Gamma-ray Shielding Research Articles

Next generation gamma ray shielding blocks developed using alumina industry waste

Red mud (RM) is a hazardous by-product of alumina industry, which accumulates and pollutes the environment due to inadequate technologies for large-scale utilization. This iron rich (30–60%) RM is converted into γ-ray shielding blocks as an alternative of toxic-lead and concrete. High dense γ-ray shielding blocks were fabricated by hot compacting (HC) RM (HC-RM), RM:Ba(OH)2·H2O (HC-RMBa) and RM:Bi2O3 (HC-RMBi) close to their melting point, which assist to close the pores and thereby to attain 97 to 98% of compaction. The density of HC-RM, HC-RMBa and HC-RMBi blocks are 3.34, 4.61 and 5.23 g/cm3, respectively, which is two times higher than the cold compacted (CC) ones. The linear attenuation coefficient (µ) of HC-RM, HC-RMBa and HC-RMBi blocks are 0.0209, 0.0269 and 0.0329 mm−1, respectively at 1.33 MeV (60Co). The HC-RM, HC-RMBa and HC-RMBi samples possess 38, 49 and 60% attenuation of lead at 1.33 MeV and possess the compressive strength of 34, 243 and 283 MPa, respectively. No heavy elements were found to leach out after hot compaction. The developed shields are thermally stable and found to be suitable for building radiation shielding structures in an economically viable manner than toxic-lead and concrete.

Investigation of Gamma-Ray Shielding Properties of Bismuth Oxide Nanoparticles with a Bentonite–Gypsum Matrix

Due to the present industrial world, the risk of radioactivity is notably increasing. Thus, an appropriate shielding material needs to be designed to protect humans and the environment against radiation. In view of this, the present study aims to design new composites of the main matrix of bentonite-gypsum with a low-cost, abundant, and natural matrix. This main matrix was intercalated in various amounts with micro- and nanosized particles of bismuth oxide (Bi2O3) as the filler. Energy dispersive X-ray analysis (EDX) recognized the chemical composition of the prepared specimen. The morphology of the bentonite-gypsum specimen was tested using scanning electron microscopy (SEM). The SEM images showed the uniformity and porosity of a cross-section of samples. The NaI (Tl) scintillation detector was used with four radioactive sources (241Am, 137Cs, 133Ba, and 60Co) of various photon energies. Genie 2000 software was used to determine the area under the peak of the energy spectrum observed in the presence and absence of each specimen. Then, the linear and mass attenuation coefficients were obtained. After comparing the experimental results of the mass attenuation coefficient with the theoretical values from XCOM software, it was found that the experimental results were valid. The radiation shielding parameters were computed, including the mass attenuation coefficients (MAC), half-value layer (HVL), tenth-value layer (TVL), and mean free path (MFP), which are dependent on the linear attenuation coefficient. In addition, the effective atomic number and buildup factors were calculated. The results of all of these parameters provided the same conclusion, which confirms the improvement of the properties of γ-ray shielding materials using a mixture of bentonite and gypsum as the main matrix, which is much better than using bentonite alone. Moreover, bentonite mixed with gypsum is a more economical means of production. Therefore, the investigated bentonite-gypsum materials have potential uses in applications such as gamma-ray shielding materials.

Examinations of mechanical, and shielding properties of CeO2 reinforced B2O3–ZnF2–Er2O3–ZnO glasses for gamma-ray shield and neutron applications

The glass system 75B2O3 - 4.5ZnF2 – 0.5 Er2O3–(20−x) ZnO- x CeO2, x = (0 ≤ x ≤ 1 mol. %) was manufactured using a melt quenching process, with CeO2 substituted for ZnO in the glass matrix in concentrations ranging from 0 to 1 mol %. The Makishima–Mackenzie model and sound wave velocity measurements were used to evaluate the mechanical parameters and elastic characteristics of the examined glass system, respectively. The results showed that increasing CeO2 doping ratio from 0 to 1 mol% increased density, sound velocities, elastic properties, and microhardness from 5.80 to 9.01 GPa. Phy-X/PSD software was employed to assess the effect of replacing ZnO with CeO2 on shielding capacity. The obtained results revealed that replacing ZnO with CeO2 enhances shielding characteristics and the manufactured glass may be useful in shielding applications.

