Radiation Shielding Capability Research Articles

Characterization of Radiation Shielding Capabilities of High Concentration PLA-W Composite for 3D Printing of Radiation Therapy Collimators.

This work evaluates the radiation shielding capabilities of the PLA-W composite for MV energy photons emitted by a linear accelerator and the feasibility of manufacturing a clinically-used collimator grid in spatially fractionated radiotherapy (SFRT) using the material extrusion (MEX) 3D printing technique. The PLA-W filament used has a W concentration of 93% w/w and a green density of 7.51 g/cm3, characteristics that make it suitable for this purpose. Relevant parameters such as the density and homogeneity distribution of W in the manufactured samples determine the mass attenuation coefficient, directly affecting the radiation shielding capacities, so different printing parameters were evaluated, such as layer height, deposition speed, nozzle temperature, and infill, to improve the protection performance of the samples. Additionally, physical and mechanical tests were conducted to ensure structural stability and spatial variability over time, which are critical to ensure precise spatial modulation of radiation. Finally, a complete collimator grid measuring 9.3 × 9.3 × 7.1 cm3 (consisting of 39 conical collimators with a diameter of 0.92 cm and center-to-center spacing of 1.42 cm) was manufactured and experimentally evaluated on a clinical linear accelerator to measure the radiation shielding and dosimetric parameters such as mass attenuation coefficient, half-value layer (HVL), dosimetric collimator field size, and inter-collimator transmission using radiochromic films and 2D diode array detectors, obtaining values of 0.04692 cm2/g, 2.138 cm, 1.40 cm, and 15.6%, respectively, for the parameters in the study. This shows the viability of constructing a clinically-used collimator grid through 3D printing.

Nuclear power plant pipeline detection robot based on a new radiation-proof material

Soft robots are gradually gaining recognition in recent years for their ability to work in extreme environments. However, radiation shielding is a major issue when designing soft robots for use in nuclear environments. In this paper we present an effective soft robot design and develop new radiation shielding materials that enable the robot to perform a variety of tasks in the complex pipelines of a nuclear power plant while being sufficiently radiation shielded. To achieve this, we used a mixture of silicone and lead powder with excellent radiation shielding capabilities and designed and built a soft robot prototype consisting of multiple pneumatic actuators and a resin frame. It is capable of moving through complex pipelines and performing inspection tasks, while also providing radiation shielding for the internal components of the robot. Finite element simulations and prototype experiments were then carried out to evaluate the robot's performance in various scenarios. Simulation results show that the soft robot is able to perform inspection of nuclear power plant pipelines efficiently and effectively. Furthermore, the radiation shielding provided by the radiation-proof material is effective in protecting the internal components of the robot from radiation exposure. In conclusion, we have successfully developed a soft robot prototype that is capable of performing pipeline inspections in extreme environments such as nuclear power plants, while providing adequate radiation shielding. The proposed approach can be extended to other soft robotics applications in the nuclear environment and has the potential to improve the safety and efficiency of nuclear power plant operations.

Nuclear radiation shielding performance of the new lead‐free TeO2–Bi2O3–ZnO–BaF2glass

AbstractThis paper studied the radiation shielding properties of new lead‐free telluride glass with different BaF2content. The 65TeO2–15Bi2O3–(20 − x)ZnO–xBaF2glass systems (wherex = 1, 3, 5, 7, 9 mol%) were tested through the X‐ray diffraction, ultraviolet–visible spectrophotometer, and differential scanning calorimetry. The glass system exhibited good thermal stability and a uniform surface without surface crystallization. The linear attenuation coefficient of the TBZBF series glass was tested using five different gamma radiation sources (241Am,133Ba,57Co,137Cs, and60Co). They were calculated to the mass attenuation coefficient, half‐value layer, mean free path, and effective atomic number through numerical simulations with XCOM software. The maximum mass attenuation coefficient for TBZBF‐9 was calculated to be 5.3577 cm2/g. Comparisons were made between this glass system and other tellurite and leaded glasses reported in the literature. The glass system exhibited superior radiation shielding capability compared to leaded tellurite glass under the same testing conditions. The gamma radiation shielding capacity increased with BaF2content in the glass system. These results show that TBZBF‐9 exhibited the best gamma radiation shielding effectiveness while maintaining glass transparency.

