Radiation Shielding Research Articles

Bismuth oxide effects on optical, structural, mechanical, and radiation shielding features of borosilicate glasses

Four glasses were synthesized using traditional melting and then the annealing process to study the possible enhancement effects of heavy metals like Bi2O3 on the borosilicate glass system for the composition ((50-x)B2O3–5SiO2–40MgO-xBi2O3 where x = 5, 10, 15, and 20). The structural features were investigated using Fourier-transform infrared (FT-IR) analysis and X-ray diffraction (XRD). Many physical and mechanical parameters have been studied. Optical absorption was measured for all samples to investigate direct and indirect transitions for optical band gap energy (Eg) and Urbach’s energy (EU) and extract various optical properties. The well-known Phy-X simulation was utilized to achieve the study’s goal of calculating the shielding parameters of various gamma energies. Based on XRD results, the amorphous nature of all samples was observed. Adding Bi2O3 instead of the B2O3 side improves the ionizing radiation shielding properties and glass transparency. For example, the MAC values at 15 keV increased from 34.75244 to 73.80841 cm2/g with adding Bi2O3. At the same time, the glass transparency rose from 62 % to 72 %. In contrast, adding Bi2O3 reduced the glass stability according to mechanical and structural properties results. For example, Young’s modulus reduced from 88.745 to 62.109 GPa with increasing Bi2O3. The packing density (Vt) also decreased from 0.606 to 0.468. Based on the results, the current glass is valid for use in a radiation shielding field.

Eggshell-enhanced composites: Innovative radiation shielding materials for diagnostic X-ray applications

Concrete, a widely-utilized construction material for diagnostic room, heavily relies on Portland cement which is a major contributor to carbon emissions. Thus, this study focused on replacing cement with combination with clay (bentonite and kaolin) and eggshell powder (ESP) as possible shielding materials for diagnostic x-rays. 2 cm blocks are made from combination of clay-ESP, clay-cement and cement-ESP with replacement portions of 0%, 25%, 50% and 75%. Radiation shielding parameters (RAR, LAC, MAC and HVL) of these samples are investigated using a general x-ray machine at 60, 80, 100 and 120 kVp. In addition, elemental composition and compressive strength test are also performed on the blocks. As a result, between all combination, cement-ESP shows the highest RAR, LAC and MAC, however addition of ESP in cement did not show a significant photon absorption capability. Meanwhile, addition of ESP in the mixing portion for both clay results the RAR and MAC to increase due to presence of Si and Ca element in the blocks. In addition, clay-cement combination shows comparable shielding properties value and compressive strength to pure cement block. Therefore, since the objective of this study is to substitute cement with an environmentally friendly material, this particular combination is adequate for serving as a protective barrier for diagnostic purposes.

FTIR, Raman spectroscopic, microstructure and neutron-particle interaction properties of Mo3+ doped cadmium zinc lithium-borate glasses

The application of different glass materials in the area of radiation shielding and charge particle attenuation has necessitated a comprehensive study of glass materials doped with special elements to examine the impact of the special element on the microstructure and shielding capabilities of resultant glass materials. In this study, the optical absorption spectra of Mo3+ doped cadmium zinc lithium borate glasses (BCZLMx) was investigated using X-ray diffraction (XRD), Fourier transform infrared (FTIR) spectroscopy and Raman spectroscopic methods to ascertain the suitability of BCZLMx glass microstructure to neutron and charge particle attenuation. Results show that the absorption cross-section is the dominant contributor to the total cross section for all samples, ranging from 110.9 cm−1 to 111.7 cm−1. BCZLM1 glass sample appears to be slightly more effective at removing fast neutrons from the beam while BCZLM5 glasses are effective at stopping electrons, protons, alpha particles, and carbon ions when compared to the other BCZLMx glasses samples. This implies that doping cadmium zinc lithium borate glasses with Mo3+ reduces fast and thermal neutrons shielding potential and increased charge particles interaction of the BCZLMx glass system.

