Gamma-ray Shielding Research Articles

Mechanical and radiation shielding features of lithium titanophosphate glasses doped BaO

Glasses with the formulation 15TiO2 -70P2O5 –(15−x) Li2O- x BaO x = (0 ≤ x ≤ 10 mol. %) are fabricate by the melt quenching procedure. As BaO concentration increased, the observed density increased and the predicted molar volume decreases. To assess the elastic properties of glasses, ultrasonic velocities were measured. Ultrasonic velocities (VL&VT) increases as the amount of BaO content increases. The higher connection strength of BaO proportional to Li2O as well as an increment in coordination number results in an increment in elastic moduli. The Phy-X/PSD program was also used to describe the samples' gamma-ray shielding parameters, like the mass attenuation coefficient (MAC) (cm2/g). According to studies on radiation shielding in glasses, the BaO content is the only factor affecting the radiation shielding phenomenon. All the samples have (MAC) values of 7.868, 9.177, 10.432, 12.794, 13.907, and 0.021, 0.022, 0.022, 0.023, and 0.024 at lower and higher energies. One can deduce that BaO reinforcement has multiple functions, including increasing the density of comparable glass compositions and thus their mechanical and gamma-ray shielding properties. This study suggests, there is a strong correlation between the mechanical and radiation properties of the glasses.

Mechanical, Durability, and Gamma Ray Shielding Characteristics of Heavyweight Concrete Containing Serpentine Aggregates and Lead Waste Slag

Heavyweight concrete is used to prevent harmful radiation for the construction of hospital, military, and nuclear power plants and also to increase the durability for the construction of marine concrete structures. In this research, using a combination of serpentine aggregates and lead slag, the mechanical, durability, impact resistance, and shielding properties of heavyweight concrete were examined. The variables included fine and coarse serpentine aggregates, which were replaced with normal fine and coarse aggregates in amounts of 0, 25, 50, and 100 percent, respectively. The lead slag in all samples was considered constant. Slump, compressive strength, flexural strength, water penetration depth, impact resistance (drop hammer), and gamma ray attenuation coefficient tests were conducted. The chemical composition of serpentine aggregates and lead slag were evaluated by X-ray powder diffraction. The results showed that the density and linear attenuation coefficient (LAC) increased with the increase of fine and coarse serpentine aggregates in heavyweight concrete containing lead slag. The highest density and LAC were obtained in a sample in which 100% fine serpentine aggregates and 100% coarse serpentine aggregates were used. Using 25% of serpentine fine aggregates and 25% of serpentine coarse aggregates in heavyweight concrete samples containing lead slag has achieved the highest compressive strength and flexural strength. But with the increase of fine and coarse serpentine aggregates to more than 25%, the upward trend of increasing compressive strength decreased. Silica constitutes a large part of the chemical structure of serpentine aggregates (about 42%). Increasing the amount of serpentine aggregates in concrete mixes leads to excessive release of calcium hydroxide in concrete. This issue can lead to the formation of a weak zone in concrete and decrease the compressive and impact resistance.

A closer look at the structure and gamma-ray shielding properties of newly designed boro -tellurite glasses reinforced by bismuth (III) oxide

This work presents the synthesis and preparation of a new glass system described by the equation of (70-x) B2O3–5TeO2 –20SrCO3–5ZnO –xBi2O3, x = 0, 1, 5, 10, and 15 mol. %, using the melt quenching technique at a melting temperature of 1100 °C. The photon-shielding characteristics mainly the linear attenuation coefficient (LAC) of the prepared glass samples were evaluated using Monte Carlo (MC) simulation N-particle transport code (MCNP-5) at gamma-ray energy extended from 59 keV to 1408 keV emitted by the radioisotopes Am-241, Ba-133, Cs-137, Co-60, Na-22, and Eu-152. Furthermore, we observed that the Bi2O3 content of the glasses had a significantly stronger impact on the LAC at 59 and 356 keV. The study of the lead equivalent thickness shows that the performance of fabricated glass sample with 15 mol.% of Bi2O3 is four times less than the performance of pure lead at low gamma photon energy while it is enhanced and became two times lower the perforce of pure lead at high energy. Therefore, the fabricated glasses special sample with 15 mol.% of Bi2O3 has good shielding properties in low, intermediate, and high energy intervals.