Advancements and environmental considerations in portland cement-based radiation shielding concrete: Materials, properties, and applications in nuclear power plants– review

Radiation Shielding Concrete plays a critical role in safeguarding against ionizing radiation, in nuclear power plants, medical facilities, and other radiation-sensitive environments. This review paper presents a comprehensive examination of radiation shielding concrete development, highlighting a novel approach that incorporates a diverse range of natural and industrial materials. Traditional radiation shielding concrete formulations rely heavily on virgin materials, contributing to environmental degradation and resource depletion. In contrast, this paper explores the innovative use of natural materials, industrial by-products, and waste materials, emphasizing the environmental sustainability and resource efficiency of such approaches. By harnessing these alternative materials, the paper outlines how radiation shielding concrete production can significantly reduce its ecological footprint while maintaining or even enhancing its radiation shielding capabilities. The paper delves into the functional aspects, composition variations, and performance characteristics of radiation shielding concrete, providing a holistic perspective on the diverse materials employed. Additionally, it thoroughly examines the factors influencing the effectiveness of radiation shielding concrete in nuclear power plants. Furthermore, this review discusses recent developments and advancements in radiation shielding concrete, offering insights into the cutting-edge research and innovations that are shaping the future of radiation shielding. The integration of natural and industrial materials presents promising avenues for enhancing the versatility, cost-effectiveness, and sustainability of radiation shielding concrete.

A comparative study of the activation energy and shielding properties of some binary and ternary echo-friendly alloys reinforced by Bi substitutes Zn particles for radiation protection

The thermal and mechanical stability besides environmentally friendly of some low-melting binary systems dopant with third element such as Bi started to gain much attention. This study provides the synthesized, effects of rapid solidification processing (RSP) and Bi doping on the microstructural, mechanical performance and gamma radiation shielding of various lead-free binary and ternary alloys have compositions Sn-(50-x)Zn-xBi (where x = 0, 10, 20, 30 and 40 wt.%) using high cooling rate. Microstructure modifications, elastic and plastic behavior were investigated. As well as the gamma-ray shielding performance of all as-prepared melt-spun process alloys was examined experimentally using FH 40G dose rate measuring unit. Phy-X/PSD software was used to compute the μ m values across a large energy range of 0.015 MeV–15 MeV. To clearly understand the gamma radiation shielding capability of the melt-spun process alloys, different shielding parameters includes linear attenuation coefficients, LAC, mass attenuation coefficient, MAC, mean free path, MFP, half value layer (HVL) and tenth value layer (TVL) were calculated and compared to other commonly shielding materials. X-ray diffraction (XRD) analysis confirms the presence of different phases such as β-Sn, Bi, Zn as well as two IMCs Sn0.95Bi0.05 and Sn0.85Zn0.15. The morphology features of the samples using scanning electron microscopy (SEM) revealed that Bi particles dopant the matrix led to refine the microstructures as well as forming a uniform and homogeneous distribution of IMCs. It is also, reported that the increase of Bi dopant led to enhancing the Bi segregation in the matrix in addition to decreasing the crystallite size which reinforces the mechanical strength and radiation shielding properties. The elastic modulus and Vickers microhardness increase with increasing Bi additions to about 35% and 27%, respectively. The results showed that correlation between activation energy and shielding properties of as-prepared alloys. The mass and linear attenuation coefficient for all prepared samples increases as Bi increases from 10 to 40 wt.%. On the other hand, low activation energies indicate easier formation and growth of IMCs. The results also show that the Sn-10Zn-40Bi alloy has the highest mechanical and shielding attenuation properties. It may be attributed to promoting the brittleness of Bi, refinement of crystallite size, extended the solid solubility and microstructure features accompanying Bi content using rapid cooling. As a result, Sn-10Zn-40Bi alloy may be recommended as a preferable alloy for radiation shielding performance to be used for medical, industrial and nuclear waste storage fields. In the current work, an attempt has been made not only to summarize the various investigations made so far on visualizing the feasibility of alloys as radiation shielding material; but also, to provide a comparative study for further consideration to be used in other fields.

