel composite material was fabricated in our laboratories and characterized for photon and neutron shielding. Waste materials were used as partial substitutes for aggregates in concrete, which is a sustainable practice in the building industry at present. The main components of the composite material are iron filings, rubber, and concrete. Concrete samples were mixed with iron filings at varying percentages (0%, 10%, 20%, and 30%) and a fixed 5% crumb rubber content. The material’s photon and neutron shielding characteristics were evaluated through experimental and simulation methods. Gamma-ray attenuation measurements were experimentally carried out using a NaI(TI) spectrometer and a Cs-137 0.662 MeV energy source. In contrast, GEANT4, PHY-X/PSD, and NIST-XCOM codes were used to simulate photon and neutron cross-sections. The findings indicate that an increase in iron filings results in enhanced radiation attenuation, reflected by a higher linear attenuation coefficient (μ). The linear attenuation coefficient values range from (0.1590 ± 0.0004) to (0.2045 ± 0.0003) cm−1 for samples with no crumb rubber and from (0.1521 ± 0.0002) to (0.1920 ± 0.0004) cm−1 for samples with 5% crumb rubber. Half Value Layer (HVL) decreases with an increase in iron content and is slightly higher in samples with crumb rubber. The HVL results from simulations and measurements agree. This study optimizes the potential of concrete as a radiation-shielding material while promoting sustainable construction and environmental practices.

Nuclear radiation shielding properties of calcium aluminum barium sodium borate glass samples doped with Dy3+ ions

Nuclear technology finds extensive application across various industries, medical physics, and research institutions, spanning fields such as agriculture and food technology. Despite its benefits, the pervasive use of ionizing radiation underscores the need for effective shielding materials to mitigate associated risks. Lead and concrete, traditionally favored for their attenuation properties, pose challenges due to weight, opacity, and toxicity concerns. In this context, calcium aluminum barium sodium borate glasses doped with Dy3+ ions emerge as promising alternatives for radiation shielding. This study investigates the ionizing electromagnetic radiation (gamma and X-ray) shielding capabilities of calcium aluminum barium sodium borate glasses doped with Dy3+ ions across a range of concentrations (0.1, 0.3, 0.5, and 1.0% mol). The mass attenuation coefficients and linear attenuation coefficients of four glass samples (S1 to S4) were determined using the software (Phy-X). Additionally, parameters such as effective atomic number (Zeff), half-value layer (HVL), tenth-value layer (TVL) and mean free path (mfp) were computed to assess shielding effectiveness.The results indicate that higher Dy3+ concentrations correlate with increased attenuation effectiveness, as evidenced by elevated μ and μm values. Glass sample S4, with the highest Dy3+ concentration, demonstrated superior shielding properties, attributed to its elevated density. Notably, the study elucidates the relationship between attenuation coefficients and photon energy, highlighting the dominance of photoelectric and Compton scattering effects. Furthermore, analysis of HVL, mfp, and Zeff values reveals the nuanced interplay between glass composition and radiation attenuation. Despite variations in composition, S4 consistently exhibited optimal shielding characteristics across photon energy ranges. The investigation also examines exposure and energy absorption buildup factors, indicating that higher Dy3+ concentrations lead to lower buildup values, indicative of enhanced shielding performance.In conclusion, the study underscores the potential of Dy3+ doped calcium aluminum barium sodium borate glasses as effective radiation shielding materials, offering insights into their composition-dependent attenuation properties. These findings contribute to the development of lead-free alternatives and advance the understanding of radiation shielding mechanisms in glass matrices, with implications for diverse applications in nuclear technology and beyond.

Enhancing shielding efficiency of ordinary and barite concrete in radiation shielding utilizations