PbO-TeO2-MgO-Na2O-B2O3 glasses: Optical properties and gamma ray shielding behaviour studies using the Monte Carlo simulation

Melt quenching is used to make the PbO-TeO2-MgO-Na2O-B2O3 glasses. As lead concentration rises, so does density rise from 3.283 to 3.923 g/cm3. The indirect band gap values decrease from 3.262 to 3.111 eV as lead oxide increases. The refractive index (n), optical dielectric constant, and dielectric constant (ε) increase from 2.329 to 2.368, 4.428 – 4.606, and 5.428 – 5.606 with the increase in lead content. The metallization value of all the samples is less than unity which confirms the non-metallic nature of all samples. The partial replacement of B2O3 by PbO compounds affects also the shielding characteristics. The Monte Carlo simulation for the gamma-ray shielding parameters depicts that the linear attenuation coefficient (LAC) of the fabricated samples increases gradually with rising the B2O3 substitution ratio. For example, at 244 keV, the linear attenuation coefficient enhances by 51% with increasing PbO content. The increase in LAC was associated with a significant decrease in the half-value thickness, thickness equivalent, and transmission factor while the radiation protection efficiency of the fabricated samples was enhanced. Therefore, fabricated glasses are considered a better choice to be used in the radiation zones.

Synthesis of Novel Li2O-CuO-Bi2O3-B2O3 Glasses for Radiation Protection: An Experimental and Theoretical Study

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

Americium-beryllium shield container optimization with new high alloyed stainless steel and composite material using MCNPX code

In this paper the goal is to optimize a shield for the americium-beryllium radioactive source, which generates a mixed neutron and gamma-ray radiation field, using two different materials designed with simultaneous moderation and absorption of neutrons and gamma-ray shielding in mind: a new type of stainless steel and epoxy resin (C21H25ClO5) composite with a 40% NiO additive. For this purpose, MCNPX was used and the equivalent dose rate for both types of radiation was calculated. After the optimization process, the shield volume experienced a 54% reduction while its weight, due to the use of a steel alloy, was increased by 3.56 %. At a distance of 1 m from the center of the source, the equivalent dose rate was reduced by 10.98% in comparison to that of the original system.

DMSO-Bismuth polymer composite as gamma radiation shield – A computational study

The present study deals with investigating several shielding parameters of Dimethyl Sulfoxide (DMSO) with varying concentration of bismuth as a filler. Exhaustive work has been done in finding the best shielding material from a multitude of materials, composites, glasses etc., by using multiple methods of study. In this study the chosen composites were explored by using the computational method of finding the shielding parameters, which are an important guide in establishing if the material selected can be a shielding material and whether it is a good option as well. The parameters computed for this study are linear attenuation and mass attenuation coefficient, half value layer (HVL), tenth value layer (TVL), mean free path (mfp), effective atomic number, effective electron density and the build-up factors for the said composites using XCOM, XMuDAT and PhyX. Upon obtaining the parameters of these composites and detailed analysis, it is observed that the attenuation coefficient increases with increase in bismuth content and the composite with 90% Bismuth showed the best results in terms of shielding. To understand the efficiency of these shielding materials, they were compared with Lead and Barite which are considered as the traditional shielding materials. From these comparisons, it is seen that 10%DMSO + 90%Bismuth is an ideal candidate for shielding of gamma rays and also proves to be light weight in contrast to the standard shielding materials.