Comparative study between micro- and nano-carbon with epoxy for gamma shielding applications

In the current study, the epoxy material was mixed with 10%, and 30% weight percent carbon material as filler in different thicknesses (1 cm, 1.5 cm, and 2 cm). Transmission electron microscope (TEM) measurements showed the average size of the nano-carbon was 20 nm with a standard deviation of 5 nm. The morphology of samples was examined using scanning electron microscopy (SEM), which showed the flatness of the epoxy surface, and when the content of carbon increases, the connection between the epoxy array and carbon increases. The compression test indicates the effect of nano-size on enhancing the mechanical properties of the studied samples. To survey the shielding properties of the epoxy/carbon composites using gamma-rays emitted from Am-241, Ba-133, Cs-137, Co-60, and Eu-152 sources, which covered a wide range of energies from 0.059 up to 1.408 MeV, the gamma intensity was measured using the NaI (Tl) detector. The linear and mass attenuation coefficients were calculated by obtaining the area under each peak of the energy spectrum observed from Genie 2000 software in the presence and absence of the sample. The experimental results obtained were compared theoretically with XCOM software. The comparison examined the validity of experimental results where the relative division rate ranged between 0.02 and 2%. Also, the measurement of the relative division rate between linear attenuation coefficients of micro- and nano-composites was found to range from 0.9 to 21% The other shielding parameters are calculated at the same range of energy, such as a half-value layer (HVL), mean free path (MFP), tenth-value layer (TVL), effective atomic number (Zeff), and the buildup factors (EBF and EABF). The data revealed a consistent reduction in the particle size of the shielding material across various weight percentages, resulting in enhanced radiation shielding capabilities. The sample that contains 30% nano-carbon has the lowest values of TVL (29.4 cm) and HVL (8.85 cm); moreover, it has the highest value of the linear attenuation coefficient (LAC), which makes it the best in its ability to attenuate radiation.

Radiation shielding capability and exposure buildup factor of cerium(iv) oxide-reinforced polyester resins

Abstract The radiation shielding characteristics of the polyester resin composites reinforced with cerium(iv) oxide (CeO2) have been studied. The prepared composites were pure polyester–resin (Poly/CeO2-0), 90% per weight polyester resin and 10% CeO2 (Poly/CeO2-10), (Poly/CeO2-30), (Poly/CeO2-50), and (Poly/CeO2-60). The linear attenuation coefficient (LAC) values for the free polyester and polyester samples with CeO2 were experimentally measured compared with the XCOM data. The experimental LAC value was found to be 0.2377 cm−1 at 0.0595 MeV, which is in good agreement with the calculated value of 0.2454 cm−1. Also, for the same sample, the experimental LAC was found to be 0.1034 cm−1 at 0.662 MeV, showing a good agreement with the calculated value of 0.1057 cm−1. The LAC values for the free polyester, Pol/CeO2-30, and Pol/CeO2-60 are 1.43, 31.82, and 107.77 cm−1 at 0.015 MeV, respectively. The big difference in the LAC values between the composite with 0 and 60% CeO2 is evident. The radiation shielding efficiency (RSE) of the polyester with different amounts of CeO2 was experimentally measured at four energy values. Also, we extended the calculation of RSE at other energy values in the range of 0.015–15 MeV). The exposure buildup factor (EBF) values for the free CeO2 sample and the samples with CeO2 are calculated. The EBF is small at low energies, then increases, and attains a maximum value at moderate energy; the EBF shows a decreasing trend with an increase in the energy.

Gamma radiation shielding by titanium alloy reinforced by polymeric composite materials

The Ti-6Al-4V alloy (TAV) has several desirable properties, including high density, strength, low corrosion, biocompatibility, and flexibility. Based on these attractive features, we study the gamma radiation shielding capabilities of a titanium alloy TAV strengthened by polymeric composite materials. Examining the TAV alloy demonstrates discernible X-ray diffraction (XRD) peaks corresponding to specific crystallographic planes, showing its crystalline nature. The produced composites exhibit mass attenuation coefficient (μm) values that are very competitive compared to those of other shielding materials recorded in the current literature. The study results provide compelling evidence that incorporating TAV into polymeric composites has considerable promise in their effectiveness as gamma radiation shielding materials. These favorable features can be attributable to a high strength-to-weight ratio, corrosion resistance, non-magnetic properties, and biocompatibility. This work describes the photon attenuation characteristics and performance of an innovative polymer composite constructed with a matrix reinforced with four different TAV content proportions (20, 30, 40, and 50 wt%). Composite materials significantly improve μm values, particularly as their density increases, especially at lower gamma energy levels. The attributes make composites highly suitable for utilization in the fields of radiation and diagnostics, where the presence of adequate shielding is of utmost importance. At the energy level of 662 keV, the μm of the shielding material exhibited a notable increase as the amount of TAV was gradually raised, reaching 0.075 at a loading rate of 20% and significantly improving to 0.136 at a loading rate of 50%. The study reveals that the half-value layer (HVL) of composites increases with the energy level of the incoming gamma photons, indicating that the composites can attenuate low-energy gamma radiation and that higher-energy photons require larger thicknesses. The HVL also depends on the amount of material filling the polymer matrix, and its effectiveness improves as filler material increases.

