Gamma Radiation Shielding Research Articles

Loading of rubber nanocomposites by lead nanoparticles for gamma radiation shielding

Loading of rubber nanocomposites by lead nanoparticles for gamma radiation shielding

A Monte Carlo Simulation study on the Gamma Radiation Shielding Properties of Concrete with PET Plastic Composite using the PHITS Code

The gamma radiation shielding properties of four different types of PET concretes, containing 0 %, 5 %, 10 %, and 15 % PET additives, were simulated using the PHITS code. The simulation covered photon energy levels ranging from 0.01 to 1.5 MeV and employed a NaI (Tl) scintillation detector. Parameters such as the linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half-value layer (HVL), and mean free path (MFP) were calculated to evaluate the gamma-ray attenuation for each photon energy level. The effectiveness of PET plastics as a radiation shield depends on factors like material thickness, the type of radiation, and specific application requirements. However, this research provides valuable insights into repurposing waste PET plastics to enhance the radiation-shielding properties of concrete, contributing to improved waste management practices and the development of radiation-shielding materials. The results obtained from the PHITS code align satisfactorily with both the simulation results and the theoretical XCOM data.

Impact of BaO Content on Gamma Radiation Shielding Attributes of Borosilicate Glasses at Low Energy Range

Impact of BaO Content on Gamma Radiation Shielding Attributes of Borosilicate Glasses at Low Energy Range

Sm2O3 micron plates/B4C/HDPE composites containing high specific surface area fillers for neutron and gamma-ray complex radiation shielding

In this study, a series of Sm2O3 micron plates/B4C/HDPE composites composed of synthesized Sm2O3 fillers (Sm2O3 micron plates) are prepared for shielding neutron and gamma radiation. The influence of micromorphology of Sm2O3 fillers on neutron and gamma radiation shielding properties of composites is investigated in detail. The XRD pattern reveals that the phase of synthetic Sm2O3 is cubic crystal systems, body-centered cubic lattices, and its space group is Ia 3‾ (206). SEM images and BET analyses reveal that the micromorphology of synthesized Sm2O3 is micron plates. The BET-specific surface area of the Sm2O3 fillers is increased with addition of urea content. The differential scanning calorimetry (DSC) curves reveal that Sm2O3 fillers increase the melting temperature of the composites, which is up to 138.6 °C. The thermogravimetric analysis (TGA) results reveal that the initial thermal degradation temperatures of the composites are all above 440 °C. The neutron and gamma radiation shielding tests show that Sm2O3 fillers with high BET-specific surface area (8.20 m2/g) and uniform size improve the neutron and gamma shielding rate of composites. A superior composite containing 10 wt% Sm2O3 (R = 1:25, R value represents the molar ratio of rare earth elements to urea)/20 wt% B4C/70 wt% HDPE has a neutron radiation shielding rate of 98.7% with a thickness of 15 cm under the 252Cf neutron source and a gamma radiation shielding rate of 72.1% with a thickness of 15 cm under 137Cs gamma source. And these lead-free and environment-friendly composites can be widely used in the neutron and gamma complex radiation fields.

Fired clay bricks synergistically valorizing hazardous nickel chrome-plating sludge and fly ash: Performance assessment

Nickel Chrome Plating Sludge (NCPS) is a hazardous waste containing 25%-30% nickel and chromium. Previous attempts to immobilize NCPS into fired clay bricks resulted in weakened strength due to porosity and microstructure deterioration. This study introduces co-valorization of NCPS and fly ash in fired clay bricks to address these issues. Factory-scale firing of green bricks, alongside conventional clay bricks, assessed the commercialization potential. The optimal proportion of NCPS, fly ash, and clay was found to be as 12.5:37.5:50.0, respectively. Fly ash addition significantly improved brick properties, causing compressive strength to increase from 3.2 MPa to 11.6 MPa for a NCPS content of 12.5%. Microstructural analysis highlighted fluxing oxides in NCPS, amorphous silica-alumina in fly ash, synergistic ceramic bond formation, enhanced sintering and pore filling during vitrification. The study also demonstrated substantial fuel savings of 40%-50% due to NCPS's high heat of combustion causing internal firing of green bricks. The developed bricks exhibited almost double linear attenuation coefficients, indicating enhanced gamma radiation shielding. Leaching tests confirmed successful heavy metal immobilization. This co-valorization approach not only overcomes previous drawbacks but also offers significant environmental and economic benefits in utilizing NCPS in brick production.