Microstructure and radiation shielding characteristics of PVA fiber-reinforced ultra-high performance concrete

The application of nuclear technologies simulates the development of radiation shielding materials. Traditional heavy-weight concrete used for radiation shielding is limited in practical construction due to the poor mechanical properties and durability. This study developed a PVA fiber-reinforced ultra-high performance concrete (UHPFRC) with magnetite as heavy aggregates used for radiation shielding. Due to the scientific skeleton design, UHPFRC exhibits superior mechanical properties, with compressive strength and flexural strength reaching up to 121.9 MPa and 23.2 MPa, respectively. The microstructure of UHPFRC was investigated in detail and the results revealed that the incorporation of PVA fibers refined the pore structure of UHPFRC. The interfacial transition zone between magnetite aggregates and cementitious matrix in UHPFRC was much denser than that in traditional concrete due to the low water to binder ratio. The gamma and neutron radiations shielding capacity of UHPFRC were evaluated by the combination of actual measurement and simulation. By introducing light nuclei and refining the pore structure, the incorporation of PVA fibers improved the neutron radiation shielding capabilities of UHPFRC by 5.1%.

Physical, chemical and radiation shielding properties of metakaolin-based geopolymers containing borosilicate waste glass

Upcycling waste borosilicate glass (BS) is a viable and sustainable way of preserving the natural resources required for the production of new materials and ensuring environmental sanitation and safety. This study was aimed at investigating how the addition of BS influences the physical, chemical, and mechanical properties and shielding performance against neutrons and charged particles on metakaolin-based geopolymer G. Four batches of G infused with 10%, 20%, and 30% wt BS samples and coded as G, G-10BS, G-20BS, and G-30BS, respectively, were fabricated based on the solid-state reaction method. The samples were characterized accordingly using experimental and theoretical procedures. X-ray diffraction analysis of the materials showed that the addition of BS suppressed crystal peaks in the geopolymers. The Vickers hardness values were calculated as 554, 503, 517, and 528 HV under a 0.1 kg load. The values of fast neutron macroscopic cross-section increased from 0.0601 cm−1 to 0.0706 cm−1 as BS content increased from 0 to 30 wt%. The coherent, incoherent, absorption, and total interaction probabilities of thermal neutrons increased in the geopolymer samples. For electrons, the stopping powers were in the range of 1.575–13.17 cm2/g, 1.571–13.15 cm2/g, 1.571–13.16 cm2/g, and 1.571–13.18 cm2/g for G, G-10BS, G-20BS, and G-30BS, respectively. The projected ranges of carbon ions in G, G-10BS, G-20BS, and G-30BS are within the limits 0.069–17.87 μm, 0.064–16.99 μm, 0.064–16.99 μm, and 0.057–15.24 μm. The trend of the projected ranges of electrons, protons, α-particles, and C ions with kinetic energies within 15 keV and 15 MeV was mostly in the sequence G > G-10BS > G-20BS > G-30BS. This order was consistent with the density and BS content of the geopolymer samples. The addition of BS to the metakaolin-based geopolymer improved the fast neutron moderating capacity and thermal neutron cross-sections and reduced the range of charged particle radiation in the geopolymers. The neutron shielding ability of G-30BS was found to be better than that of some existing shielding materials. The BS-infused concrete can be useful for the production of concrete used for radiation control.

Numerical approximation for the radiation shielding properties of borosilicate glasses with ZnO using piecewise cubic Hermite interpolating polynomials and Akima interpolation

Numerical approximation for the radiation shielding properties of borosilicate glasses with ZnO using piecewise cubic Hermite interpolating polynomials and Akima interpolation

Impact of bismuth oxide on structural, optical and gamma-ray shielding properties of calcium-sodium-borate glasses.