Sm2O3 doping-adjusted radiation shielding properties and optical stability under sunlight irradiation of B2O3–Na2O–Sm2O3–Fe2O3 glass

In this work, we prepared sodium borate glass doped with different amounts of iron oxide (Fe2O3) and samarium oxide (Sm2O3). The effects of replacing Fe2O3 with Sm2O3 on the absorbance, optical band gap, Urbach energy, and radiation shielding parameters were studied. With further additions of Sm2O3, the optical band gap values increased from 2.50 to 2.67 eV, while Urbach energy values decreased from 0.49 to 0.42 eV. Further, we explored the effect of sunlight on the absorbance, optical band gaps, and Urbach energy at 90 min of irradiation time. With further exposure to sunlight, the values of the optical band gaps decreased and Urbach energy increased as the exposure time increased from 0 to 90 min. Moreover, the percent of change in absorbance, optical band gap, Urbach energy, refractive index, nonlinear refractive index and third order susceptibility for the glass samples containing the highest concentration of Sm2O3 is insignificant (<10%). The small percentage changes in absorbance, optical band gap, and Urbach energy show that the glasses are stable when exposed to sunlight. On the other hand, the inclusion of higher concentrations of Sm2O3 leads to improved radiation shielding capabilities, as seen by the increased values of the mass attenuation coefficient and half-value layer. Herein, the investigated glasses are both more transparent and more effective at shielding radiation; they're prime candidates for use in this field.

Investigated mechanical, physical parameters and Gamma-Neutron radiation shielding of the rare earth (Er2O3/CeO2) doped barium borate glass: Role of the melting time and temperature

In this study, we aimed to explore the effects of CeO2/Er2O3, melting time, and temperature on the physical, radiation shielding, and mechanical properties of a glass composition. Specifically, we examined a glass composition comprising of 60B2O3-(40-X) BaO-XMO (where MO- Er2O3/CeO2 and X = 0.5,1.0,1.5 mol percentage). To assess the radiation shielding capabilities of the glass structure, we conducted theoretical evaluations including determining the mass Attenuation Coefficients (MAC), Fast Neutron Removal Cross-Section (FNRCS), and Mean Free Path (MFP). Furthermore, the study involved investigating the mechanical properties of borate glasses with CeO2 and Er2O3 doping, specifically examining Young's modulus, Bulk modulus, Shear modulus, and Longitudinal modulus. The obtained results were then compared. In order to determine the radiation shielding parameters, the Phy-X/PSD program and Geant4 simulation were utilized, covering an energy range from 0 to 10 MeV. The results indicate that there is strong agreement between the Phy-X/PSD and Monte Carlo simulation results for MAC values for glass samples. Our research suggests that these glasses have superior radiation shielding capabilities compared to commonly used materials for blocking radiation. This suggests that these glasses have great potential for use as effective shielding materials in radiation protection applications. It was observed that doping 1.5 mol% of Er2O3 in the lowest temperature and the longest time decreased the reflectivity of the gamma rays of the barium borate glass compared to the doping 1.5 mol% of CeO2.