Gamma radiation shielding efficiency of some different ceramic composites: A comparative study

The development of a non-toxic, and low-cost material that offers good shielding against harmful ionizing radiation is highly demanded. This work offers a strategy for combining ceramic composites and carbon nanotubes to produce composites with desirable radiation shielding properties. First, we successfully prepared barium titanate (BT) ceramic by sol-gel auto-combustion method. Then, a series of CERAM-1, CERAM-2, and CERAM-3 ceramic composites were formed by inserting into BT different types of ferrite and carbon nanotubes. The crystal structural analysis indicated that all ceramic composites crystallized into a cubic structure. The crystallite sizes of the final products were calculated and were found to be 30.8 nm, 25.4 nm, 35.9 nm, and 33.1 nm for pure BT, CERAM-1, CERAM-2, and CERAM-3, respectively. The gamma radiation shielding parameters were experimentally examined at four energies ranging from low to high energy radiation. At 0.06 MeV, the ceramics have the greatest linear attenuation coefficient (LAC) values, ranging from 31.760 to 29.683 cm−1. The results showed that CERAM-1 has the greatest LAC values at 0.060 and 0.662 MeV, which indicated that CERAM-1 is the most effective shield to its advantage over the other ceramic samples at low and middle energies. Based on the obtained results, it can be concluded that various prepared ceramics can be useful for low-energy radiation protective applications.

Innovative shielding solutions by geopolymer paste and fly ash as effective substitution of cement materials for sustainable protection

This study aimed to evaluate gamma radiation shielding material based on fly ash (FA) type ASTM C 618 Class F with a sodium silicate solution with two molarity values. The composite geopolymer paste was synthesized by activating the alkaline solution and curing at 70 °C for 1 h. The sodium silicate solution was added to the FA matrix with two molarity values of SiO2/Na2O (2.2 and 3.3). The density of each sample GPp1 and GPp2 are 2.121 g/cm3 and 2.212 g/cm3, respectively. The XRD patterns revealed the successful preparation of the prepared samples. Scanning electron microscopy (SEM) and energy dispersive X-ray (EDX) determined the samples' surface morphology and elemental composition. The compressive strength of GPp2 sample was higher than for the GPp1 sample at 7 and 28 days, respectively. The density and tensile strength of the GPp2 sample are high compared to GPp1. Also, the thermal expansion coefficients for GPp2 are 5.16 × 10-4 K-1 while the GPp1 equals 2.65 × 10-4 K-1. To evaluate the photon shielding competences of the geopolymer samples, the parameters such as half-value layer (HVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Neff), and exposure buildup factor (EBF) were calculated. The highest Zeff was obtained for the GPp2 sample, whereas the lowest values were obtained for MFP, HVL, and Neff. Additionally, μm values were compared to theoretical Phy-X/PSD. It can be concluded that the investigated fly ash-based geopolymer paste is a promising material for gamma radiation shielding.

Influence of ZnCl2 on gamma attenuation and radiation shielding of tellurite glasses containing Bi2O3 and B2O3

This paper investigates the influence of ZnCl2 on the gamma attenuation and radiation shielding properties of tellurite glasses incorporating Bi2O3 and B2O3. Employing Geant4 simulation and XCOM program, the study explores the impact of varying ZnCl2 content on different gamma attenuation parameters such as linear attenuation coefficient (μ), radiation protection efficiency (RPE), effective atomic number (Zeff), and HVL. Moreover, the relation between these factors and the density of the studied glass system is discussed in details. It is found that the incremental addition of Bi2O3 significantly enhanced the photon attenuation properties of the tellurite glasses involved. The maximum Zeff values are observed at the low energy region between 0.015 and 0.1 MeV with the values of 53.016, 60.133, 65.950, 70.370, and 73.791 for the glass samples namely TBBZC1, TBBZC2, TBBZC3, TBBZC4, and TBBZC5, respectively. Furthermore, the HVL values fall between 0.0016 cm and 4.3546 cm indicates that the current glass system can be utilizes for gamma shielding applications. The results provide insights into the potential enhancement of radiation shielding efficiency in tellurite glasses, contributing valuable knowledge for the development of advanced materials in nuclear safety applications.