In the present study, we have prepared six glass samples of bismuth borate using the melt-quenching method with the composition (70-x)B2O3-10CaO-20Na2O-xBi2O3; x=0, 3, 6, 9, 12 and 15mol%. The density of the prepared glasses was determined using Archimedes principle. The X-ray diffraction patterns provide confirmation of the amorphous nature of the prepared samples, whereas the Fourier transform infrared measurements pointed to the existence of structural units like BO3, BO4, BiO3 and BiO6 within the glass network. An assessment of the optical absorption spectra unveiled that with the increase in the bismuth oxide content, there was a decrease observed in both the direct and indirect band gap energies. Specifically, they decreased from 3.40 to 2.79eV and from 3.10 to 2.46eV, respectively. The properties related to gamma ray attenuation, including the mass attenuation coefficient (μm), effective atomic number (Zeff), half-value layer (HVL) and mean free path (MFP), were examined for all the glass samples. This investigation was carried out using the Phy-X/PSD software, covering the energy range from 0.511 to 1.332MeV. Out of all the samples, Bi-15, featuring the highest Bi2O3 content, demonstrated the highest μm, Zeff, the smallest HVL and MFP. These results suggest that the glass with 15mol% of Bi2O3 offers the most effective gamma radiation shielding performance. Moreover, the glasses examined in this study exhibit superior radiation shielding characteristics compared with specific concrete types, namely, ordinary concrete, Hematite serpentine concrete and barite concrete, as well as commercial glasses such as RS-360 and RS-253.

Study on polymer composites with glass for gamma ray shielding.

The shielding of gamma radiation is of the utmost importance in industries, such as nuclear power plants, medical imaging, and space exploration. For the purpose of shielding objects in such an environment, it is essential to design materials with flexibility as well as high shielding capability. In order to enhance the radiation attenuation effectiveness of polymers, such as polyvinyl alcohol (PVA), glass has been blended with varying percentages. The fabricated composite has been subjected to gamma-ray interaction studies. The radiation shielding parameter, such as mass attenuation coefficient (μ/ρ), has been determined for various energies, such as 137Cs (661.6keV) and 60Co (1173 and 1332keV). It is observed that the PVA composite with glass exhibits improved gamma radiation shielding properties compared to PVA. Therefore, the present work paves the way for the utility of PVA polymer with glass, offering a cost-effective and sustainable approach to gamma radiation shielding in radiation environments.

Exploration of optical, mechanical and radiation shielding properties in B2O3-BaO-Na2O-ZnO-CaO glasses: A compositional study

We investigated the optical, mechanical, and radiation shielding features of a novel B2O3-BaO-Na2O-ZnO-CaO glasses prepared using the melt-quench method. Using UV–Vis spectroscopy, the optical features were characterized. The results indicate that upon reducing the B2O3 content, the band gap decreases from 3.722 eV to 3.069 eV, and refractive indices increase from 2.225 to 2.378. On the other hand, mechanical properties were studied based on the Makishima–Mackenzie model. Young's modulus, for instance, decreased from 93.314 GPa (G1) to 78.896 GPa (G4). Radiation shielding properties were studied using the Phy-X software, and the results showed significant variations, with the linear attenuation coefficient (LAC) values at 0.015 MeV being 48.378 cm−1 for G1, cm−1 for G2, 75.282 cm−1 for G3, and 89.360 cm−1 for G4. The half-value layer (HVL) at 0.015 MeV ranged from 0.014 cm (G1) to 0.008 cm (G4). The results indicate that increasing BaO-Na2O-ZnO-CaO content improves the glass's radiation shielding ability but decreases its mechanical strength.

COAT Project: Intercomparison of Thermometer Radiation Shields in the Arctic

A metrological field intercomparison of thermometer radiation shields in the Arctic was conducted with the aim of obtaining information to increase the worldwide comparability of air temperature measurements. Air temperature measurements are performed by different combinations of thermometers and shields. The response of each system (thermometer + shield) to local meteorological conditions depends on the system itself, limiting the comparability of air temperature measurements. Ten different models of radiation shields were included in the intercomparison, involving two campaigns: (1) the laboratory campaign, where all the instrumentation was calibrated just before and just after the field campaign, and (2) the field campaign that lasted 14 months where 41 thermometers were sampled every 2 min. All the delivered data were subjected to quality control to assure the robustness of the conclusions. A reference shield was defined, and the other shields were compared to the reference one for the conditions where maximum divergences were expected, solar irradiance being the highest impact factor. A maximum divergence value of 1.29 °C was derived for one of the shields and, for all the shields, the difference from the reference one decreases with wind speed. Finally, the uncertainties associated with the shields intercomparison were calculated.