Synthesis, physical properties, neutron, and gamma-ray shielding competence of borate-based glasses reinforced with erbium (III) oxide: a closer-look on the impact of Eu2O3

Synthesis, physical properties, neutron, and gamma-ray shielding competence of borate-based glasses reinforced with erbium (III) oxide: a closer-look on the impact of Eu2O3

Assessment of the usability conditions of Sb2O3–PbO–B2O3 glasses for shielding purposes in some medical radioisotope and a wide gamma-ray energy spectrum

Abstract We report some fundamental gamma-ray shielding properties and individual transmission factors (TFs) of five distinct glass samples with a nominal composition of xSb2O3·(40 − x)PbO·60B2O3·0.5CuO and (where; 0 ≤ x ≤ 40 mol%). Phy-X/PSD and MCNPX (version 2.7.0) Monte Carlo code are utilized to determine several critical parameters, such as cross-sections, attenuation coefficients, half and tenth value layers, build-up factors, and TFs. A general transmission setup is designed using basic requirements. Accordingly, TFs are evaluated for several medical radioisotopes. Next, the gamma-ray shielding parameters and TFs are assessed together in terms of providing the validity of the findings. Our results showed that there is a positive contribution of increasing Sb2O3 amount in the glass matrix owing its direct effect to the density increment as well. This positive effect on gamma-ray shielding properties is also observed for decreasing mean free path values from S1 to S5 samples. The exposure build-up factor (EBF) and energy absorption build-up factor (EABF) values, increasing the quantity of Sb2O3 supplementation, resulted in a general reduction in EBF and EABF values (i.e., from 0.5 to 40 mfp). When the quantity of Sb2O3 rises from S1 to S5, the collision rate of incoming gamma rays in glass samples increases significantly. The TF figures reveal that S5 showed the least transmission behavior across all the above-mentioned studied glass thicknesses. It can be concluded that increasing the Sb2O3 additive is a beneficial and monotonic technique, when the gamma-ray shielding qualities or TF values must be further enhanced.

Enhanced wide energy regions gamma ray shielding property for Bi2O3-Gd2O(CO3)2∙H2O/EP composites with strong electron cloud overlap

With the complexity of the radiation environment and the increased demand for radiation protection, there is an urgent need for high-performance and wide-energy range gamma ray shielding materials. Bi2O3 has excellent gamma ray shielding properties, while Bi exhibits weak shielding performance of low-energy gamma rays in the range of 36.4–90.5 keV. In this work, a two-step hydrothermal strategy was proposed for Bi2O3-Gd2O(CO3)2∙H2O heterostructure (h-BG) to achieve effective shielding of the materials of low-energy gamma radiation. Bi2O3-Gd2O(CO3)2∙H2O/EP-30 composite has excellent shielding performance against low, medium, and high energy gamma radiation. In addition, the shielding performance of the Bi2O3-Gd2O(CO3)2∙H2O/EP-30 composites proved to be superior to some materials in the literature of 59.5 keV. Furthermore, simulations with the Phy-X/PSD program demonstrate that Gd2O(CO3)2∙H2O combined with Bi2O3 is an adequate method for achieving gamma radiation shielding in a wide energy region. The differential charge density calculations suggest that the formation of a heterogeneous interface between Bi2O3 and Gd2O(CO3)2∙H2O leads to an overlap of the interfacial electron cloud, which increases the probability of collision between the rays and the electrons. This is an essential reason for the enhanced gamma shielding property. This work could serve as a new strategy for the design of gamma radiation shielding materials.

Sensitivity analysis of gamma-ray shielding characteristics to the TiO2 concentration in the Bi2O3–ZnO–Pb3O4–Al2O3 glass sample based on the Monte Carlo method

In this paper, the MCNP Monte Carlo (MC) code, was adopted for evaluation the properties of protection against gamma-rays of the glass system with the composition of (55-x)Bi2O3–15Pb3O4–20Al2O3–10ZnO- xTiO2 with specific concentrations of (x = 0, 5, 10, 15, 20, 25, 30 and 35 mol percent). For this purpose, several parameters related to photon attenuation such as the, Half-Value Layer (HVL), Tenth-Value Layer (TVL), mean free range (MFP), mass attenuation coefficient (μm), effective atomic number (Zeff) and buildup factor (BF) was investigated at the different energy levels between 0.1 and 1.5 MeV. To verify the results of the simulation, the data obtained from the simulation were compared with the experimental data available in the XCOM database. The NIST-XCOM database and the results of the simulation in the present study were in good agreement. The percentage deviation (PD) between the XCOM database and the MCNP program for calculating the μm was less than 0.59% in most cases. The results show that compared to conventional protective materials such as concrete and lead, the new combination shows more effective attenuation parameters. The glass with the highest concentration of TiO2 has the most favorable state in terms of density compared to the investigated protective materials. The close agreement of μm measurements with the XCOM database of this research shows that MC modeling in this research is a valuable and valid method.