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.

Characterization of glasses composed of PbO, ZnO, MgO, and B2O3 in terms of their structural, optical, and gamma ray shielding properties

The amorphous glasses containing PbO, ZnO, MgO, and B2O3 have been fabricated using the melt quenching technique. The structural properties have been analysed using the Fourier-transform infrared (FTIR) and Raman spectroscopy. Derivative of Absorption Spectra Fitting (DASF) method have been used to estimate the band gap energy from the UV–Vis absorption data which decreases from 3.02 eV to 2.66 eV with increasing the concentration of the PbO.The four glass samples 0.284 and 0.826 MeV showed unique variations in terms of gamma attenuation ability. LZMB4 glass sample proved to be the mist effective in terms of shielding of gamma radiation as it requires little distance compared to LZMB3, LZMB2 and LZMB1 to attenuate. RPE revealed a raise with increase in the thickness of the material and reduces as the energy raises. TF is superior in LZMB1 compared to LZMB2, LZMB3 and LZMB4, confirming that, LZMB4 will attenuate better. The ZEff of the materials was seen falling as the energy increases, confirming that the linear attenuation coefficient of the glass materials decreases when the energy is increased. The results confirmed that, glass material LZMB4 is the best option especially for gamma radiation shielding applications compared to LZMB3, followed by LZMB2, then LZMB1.

Design and Study of Novel Composites Based on EPDM Rubber Containing Bismuth (III) Oxide and Graphene Nanoplatelets for Gamma Radiation Shielding.

The mechanical, thermal and gamma radiation attenuation properties of ethylene-propylene-diene monomer (EPDM)-based composites containing graphene nanoplatelets (GNs) and bismuth (III) oxide nanoparticles (B) were investigated. The use of polyethylene glycol (PEG) as a compatibilizer to improve the dispersion of the fillers was also investigated. The results showed that the combined use of these fillers resulted in a drastic increase in mechanical properties, reaching 123% and 83% of tensile strength and elongation at break, respectively, compared to those of EPDM. In contrast, the addition of PEG to composites containing EPDM GNs and B resulted in composites with lower values of mechanical properties compared to the EPDM/B/GN-based composite. However, the presence of PEG leads to obtaining a composite (EPDM/B/GNP) with a mass attenuation coefficient to gamma radiation (137Cs, 662 keV) superior to that composite without PEG. In addition, the composite EPDM, B and PEG exhibited an elongation at break 153% superior to unfilled EPDM. Moreover, the binary filler system consisting of 100 phr of bismuth (III) oxide and 10 phr of GN leads to reaching 61% of the linear damping coefficient of the EPDM composite compared to that value of the unfilled EPDM. The study of the morphology and the state of filler dispersion in the polymer matrix, obtained using scanning electron microscopy and energy-dispersive X-ray spectroscopy, respectively, provides a useful background for understanding the factors affecting the gamma radiation attenuation properties. Finally, the results also indicated that by adjusting the formulation, it is possible to tune the mechanical and thermal properties of EPDM composites reinforced with bismuth oxide and graphene nanoplatelets.

Gamma attenuation and radiation shielding performance of SnX (X = As, Bi, P, and Sb) monolayers

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

Exploration of optical and gamma radiation shielding characteristics of zinc oxide nanoparticles doped functionalized multi-walled carbon nanotubes nanohybrids based polyaniline ternary nanocomposites

This study explores the synthesis and characterization of polyaniline (PANI)-based nanocomposites integrated with functionalized multi-walled carbon nanotubes (FMWCNTs) and zinc oxide (ZnO) nanoparticles. Leveraging the inherent properties of PANI, such as cost-effectiveness and tunability, and the unique mechanical, electrical, and optical characteristics of FMWCNTs and ZnO, we aim to develop advanced materials suitable for applications in radiation shielding, optics, and electronics. The FMWCNTs were first functionalized to enhance their solubility and processability. Subsequently, FMWCNTs@ZnO nanocomposites were prepared and incorporated into the PANI matrix using an in-situ polymerization technique. High-resolution transmission electron microscopy (HRTEM) and X-Ray Diffraction (XRD) analyses were conducted to ascertain the morphology and structural integrity of the nanocomposites. Additionally, UV–Vis spectroscopy was employed to investigate their optical properties. It was found that there is 99.5 % increase in absorbance from pure PANI0 to PANI5 in the UV area, as well as the energy gap (Eg) diminishes as the quantity of FMWCNTs@Zn nanoparticles in the PANI matrix increases. The nanocomposites demonstrated a significant potential in gamma radiation shielding, as evidenced by their capacity to attenuate gamma radiation across various energies. This research not only provides a novel approach to designing polymer nanocomposites but also broadens the scope of their application in fields demanding advanced material properties.