Concrete has been widely utilized as a radiation shielding material due to its properties and structural integrity. This study aims to evaluate the efficiency of ordinary concrete versus barite concrete as radiation shielding materials, focusing on the physical aspects and changes in crystal size lattice parameters after neutron irradiation. Specifically, the research investigates the shielding effectiveness of these materials across different grades (M15, M25, M35, and M45) against gamma-ray sources Cobalt-60 and Caesium-137. The methodology involves measuring the linear attenuation coefficient (μ), half value layer (HVL), tenth value layer (TVL), and mean free path (MFP). Additionally, X-ray diffraction (XRD) was employed to assess crystallite size and lattice parameter changes post-irradiation for neutron irradiation. Results indicate that incorporating barite as an aggregate significantly enhances the density and crystallite macroscopic properties of the concrete. Irradiation with Cobalt-60 and Cesium 137 revealed that ordinary concrete has a lower linear attenuation (μ) ranging from 0.172 to 0.195 cm−1, with consistent mass attenuation across all grades at 0.81 cm2/g. XRD analysis demonstrated a rightward shift in the SiO₂ and BaSO₄ peaks post-irradiation, signifying crystalline expansion. In terms of lattice parameters, the d-value showed a notable decrease of 0.10 after 48 h of irradiation in grade 25, while the most significant increase of 0.02 occurred after 24 h of irradiation in grades 15 and 45. In conclusion, barite concrete proves to be more effective for radiation shielding in nuclear facilities, whereas ordinary concrete is suitable for medical shielding, or facilities exposed to lower radiation doses.

Advancing gamma radiation shielding with Bitumen-WO₃ composite materials

This research focuses on a manner in which bitumen-WO₃ (petroleum-derived bitumen mixed with tungsten trioxide nanoparticles) materials can be a good shielding candidate against gamma radiation. The objective we set in mixing WO₃ nanoparticles with bitumen was to take advantage of both the bitumen's natural qualities and the WO₃'s excellent shielding capabilities. The prepared composites were tested against various gamma-ray energies emitted from multiple gamma-ray sources to examine their shielding capabilities. The X-ray diffraction (XRD) analysis of the composites' structural properties verified the effective integration of the WO₃ with the bitumen structure. Scanning electron microscopy (SEM) showed that microstructural changes, such as an increase in material density and an improvement in particle dispersion, are caused by a rise in WO3 concentration, which is an essential step toward efficient shielding. Then, the Mean Free Path (MFP), Half-value Layer (HVL), and Linear Attenuation Coefficients (μl) were computed, showing that the composite's capacity to reduce gamma radiation is much enhanced by raising the WO₃ content, especially at lower gamma-ray energies. For instance, at 20 keV, the LAC of 50 wt% WO₃-bitumen composite increased to 9.18 cm⁻1 compared to pure bitumen's 0.40 cm⁻1, while the HVL decreased from 1.73 cm to 0.08 cm, and the MFP dropped from 2.3 cm to 0.1 cm” The results demonstrate the potential of bitumen-WO₃ composites as a sustainable and efficient material for radiation shielding, particularly highlighting their applicability in various sectors, including the development of building wall paints against gamma radiation.

Research on B4C/PEEK Composite Material Radiation Shielding

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

Exploring the Radiation Shielding Efficiency of High-Density Aluminosilicate Glasses and Low-Calcium SCMs

A lot of work is now going into making low-calcium supplementary cementitious materials (SCMs) and aluminosilicate glasses so that they can be used as radiation shielding materials. These materials demonstrate superior performance in several aspects as compared to conventional concrete. The present investigation focuses on the radiation shielding characteristics of the evaluated materials, specifically their capacity to reduce the intensity of gamma rays and neutrons. Regarded for their exceptional density and ability to include heavy metal oxides, aluminosilicate glasses have remarkable shielding characteristics, especially when designed at the molecular scale. An evaluation of the performance of these materials in comparison to traditional concrete is carried out using Phy-X/PSD software. The goal is to determine the most important shielding properties, such as the mass attenuation coefficient, the linear attenuation coefficient, and the half-value layer. Our study findings suggest that some aluminosilicate glasses, such as GM, consistently demonstrate exceptional photon and neutron attenuation efficiency. The observation that GM performs better than other materials in tests like effective atomic number, rapid neutron removal cross section, and energy absorption accumulation factor supports this claim. There is evidence that using low-calcium glass-crystal materials (SCMs) with aluminosilicate glasses not only improves radiation protection but also makes solutions work better when space or weight are limited. The present investigation validates that these materials exhibit superior performance compared to conventional concrete in challenging environments such as nuclear waste storage, where safety is of utmost significance.