Radiation attenuation characteristics of meta-schist modified Portland cement: Comparative analysis with traditional cement

As the applications of nuclear technology increase in today's world, radiation protection becomes even more crucial. Radiation shielding is significant in various applications, such as nuclear power plants, medical imaging devices, and radiotherapy rooms. This study investigates the production of meta-schist-modified Portland cement (MMPC) to protect against atomic radiation, which poses harmful environmental effects such as gamma rays, in the context of nuclear technology implementation. The samples' mass attenuation coefficient (MAC) is experimentally determined to assess their radiation shielding capabilities. The Meta-schist-modified Portland cement exhibits higher effectiveness in radiation absorption and attenuation than traditional Portland cement(OPC). Radiation shielding tests demonstrate that MMPC is a practical material for controlling radiation due to its high density and appropriate composition. Overall, the cement sample containing meta-schist shows a high potential for radiation protection applications, and the superior properties of MMPC in terms of burnability and mechanical characteristics compared to traditional Portland cement are encouraging for the use of meta-schist in cement production. The analyses of cement and clinker samples were conducted using analytical techniques such as microstructure characterization (POLYZED MICROSCOPE), X-ray diffraction (XRD), scanning electron microscopy (SEM), and energy-dispersive X-ray analysis (EDAX). This study highlights meta-schist-modified Portland cement's effective radiation protection potential and demonstrates the significance of advancing safety measures in nuclear technology applications.

Physical and radiation shielding properties for borate, boro-tellurite, and tellurite glass system modified with different modifiers: Comparative study

Two newly synthesized glass series, 10Bi2O3-20BaO-(70-x)B2O3-xTeO2, and 10MoO3-20SrO-(70-x)B2O3-xTeO2, where x = 0, 35, and 70 mol%, were fabricated using the melt-quenching technique. The fabricated glass samples' physical properties and radiation shielding capabilities were examined. The insertion of TeO2 into the glass composition increased the density values, with the glass samples labeled BBB-T70 (6.53 g/cm3) and SBM-T70 (5.66 g/cm3) exhibiting the highest density due to the increased concentration of TeO2. The addition of TeO2 led to loosely bonded glasses, indicating lower glass stability. Using SRIM and Phy-X/PSD software, the radiation shielding capabilities of the produced samples were investigated for various radiation types, including alpha particles, protons, neutrons, and gamma rays. The increase in TeO2 content and the reduction in B2O3 revealed significant increases in the linear attenuation coefficient (LAC) values and improved gamma shielding properties. For example, the LAC values at 0.283 MeV are 0.283, 0.367, 0.667, 0.902, 1.095, 1.313, and 1.55315 cm−1 for SBM-T00, SBM-T35, SBM-T70, BBB-T00, BBB-T53, and BBB-T70, respectively. However, the SBM-T00 sample exhibited lower charged particle shielding properties. The SBT-T35 and BBB-T00 samples showed the highest ability to stop fast neutrons. In conclusion, the glass samples synthesized in this work are highly recommended for shielding against various ionizing radiation sources.

Utilization of investment casting shell waste in the production of cordierite-mullite-zircon composites for radiation shielding: The influence of La2O3 additive

Cordierite-mullite-zircon ceramic composites were produced via reaction sintering of investment casting shell waste, Al2O3, and MgO at 1350 °C. The influence of La2O3 addition on the crystalline phase composition, microstructure, densification behavior, mechanical strength, and radiation shielding capabilities of the cordierite-mullite-zircon composites has been investigated. The X-ray diffraction (XRD) analysis confirmed the successful synthesis of cordierite-mullite-zircon composites with up to 5 wt% La2O3 additive content. However, a higher La2O3 content, exceeding 7 wt% resulted in cordierite decomposition. Furthermore, the addition of La2O3 significantly enhanced the densification behavior and microstructural development, leading to improved flexural strength and enhanced shielding against fast neutron and gamma radiation. This research suggests the potential of the fabricated ceramic composites derived from investment casting shell waste for applications in radiation shielding.

A Study on the Physical, Optical and Radiation Shielding Capabilities of Phosphate Zinc Telluride Glasses as a Result of ZnO/In2O3 Translocation

New In2O3-doped phosphate zinc tellurite glasses synthesized using melt-quenching method were investigated. It was observed that the synthesized glasses exhibit transparent properties. Densities of synthesized glasses changed significantly related to the doping ratio of In2O3. This implies that radiation shielding abilities can be enhanced. In other respects, the almost linear elevation in molar volume values indicated that the glass network expanded as a result of the ZnO/In2O3 translocation. As the additive ratio increases, the optical band gap value increases from 2.96 eV to 3.47 eV, while the Urbach energies decrease from 0.350 eV to 0.180 eV. In2O3 contribution has a regulatory effect on the structure of phosphate zinc tellurite glasses. In phosphate zinc tellurite glasses evaluated in terms of radiation shielding properties, it was observed that the In2O3 additive contributed significantly to the shielding properties and the glass with the best radiation shielding was 6 mol% In2O3 doped glass. It is obvious that by raising the density values of the produced glasses, the ZnO/In2O3 translocation in phosphate zinc tellurite glasses enhanced their radiation shielding properties.