Investigating polyurethane foam loaded with high-z nanoparticles for gamma radiation shielding compared to Monte Carlo simulations

Since the beginning of research into radiation and protection against it, the importance of searching for proper materials against radiation hazards has been recognized. Gamma radiation protection materials usually deal with heavy elements with high prices, which are hard to maintain. Polyurethane-based (PU) materials are popular in sound and thermal insulation due to, their low-weight properties and, most importantly, fast and convenient construction ingredients. PU foams (PUF) can be used as radiation shield and noise and heat resistance due to their approachability, light-weight, high resistance, and comfortable construction. This study involved simulation and an experiment to construct and investigate the properties of Polyurethane material doped with lead oxide as a gamma shield. The shield was considered in several weight fractions of lead, yielding several samples. The MCNPX 2.6 Monte Carlo code has been utilized for simulation procedure, and 137Cs was employed as the gamma source in both simulation and experiment. The results offer a promising response against the gamma radiation and are suitable for attenuating gamma rays.

Exploring structural and optical properties of Cu-doped and Fe-doped sodium borate glasses

This study investigated the structural and optical properties of Cu-doped and Fe-doped sodium borate glasses. X-ray diffraction (XRD) patterns confirmed that both samples were amorphous, with no sharp peaks. However, differences in the width and center of the high-intensity humps suggested variations in atomic packing and field strength between the two samples. Fourier transform infrared (FTIR) spectra showed wider vibrational modes and stronger absorption in the Fe-doped sample, confirming its higher atomic packing and field strength. Luminescence spectra indicated that the Cu-doped sample had a higher ratio of Cu2+:Cu3+ than the Fe-doped sample of Fe2+:Fe3+, resulting in greater UV–visible region absorption. Optical parameters such as absorbance, transmittance, and reflectance supported these findings, with the Fe-doped sample exhibiting higher absorbance band edges. Quality factor (Q.F.) analysis revealed that the Fe-doped sample had a larger Q.F. than the Cu-doped sample, indicating lower energy losses. Furthermore, the optical conductivity of both samples increased with photon energy, with the Cu-doped sample dominating in all energy regions. Finally, both samples exhibited high effective atomic numbers, suggesting potential applications in radiation shielding, with the Cu-doped sample having a wider radiation shielding window. Finally, the findings unique structural and optical properties suggests the Cu-doped and Fe-doped sodium borate glasses to a lot of potential applications in various fields including radiation shielding, optics, electronics, and energy storage.

Optical, physical, mechanical, structural, and radiation shielding investigations of B2O3–TeO2-GeO2-MgO-PbO for ionizing protection and optical transmission application

This study aims to investigate a new heavy glass system's potential use in the radiation shielding and optical transmission applications. Glass former like borate is replaced in this work by heavy metal oxides like lead oxide in the following glass system: (35-x) B2O3–20TeO2-10GeO2-35MgO-xPbO (where x = 2.5, 5, 7.5, and 10 mol%). Through the melt-annealing process, four transparent glasses were synthesized. A number of physical properties were reported, namely the boron–boron separation x 10−8 m, field strength x 1018 (cm2), inter nuclear distance x 10−8 m, ion concentration (N) x 1023 (ion cm3), molar volume (cm3/mol), molecular weight (g/mol), and polaron radius x 10−9 m. Moreover, the following mechanical and structural properties of the synthesized glasses were explored: bulk modulus (B, GPa), dissociation energy (kcal/cm3), fractal bond connectivity (d), longitudinal modulus (L, GPa), hardness (H, GPa), oxygen packing density, packing density (Vt), oxygen molar volume, packing factor (Vi), shear modulus (S, GPa), Poisson radius (σ), and Young modulus (Y, GPa). To study the bulk glasses' nature, the X-ray diffraction was examined. Optical absorption along with optical transmission profile have been recorded to extract various optical properties, as well as the direct and indirect band gap. The transmittance spectra of the prepared glass samples' FTIR were investigated within the 400–2000 cm−1 range. This allowed for the examination of molecular structural groups and vibrational modes. Radiation shielding parameters have been calculated and studied using XCOM software and MCNP-5 algorithm.