Variation in gamma ray shielding properties of glasses with increasing boron oxide content

Abstract The study of radiation shielding properties for a material is an important part of research in scientific world. It is expressed in terms of the linear linear coefficients (LAC) which can also be used to obtain some other parameters. The gamma shielding properties of glass with addition of boron oxides in different amounts were studied, thereby obtaining linear attenuation coefficients (LAC), mean free path (mfp), Exposure Buildup factor (EBF) which were calculated using Phy-X/PSD code. It was found that increasing boron oxide content of 0, 2, 4, 6, 8 (w %) in glass increased the gamma attenuation coefficients.

Assessment of mechanical and gamma ray shielding capability of highly dense PbO-TeO2-CdO glasses

The highly dense PbO-TeO2-CdO glasses have been fabricated by the melt quenching procedure. The prepared samples are light yellow in colour and are highly transparent. The density of the samples is very high and it lies in the range of 5.576–6.082 g/cm3. The molar volume is showing downtrend from 35.488 to 33.705 cm3 accounting towards the compactness of the samples with addition of PbO. Oxygen packing density increases from 30.996 to 32.637 whereas the oxygen molar volume is decreasing from 32.262 to 30.641 cm3 mol−1 with increase in PbO content. As PbO grows, E's modulus rises from 18.517 to 19.368 GPa, B's from 6.903 to 7.705 GPa, G's from 9.504 to 9.662 GPa, and L's from 19575 to 20.558 GPa. We used the Phy-X software to estimate the radiation shielding properties for the prepared glasses in a wide energy range of 0.015–15 MeV. We reported an enhancement in the mass attenuation coefficient (MAC) values when the PbO level increases from 70 to 77.5 mol %, this he highest MAC is found for PTC4, while the lowest MAC is reported for PTC1 sample. The photon energy has an impact on Linear attenuation coefficient (LAC) and the Greatest values of this parameter is reported at 0.015 MeV and equalling 501.64, 521.84, 549.53 and 569.17 cm−1 for the PTC1 to PTC4 glasses. In contrast, the lowest LAC is reported at 15 MeV (in the range of 0.283–0.313 cm−1). According to the LAC, the studied samples are able to attenuate more photons in the low energy region. The effective atomic number (Zeff) is also evaluated and similar to LAC, we found that the Zeff is increased due to the addition of PbO. From the results of different shielding factors, the inclusion of PbO alters the radiation attenuation performance.

Polylactic acid tungsten trioxide reinforced composites: A study of their thermal, optical, and gamma radiation attenuation performance

In the current investigation, the gamma radiation shielding abilities, structure, and thermal and optical properties of Polylactic acid PLA have been tried to be developed by introducing tungsten trioxide WO3. PLA/WO3 composites were fabricated by a solution mixing method at different weights percent (1%, 3%, 5%, and 7%). SEM indicates the good dispersion of WO3 in the PLA matrix, and the X-ray diffraction (XRD) pattern displays the existence of recognizable peaks for PLA and WO3. The thermal properties were investigated by thermo-gravimetric analysis (TGA), which enhances the thermal stability of the PLA/WO3 composites more than pure PLA. The transmittance decreases with increasing the WO3 content in the PLA matrix while the absorption and extinction coefficients α and k as well as the refractive index, rise with the increase of the WO3 content in the PLA matrix. The radiation shielding parameters have been experimentally reported. The equipment used in the experiment consisted of a NaI detector as well as a variety of radioactive point sources that released photons with energy of 80, 238, 356, 662, 1173, 1333, and 2164 keV, respectively. Examining the linear attenuation coefficient (μ), the half-value layer (T0.5), and the radiation protection effectiveness of the PLA/WO3 composites was done in order to investigate the gamma radiation shielding capabilities of the materials (RPE). Pure PLA (free WO3) was found to have the lowest μ values, and it was discovered that increasing the WO3 content led to an improvement in the photon attenuation competency of the present epoxy. The T0.5 lengths of the PLA/WO3 composites were lowered when WO3 was added. This verified that adding WO3 increases the radiation absorption capabilities of the PLA/WO3 composites. The four different energies were tested. Based on the findings, it is possible to draw the conclusion that non-toxic, naturally occurring composites that are low in cost and have a high WO3 content could play an important part in enhancing the gamma-ray shielding capabilities of PLA/WO3 composites for low-energy radiation applications, which can used as protective cover for solar cell against harm radiation.