Selected germanate glass systems with robust physical features for radiation protection material use

This study aimed to examine the radiation shielding capabilities of four distinct germanate glass systems with compositions of TeO2-GeO2-ZnO, B2O3-GeO2-Eu2O3-R2O3 (where RY, La and Gd), Li2O–Sb2O3- GeO2-XO (where X = Pb, Zn, Ba, Sr and Ca) and Li2O-GeO2-PbO-Nd2O3 at different photon energies ranging from 0.015 to 10 MeV respectively. The present study involved the determination of mass attenuation coefficients (MAC), effective atomic number (Zeff), and half value layer for four distinct germanate glass systems. The influence of chemical composition, sample density, and photon energy on these parameters was also discussed. The findings indicate that the substitution of TeO2 with ZnO leads to a reduction in the values of both the mass attenuation coefficient (MAC) and the effective atomic number (Zeff) in the glasses composed of TeO2-GeO2-ZnO. Furthermore, it has been discovered that within the B2O3-GeO2-Eu2O3-R2O3 glass system, the highest values of MAC are observed in the glass containing Gd2O3. The sample that contained PbO exhibited the highest MAC and Zeff values among the Li2O–Sb2O3-GeO2-XO glass systems. Furthermore, the findings of this study indicate that the glass specimen containing CaO exhibits the least values of MAC and Zeff within the given system. The findings indicate that the values of MAC in the Li2O-GeO2-PbO-Nd2O3 glass system exhibit an upward trend with the rise in Nd2O3 concentration from 0 to 2 mol%.

Compositional dependency of transparency, optical and radiation shielding parameters inside Gd2O3–Fe2O3–Na2O–SiO2–B2O3 glass

Radiation shielding glass is a promising material in the radiation shielding domain with enhanced radiation shielding properties. However, glass still has some drawbacks, such as low transparency with diverse modifier types. This low level of transparency requires essential developments. In this work, we study gadolinium oxide (Gd2O3), sodium oxide (Na2O) and iron oxide (Fe2O3) embedded in borosilicate glass for radiation shielding purposes. This glass system is characterized by high transparency and enhanced radiation shielding properties. The structural observations show that the glass density gradually increases from 2.303 to 3.42 g cm−3 with further additives of Gd2O3. Moreover, the glass transparency exhibits enhanced behavior over the studied range of Gd2O3 additions. Based on optical results, we obtained increased optical band gaps from 2.97 to 3.51 eV with higher concentrations of Gd2O3 inside the glass matrix. This increased optical band gap was attributed to the decreasing behavior of basicity and the decreased behavior of polarizability. Also, the linear and nonlinear refractive indices show decreased behavior with additional contents of Gd2O3. This behavior was discussed by the diminishing behavior of basicity and polarizability. While the inclusion of higher concentrations of Gd2O3 leads to improved radiation shielding capabilities, as seen by the increased values of the mass attenuation coefficient and half-value layer. Herein, the investigated glass samples are both more transparent and more effective at shielding radiation, making them prime candidates for use in this field.

Radiation shielding properties of glass composition

This work is an attempt to employ the glass to develop an alternative and environmentally friendly material for gamma-radiation protection applications. For this purpose, different concentrations of glasses where B2O3 added in different rate (0, 1.5,2.5,3.5 w%) were incorporated in the glass samples to produce the shielding composition. The analyzing of glass compositions was tested as protective materials against gamma-radiation by using PhX/PSD software. Different shielding parameters such as linear attenuation coefficient, half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Zeff), and effective electron density (Neff) were determined to assess the radiation shielding capability of the smaples. Furthermore, equivalent atomic number (Zeq) and the exposure buildup factor (EBF) values for photon energy in the range from 0.015 MeV to 15 MeV were also computed by Geometric Progression (G-P) method. The results demonstrated that increasing the B2O3 weight fractions in the glass samples, increases the shielding properties.