Lunar regolith for plasma spray coatings

On the threshold of the first human residences on the Moon, a key requirement for early colonists will be to become rapidly self-sufficient, as the transportation of supplies and materials will be limited. ISRU (In Situ Resources Utilisation) focuses on this particular aspect and proposes the use of lunar regolith as a possible solution. In this study, we consider using this prime resource to manufacture thick coatings using the plasma spray technique. A lunar regolith simulant was successfully deposited on steel substrates and was found to form very adhering coatings, exhibiting similar properties and chemistry to the raw material, that is, mare basalts. This kind of newly formed coating could play various shielding roles, such as those of a thermal barrier or radiation shield.

Synergistic optimization of physical, thermal, structural, mechanical, optical and radiation shielding characteristics in borate glasses doped with Bi2O3

This paper presents the effect of Bi2O3 on physical, thermal, structural, mechanical, optical, and radiation shielding properties of borate-based glasses having a composition (60-x)B2O3–25Na2O–13BaO-2Gd2O3-xBi2O3; x = 0, 5, 10, 15, and 20 mol%. XRD analysis confirms the amorphous structure of the prepared glasses. As Bi2O3 content increases from 0 to 20 mol%, density of the glasses increases from 2.729 to 3.896 g/cm3, and molar volume rises from 30.947 to 42.017 cm3/mol. The glass transition temperature (Tg) of the samples decreased with Bi2O3 content. FTIR analysis reveals the presence of BO3, BO4, BiO3, and BiO6 structural units in the prepared glasses. Optical absorption studies indicate a decrease in band gap energy from 3.006 to 2.573 eV for indirect transitions implying non-bridging oxygen atom formation and this inference is supported by both physical and FTIR results. The elastic parameters, derived from Makishima-Mackenzie model decreased with increased Bi2O3 concentration suggesting a reduction in mechanical properties. The mass attenuation coefficient (μm), determined through experimental measurements and using Phy-X/PSD software, yielded closely aligned values. Other shielding parameters such as half-value layer (HVL), mean free path (MFP), and effective atomic number (Zeff) were also calculated. The glass containing 20 mol% Bi2O3 exhibited a significant gamma-ray shielding potential due to its high μm value, (0.1260 cm2/g at 0.511 MeV and 0.0960 cm2/g at 0.662 MeV) and Zeff together with low HVL and MFP. A Comparative analysis of the μm values for the present glasses and that of other glasses containing Bi2O3 is also presented.

Red mud and bismuth oxide based X-ray shielding tiles for upcoming hospitals: A comprehensive study on phase quantification and physical properties

Red mud (RM) is a solid alumina industry waste generated in millions of tonnes and is stockpiled across the globe. From the environmental perspective, research and innovation strategies are utmost necessary for the minimization and utilization of red mud. In an attempt to develop an environmentally friendly technology, RM was utilized with Bi2O3 for the development of radiation shielding tiles. RM is a source of many metal oxides, which react with Bi2O3 during sintering and form various high-dense phases. The Rietveld refinement of the tiles sintered from 600 to 1100°C confirms the formations and transformations of several high-dense phases like Bi24Ti2O40, BiFeO3, and Na0.5Bi0.5TiO3. The RM-Bi2O3 mixture sintered at 1100°C (RMBi1100) exhibited high density (3.64 ×103 kg m−3), less porosity (10 %), and flexural strength of 24 MPa. The results showed that the developed sample has a half-value layer (HVL) of 1.15 mm at 140 kV. The 15.5 mm, 13.5 mm, and 7 mm thick RMBi1100 tiles can effectively replace 2.3 mm, 2 mm, and 1 mm thick lead sheets respectively, that are used to establish radiation shielding structures in computed tomography, radiography & fluoroscopy, and dental infra oral radiography installations, respectively. It can promote the utilization of red mud and thereby reduce the environmental pollution associated with lead and red mud.

Evaluation of Barium sulfate-copper breast radiation shield for use in thoracic Computed Tomography Examinations

Evaluation of Barium sulfate-copper breast radiation shield for use in thoracic Computed Tomography Examinations

An Optimal Radiation Shield Design of a Small Modular Nuclear Power Reactor by Genetic Algorithm