Evaluation of gamma and neutron radiation shielding parameters of some glass materials by Monte Carlo and theoretical method

The present study investigates the gamma-ray and neutron shielding properties of PbCu3Ti4O12, lithium borate (Li2B4O7), lithium borate glasses doped with dolomite (CaMg(CO3)) and neodymium oxide (Nd2O3) to assess their effectiveness as shielding materials against ionizing radiation. The gamma-ray shielding properties, including the attenuation and absorption characteristics of the materials were examined and compared using Geant4-based GATE simulation, XCOM, and EpiXS in the photon energy range of 80-2000 keV. When the shielding properties of the available materials were compared, it was determined that Li2B4O7-Nd2O3, PbCu3Ti4O12, Li2B4O7-CaMg(CO3), and Li2B4O7 exhibited the best shielding properties, in order from most effective to least effective. The neutron shielding properties of these materials, including scattering, absorption, and moderation capabilities, were also determined using MRCsC, Phy-X/PSD and estimation ΣR/ρ of elements. The results were then compared with the current literature. Li2B4O7, CaMg(CO3), and Nd2O3-doped lithium borate glass samples showed higher effective fast neutron removal cross-section values than water and concrete in all calculation methods. It shows that the investigated glass materials are better gamma and neutron beam absorbers and have the potential for use in gamma and neutron beam shielding applications.

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.

Determination of variation of compositions of (1-х)ZnO-0.25Al2O3-0.25WO3-хBi2O3 glass-like ceramics on protective characteristics in gamma radiation shielding

Determination of variation of compositions of (1-х)ZnO-0.25Al2O3-0.25WO3-хBi2O3 glass-like ceramics on protective characteristics in gamma radiation shielding

Artificial Neural Network for Optimizing Gamma Radiation Shielding

Artificial Neural Network for Optimizing Gamma Radiation Shielding

Eco-friendly repurposing of by-pass waste for optics and radiation protection: addressing hazardous material challenges

This study delves into the investigation of optical and gamma radiation shielding properties of glasses formulated with varying concentrations of By-pass combined with Na2O, Fe2O3, Bi2O3, and P2O5.

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.

Radiation shielding properties of some igneous rocks in isparta province at different gamma energies: Experimental and theoretical study

In this study, our aim is to experimentally and theoretically obtain the gamma radiation shielding properties of some igneous rocks extracted in Isparta, Turkey. In the first stage, experimental measurements were performed using a gamma spectroscopy system containing a NaI(Tl) detector at three different gamma energies (511, 835 and 1275 keV) emitted from two different radioactive sources (22Na and 54Mn). As a result of the experiments, linear attenuation coefficients (LACs) of igneous rocks were obtained. The variation of LAC was investigated in relation to the density and the alkali-silica content of the rocks. The results obtained indicated an increase in the LACs with higher rock and an elevated alkali-silica ratio. Using the experimental LAC results, the half and tenth value layer thickness (HVL and TVL), mean free path (MFP), transmission rate, radiation protection efficiency (RPE) and lead equivalent thickness (dPb) values were calculated. In the second stage of this study, LACs were calculated theoretically with the help of XCOM software using the chemical contents of the selected igneous rocks. The comparison of experimentally obtained LACs with those calculated using the XCOM software, revealed a good agreement between the two methods. In addition, the results obtained with the XCOM software gave information about the variation of the attenuation coefficient in different energy regions. Moreover, effective atomic number (Zeff) and electron density (Ne) parameters were calculated using XCOM and experimental results. Based on the data collected, it can be concluded that the trachy-basalt sample taken from the igneous rocks used in this study is more effective than other rocks in terms of gamma radiation shielding.