Novel slag/natural rubber composite as flexible material for protecting workers against radiation hazards

This work is an attempt to employ the electric arc furnace (EAF) slag as a by-product material to develop an alternative and environmentally friendly material for gamma-radiation protection applications such as in medical and industrial areas. For this purpose, different concentrations of micro-sized EAF slag (0, 20, 40, 60, 80, 100, 500, and 800 phr) were incorporated as fillers in the natural rubber (NR) matrix to produce the shielding composites. In addition, nano-sized EAF slag particles were prepared by using a high-energy ball milling technique to investigate the effect of particle size on the gamma-radiation shielding properties. The synthesized micro and nano EAF/NR composites were tested as protective materials against gamma-radiation by employing NaI(Tl) scintillation detector and standard radioactive point sources (152Eu, 137Cs, 133Ba, and 60Co). Different shielding parameters such as linear and mass attenuation coefficient, half value layer (HVL), tenth value layer, mean free path, effective atomic number (Zeff), and effective electron density (Neff) were determined to assess the radiation shielding capability of the EAF/NR composites. Furthermore, equivalent atomic number (Zeq) and the exposure buildup factor values for photon energy in the range from 0.015 to 15 MeV were also computed by Geometric Progression method. The experimental results of micro EAF/NR composites showed that at 121.78 keV, EAF0 composite (without EAF slag content) had the lowest μ value of 0.1695 cm−1, while the EAF800 composite (which was loaded with 800 phr of micro EAF slag) had the highest μ value of 0.2939 cm−1 at the same energy, which in turn decreases the HVL from 4.09 to 2.36 cm, respectively. Therefore, increasing the filler weight fractions of EAF slag in the NR matrix, increases the shielding properties of the composites. Moreover, the NR composite reinforced with 800 phr of nano EAF slag has better gamma-radiation shielding efficiency compared to that filled with 800 phr of micro EAF slag. The success of this work was to prepare a flexible, lightweight, low-cost, and lead-free material with better shielding capability.

Determination of X-ray and gamma-ray shielding capabilities of recycled glass derived from deteriorated silica gel

We determined the radiation shielding properties for 10CaO–xPbO–(90-x) deteriorated silica gel (DSG) glass system (x = 20, 25, 30, 35, 40, and 45 mol.%). The mass attenuation coefficient (MAC) has been estimated at photon energies of 74.23, 97.12, 122, 662, 1173, and 1332 keV using a narrow beam X-ray attenuation and transmission experiment, the XCOM program, and a PHITS simulation. The obtained MAC values were applied to estimate the half value layer (HVL), mean free path (MFP), effective atomic number, and effective electron density. Results show that the MAC value of the studied glasses ranges between 0.0549 and 1.4415 cm2/g, increases with the amount of PbO, and decreases with increasing photon energy. The HVL and MFP values decrease with increasing PbO content and increase with increasing photon energy. The recycled glass, with the addition of PbO content (20–45 mol.%), exhibited excellent radiation shielding capabilities compared to standard barite and ferrite concretes and some glass systems. Moreover, the experimental radiation shielding parameters agree with the XCOM and PHITS values. This study suggests that this new waste-recycled glass is an effective and cost-saving candidate for X-ray and gamma-ray shielding applications.

A comprehensive analysis on radiation shielding characteristics of borogypsum (boron waste) by Phy-X/PSD code

In the present study, radiation shielding characteristics of the borogypsum, which is a waste generated during the boric acid production in Turkey, was analyzed. For this purpose, we used recently developed Phy-X/PSD software, which is provided to calculate shielding parameters such as mass attenuation coefficient, linear attenuation coefficient, half-value layer, tenth-value layer, effective atomic number, total atomic cross section, total electronic cross section, effective conductivity, effective electron number, buildup factors and fast neutron removal cross section in a wide photon energy range. Additionally, mass attenuation coefficients of borogypsum were compared with those of other radiation shielding materials (ordinary concrete, obsidian, pumice, clay) in order to give a significant evaluation about the radiation shielding capability of borogypsum. Half value layer and fast neutron removal cross section values are also evaluated by other materials. It is noticed that borogypsum has higher shielding potential than other reported shielding materials.