One of the critical concerns in developing small modular nuclear reactors (SMRs) is employing efficient radiation shielding consistent with the design and implementation requirements. Besides observing the radiation shielding requirements, the design process entails developing compact, lightweight shielding as well as ensuring the safety of the staff and radiation-sensitive equipment around the reactor under different operating conditions. Conventional methods of radiation shielding design are based on experiments conducted. Therefore, the resultant design involves trial and error, rarely achieving an optimal, effective, and efficient design. In this study, a multi-objective method based on the genetic algorithm coupled with the MNCP calculation code has been used to enhance the radiation shielding system of a SMR. Using this method, the thickness of different shielding layers has been optimized to minimize the total dose (neutrons and gamma) at the output, the weight, and the overall volume of the shielding. To assess and compare the method used to an implemented conventional method, a sample design of the MRX nuclear power reactor is considered. Using the optimization technique, the radiation shielding of the reactor has been redesigned and compared with the original design. This paper discusses the existing deficiencies in the initial design of the primary shield of the reactor as a design implemented based on conventional methods. Similar to the original design, the main materials considered for radiation shielding in consecutive layers were water and steel, and the final layer contained lead. The thickness of the different layers and their arrangements have been optimized to assess the upgraded method. The calculations indicate that the overall thickness of the proposed shielding is suggested as 93.8 cm compared to 140 cm to obtain the total dose of neutrons and gammas, which is suggested as less than 10 µSv/h. The results imply a 38.56% reduction in volume and a 17.24% reduction in weight of the radiation shielding compared to the reference reactor design.

In-situ investigation of helium effect on diverse precipitate/matrix interface areas in irradiated 5052 aluminum alloy

Due to its low neutron cross-section and high irradiation swelling resistance, 5052 aluminum alloy is extensively utilized in the core structure and irradiation shielding of research nuclear reactors. Indeed, irradiation-induced defects may accumulate preferentially in the precipitates of aluminum alloys during service, leading to prior impairment of these precipitates, thereby inducing the degradation of mechanical properties. The interaction between irradiation defects and precipitates under irradiation, however, remains inadequately understood. In this work, the microstructure of 5052 aluminum alloy irradiated in-situ with He+ at different temperatures and subsequent annealing was investigated by transmission electron microscopy. After 1.0 dpa irradiation at different temperatures, the evolution of He bubbles within the precipitate was greater than in the matrix, and manifested a pronounced growth threshold between 373 K and 473 K. During post-irradiation annealing, compared to the matrix, also the dynamic evolution of bubbles was observed on the inner side of the precipitate interface, where bubbles coalesced and rapidly dissolved. The dynamic behavior of He bubbles within different precipitates manifested a certain discrepancy, and sink strength of two typical Al-containing precipitates was estimated. The difference in bubble evolution can be attributed to the different sink efficiency and vacancy concentration gradient around the precipitate.

Synergistic effects of Gd2O3 and SiO2 in enhancing the acoustic, mechanical, and shielding qualities of borate glasses

This study comprehensively analyzes the gamma radiation shielding, mechanical, and acoustic properties of novel glass composites formulated from B2O3, SiO2, and Gd2O3. Utilizing the MCNPX simulation code and Phy-X: PSD software, key parameters such as Linear Attenuation Coefficient, Half Value Layer (HVL), Mean Free Path (MFP), and Effective Atomic Number (Zeff) were meticulously evaluated for three distinct glass compositions, denoted as GL-1, GL-2, and GL-3. The investigation revealed that incorporating Gd2O3 and SiO2 notably enhances the radiation shielding efficiency of these glasses, which is evident from the decreasing trends in HVL and MFP values across the series. Employing the Makishima and Mackenzie (MM) model, this study further delved into the mechanical and acoustic characteristics of the glass samples. An increase in Gd2O3 and SiO2 content, substituting B2O3, was observed to augment the bond dissociation energy and adjust the packing density, consequently improving the elastic moduli. These mechanical enhancements were quantified through measurements of Young's modulus, bulk modulus, shear modulus, and longitudinal modulus. Acoustic properties were also calculated, including Longitudinal and Transverse velocities, mean velocity, and acoustic impedance. These parameters demonstrated a consistent improvement correlating with the increasing rigidity and mechanical strength of the glass samples, particularly for the GL-3 composition. The study concludes that the GL-3 glass sample exhibits superior performance regarding gamma photon attenuation, mechanical robustness, and acoustic properties. This underscores its potential as an effective material for radiation shielding in various industrial applications, benefiting from its enhanced mechanical and acoustic features.