Potential use of ABS polymer reinforced with nanoparticle sized yttrium as radiation shielding material

Potential use of ABS polymer reinforced with nanoparticle sized yttrium as radiation shielding material

Gamma radiation attenuation, mechanical properties and microstructure of barite-modified cement and geopolymer mortars

The present study contributes to the development of alternative materials for radiation shielding, focusing on environmental sustainability and material cost efficiency. The primary aim was to evaluate the compressive and flexural strength, mineral composition, microstructure, and gamma-ray attenuation properties of cement mortars and geopolymer mortars containing barite powder. Mortars based on ordinary Portland cement (OPC) and fly ash geopolymers with varying amounts of barite powder were assessed for their shielding properties at energy levels associated with the decay of 137Cs. From the results, key parameters such as the linear attenuation coefficient (μ), mass attenuation coefficient (μm), half-value layer (HVL), and tenth-value layer (TVL) were determined. The results showed that while cement-based composites exhibited superior gamma radiation attenuation compared to fly ash geopolymer mortars, the latter had higher mass attenuation efficiency, meaning less material density was required for the same level of shielding. Additionally, cement mortars had 23–25 % higher mechanical strength than geopolymer mortars. Importantly, the inclusion of barite powder improved the radiation shielding performance of both materials by 7–10 %, demonstrating its effectiveness in enhancing the protective properties of these mortars. This research highlights the potential of fly ash geopolymer mortars as viable, eco-friendly alternatives to traditional cement mortars in radiation shielding applications.

Assessment of different shielding materials for radiation therapy of maxillofacial tumors – An in vitro study

Aim: Since the advent of radiotherapy, the success rate of head and neck cancer treatment has increased significantly. However, when the tissue tolerance level is exceeded, unnecessary and uncontrolled exposure to radiation is considered detrimental. Such problems remain difficult to prevent and manage. The aim of the study to evaluate and compare the degree of attenuation of therapeutic radiation using four different radiation shielding materials of varying thickness. Study Setting and Design: In vitro experimental study. Materials and Methods: The samples were divided into four groups based on the different radiation shielding materials of thickness 3mm and 5mm. The materials are Lead (Pb), Silver-tin alloy (Ag-Sn) with Polyvinylsiloxane (PVS), Polymethylmethacrylate (PMMA) with Barium sulphate (BaSO4), and a combination of Ag-Sn with PVS and PMMA with BaSO4 which was exposed to radiation. The radiation dose measurements were recorded and the radiation attenuation properties of the shielding materials were evaluated. Among all of the shielding materials the most efficient material under consideration is determined. Statistical Analysis Used: One-way ANOVA followed by post hoc test was used to compare the means of all four groups. Results: A statistically significant difference between groups was found by a one-way ANOVA with a P = 0.001. In the post hoc test, statistically significant findings were obtained with a P = 0.05 when comparing the variation values of 3mm and 5mm thickness between each group and other groups. Conclusion: The shielding materials results in significant reductions in radiation dosage. It was concluded that the combinations of Ag-Sn alloy with PVS, and PMMA with BaSO4 of thickness 5 mm had a good shielding effect.

Optical and gamma-ray shielding properties of calcium sodium borate glasses with varied equal concentrations of ZnO and BaO

This study presents the optical and radiation shielding characteristics of a newly developed borate glass, doped with equal quantities of ZnO and BaO, and modified with calcium and sodium. The glass samples were prepared using the melt quenching technique, with the composition formula (80-x-y)B2O3-10CaO-10Na2O-xZnO-yBaO, where x and y were varied at 5, 10, 15, and 20 mol%. Comprehensive analyses of the optical and gamma shielding properties were carried out using UV–visible spectrophotometry and Phy-X software, respectively. The UV–visible spectroscopic data allowed for the calculation of various parameters including the direct and indirect optical energy band gaps, refractive index, dielectric constants, and polarizability. It was observed that the direct optical energy band gap decreased from 3.91 to 3.10 eV, while the indirect band gap fell from 3.41 to 2.91 eV with increasing ZnO and BaO content. Conversely, the refractive index rose from 2.29 to 2.42 with higher concentrations of ZnO and BaO. The linear attenuation coefficients (LACs) across the range of 0.015–15 MeV exhibited an inverse relationship. Among the glass samples, B40Zn20Ba20 exhibited the lowest tenth value layer (TVL) and the highest effective atomic number (Zeff), indicating its superior performance as a radiation shielding material. Overall, the produced glass samples demonstrate commendable properties for both optical applications and radiation shielding.