Gamma ray shielding and structural properties for TeO2-BaO-MO modified with Bi2O3, TiO2, MnO2, MoO3

In this study, we fabricated four glass samples of TeO2-BaO-MO (where MO = Bi2O3, TiO2, MnO2, MoO3) using the melt quench method. The structural properties were explored using different techniques such as x-ray diffraction (XRD) and Fourier transform infrared (FTIR). Moreover, the radiation shielding properties were determined using Phy-X software. The XRD results affirm the amorphous nature of current glasses. At the same time, the FTIR showed a broad peak associated with overlapping between asymmetrical stretching vibrations of the TeO3 trigonal structural and stretching vibrations of Te–O vibration in TeO4 units. The highest density was achieved by a sample containing bismuth (BTBi), followed by manganese (BTMn), molybdenum (BTMo), and titanium (BTTi), and the density values were ranged from 5.087 to 6.059 g/cm3. These results were reflected in the shielding properties in the same order. The mass attenuation coefficient (MAC) for BTBi, BTMo, BTMn, and BTTi at 0.2 MeV are 35.271, 23.520, 20.166, and 19.942 cm2/g for BTBi, BTMo, BTMn, and BTTi, respectively, indicating the superiority of the BTBi sample on the other samples in radiation shielding field. So, it is an excellent option for use in the radiation shielding field.

Physical Features of High-Density Barium–Tungstate–Phosphate (BTP) Glasses: Elastic Moduli, and Gamma Transmission Factors

We present elastic moduli, gamma radiation attenuation characteristics, and transmission factor of barium–tungstate–phosphate (BTP) glasses with the chemical formula (60-y)BaO-yWO3-40P2O5, where y = 10 (S1)–40 (S4) in steps of 10 mole%. Different types of mathematical and simulation approaches, such as the Makishima-Mackenzie model, the Monte Carlo method, and the online Phy-X/PSD software, are utilized in terms of determining these parameters. The total packing density (Vt) is enriched from 0.607 to 0.627, while the total energy dissociation (Gt) is enriched by increasing the WO3 content (from 52.2 (kJ/cm3). In the investigated glasses, increasing tungstate trioxide (WO3) contribution enhanced Young’s, shear, bulk, and longitudinal moduli. Moreover, Poisson’s ratio is improved by increasing the WO3 content in the BTP glasses. The 20BaO-40WO3-40P2O5 sample possessed the highest values of both linear (µ) and mass attenuation (µm) coefficients, i.e., (µ, µm)S4 > (µ, µm)S3 > (µ, µm)S2 > (µ, µm)S1. Moreover, the 20BaO-40WO3-40P2O5 sample had the lowest values of half (HVL) and tenth (TVL) layers, i.e., (half, tenth)S4 < (half, tenth)S3 < (half, tenth)S2 < (half, tenth)S1. The effective atomic number (Zeff) of the studied glasses has the same behavior as µ and µm. Finally, the 20BaO-40WO3-40P2O5 is reported with the minimum values of transmission factor (TF) for all the BTP investigated at a thickness of 3 cm. In conclusion, the sample with composition 20BaO-40WO3-40P2O5 which has the maximum WO3 reinforcement may be a beneficial glass sample, along with its advanced mechanical and gamma ray shielding properties.

Effect of bismuth oxide nanoparticles on the radiation shielding of bentonite clay using Fluka modeling calculations and simulation studying

This research aims to evaluate the radiation shielding ability of fabricated bentonite clay doped with xBi2O3 nanoparticles (x = 0, 10, 20, 30, and 40 wt%). Gamma-ray shielding parameters for the newly designed bentonite/Bi2O3 nanocomposites were calculated with the help of the Monte Carlo software (FLUKA), for photon energies ranging from 0.015 to 15 MeV. Five shielding parameters were measured including the nanocomposites' mass attenuation coefficient, effective atomic number, electron density, mean free path, and half-value layer. X-ray diffraction analysis, Energy dispersive X-ray and the scanning electron microscope were used to investigate the characteristics of the developed nanocomposites (structural and morphological), as well as those of the as-prepared Bi2O3 nanoparticles. The findings demonstrated that an increase in the amount of Bi2O3 nanoparticles in the bentonite clay matrix enhances the predicted gamma-ray shielding characteristics of the resulting nanocomposites. As a result, the sample of bentonite clay including 40 wt% Bi2O3 nanoparticles had the highest value for mass attenuation, effective atomic number, and electron density, and the lowest value of mean free path and half-value layer, of all the developed nanocomposites.

Effect of Polymer Shell Structure of a Gamma-ray Shielding Film Prepared Using Composite Material on Shielding Performance

Medical protective clothing should be flexible to ensure free movement of healthcare personnel. This study aimed to investigate the effects of a polymer’s physical properties on the particle composition of a shielding material, constituent component miscibility, and shielding performance. To ensure flexibility by reducing the thickness of the shielding garment, polymer-based composite materials are mainly used as shielding materials. The shielding performance varies depending on whether the polymer used is in an emulsion or powder state. In this study, we found that a shielding film manufactured through an injection process after mixing a polymer in a powder form with tungsten powder exhibited 0.95%–2.5% higher shielding performance than that manufactured using the calendering process with an emulsion polymer. The shell structure formed when using the powder polymer maintains the spacing between the particles owing to the double coating of the tungsten particles and improves their dispersion. Additionally, the primary issue when combining an emulsion polymer and shielding material, that is the aggregation between the shielding material particles and between the polymer particles, could be alleviated, resulting in improved shielding performance. We concluded that the polymer-powder mixing method contributes to the reproducibility of the process technology when manufacturing shielding films.

Physical, structural, optical, and gamma ray shielding properties of Li2O–ZnO–SiO2–P2O5 glasses doped with Nd2O3

Physical, structural, optical, and gamma ray shielding properties of Li2O–ZnO–SiO2–P2O5 glasses doped with Nd2O3

Investigation of gamma-ray shielding parameters of bismuth phospho-tellurite glasses doped with varying Sm2O3

The gamma ray shielding parameters such as mass attenuation coefficient, effective atomic number, equivalent atomic number, exposure buildup factor, and energy absorption buildup factor were determined for the 47.5P2O5+45ZnO+(5-x) Bi2O3+2.5TeO2 +xSm2O3 glass system using Phy-X/PSD software in the energy range from 0.015 to 15 MeV at penetration depths of 1–40 MFP. To understand the effect of Sm2O3 on gamma ray shielding parameters in selected glass system, the Sm2O3 was varied in the glass from 0.01 to 1 mol%. The calculated results show that the mass attenuation coefficient decreases with increasing photon energy but not influenced by the addition of Sm2O3. The Zeq values are lower in low (≤100 keV) and high energy regions (1 MeV–15 MeV) and higher in the medium energy region, indicating that the Compton scattering is significant in the medium energy region. The values of exposure buildup factors and energy absorption buildup factors are smaller in the low and high energy regions than in the intermediate energy region, indicating that the photo absorption and pair creation processes are important in the low and high energy regions, respectively. The 1% mole concentration of Sm2O3 in the selected glass shows higher exposure buildup factor and energy absorption buildup factor values in the intermediate energy region. The high density, high effective atomic number, and transparency to visible light of these materials indicate that they can be used as shielding materials in nuclear reactors and nuclear technology.