Assessment of the Usability of a Composite Containing Boron Carbide for Shielding the Gamma Rays

Considering the negative effects on the environment and toxicity of lead, which has been widely used for gamma shielding for a long time in nuclear technology, studies have been focused on the development of various materials that can be used as an alternative to lead in gamma radiation shielding. In this research, a composite material containing magnetite and boron carbide (epoxy/magnetite/boron carbide) and gamma transmission technique which is emphasized in nuclear applications have been used for the study of gamma ray shielding. The radiation sources considered for this technique are the radioisotopes Am-241, Cs-137, Na-22 and Co-60, which are important in nuclear technology. The interactions between the composite material and gammas with 59.5, 511, 661.6, 1173.2, 1274.5 and 1332.5 keV energies were investigated separately by the Monte Carlo method, and the ability of the material to shield the radiations at these energies was investigated. Gamma rays, one by one, followed by using cross sections and determining the probability of interaction with the composite from the point they are emitted until they leave the system (through escaping or absorption from the system) in the Monte Carlo code, which is written to determine the linear attenuation coefficient, mean free path, half value layer and tenth value layer, among the radiation shielding parameters of the composite under investigation. The shielding parameters calculated using the simulation results were also calculated using the data obtained from the XCOM software, and the results were found to be compatible with each other. On the other hand, in order to better evaluate the usability of the composite as an alternative shielding material for nuclear applications in the studied energy range, a comparison was made with the shielding parameters of various materials available in the literature.

Evaluation of the Tungsten trioxide performance on polyepoxides radiation shielding strength

The interest of this work is to improve the gamma-ray shielding capacity of polyepoxides resin using tungsten trioxide (WO3). Therefore, the polyepoxides resin is partially substituted by the WO3 compound to produce three tungsten-doped polyepoxides samples with WO3 concentrations between 0 and 10 wt%. The measurement of the density of the fabricated composite showed an enhancement in the density of the composites from 1.103 g/cm3 to 1.197 g/cm3 by raising the WO3 concentration between 0 and 10 wt%. The distribution of the WO3 compounds inside the polyepoxides resin is affirmed using the scanning electron microscope. Moreover, in order to identify the performance of WO3 on polyepoxides to boost the radiation shielding strength the γ-ray shielding parameters such as linear attenuation coefficients, and transmission factor have been evaluated using The Monte Carlo simulation in γ-ray energy interval between 59 and 1408 keV. The results demonstrated that the linear attenuation coefficient of the fabricated composites enhanced with enrichment of WO3 content where the μ values enhanced by a factor of 141% (at 59 keV), 23% (at 305 keV), 10% (at 661 keV), and 7% (at 1408 keV) when the WO3 concentration increased between 0 and 10 wt%. Hence, it can be stated that the additives WO3 enlarge the shielding ability of polyepoxides in the γ-ray energy below 661 keV.

Investigation of gamma shielding parameters of some silica borotellurite glasses with different amount of Bi[formula omitted]O[formula omitted] at energies between 10 and 150 keV

A newly developed computer code GRASP to calculate some gamma ray shielding parameters has been introduced. Mass attenuation coefficients, effective atomic numbers, half-value layers and mean free paths of TeO2-B2O3-SiO2 glasses with different amounts of Bi2O3 have been studied in detail for photon energies between 10 and 150 keV. The mass attenuation coefficients determined with GRASP are in good agreement with the ones calculated with XCOM. GRASP can be used to determine various shielding parameters as an alternative to the existing programs. All the parameters calculated with GRASP suggest that gamma shielding capability of the glasses studied gets better as the amount of Bi2O3 in the glass increases.

Impacts of praseodymium (III, IV) oxide on physical, optical, and gamma-ray shielding properties of boro-silicate glasses

The present work aims to study the influence of Pr3+ ions on the structural, optical, and gamma-ray shielding properties of borosilicate glasses. Therefore, a new series of boro-silicate glass reinforced by small concentrations of praseodymium oxide varied between 0 and 1 mol.%. The XRD was utilized to emphasize the amorphous phase of the fabricated glasses. Moreover, UV–Vis Spectroscopy is used to detect the absorbance which is used to evaluate the energy band gap (Eg, eV) and Urbach energy (Eu, eV). The optical results showed that the energy band gap for direct transition decreased from 3.508 eV to 3.086 eV and decreased for the indirect transition from 3.086 eV to 2.879 eV with raising the Pr6O11 concentration in the fabricated glasses. The Monte Carlo simulation method was applied to simulate the average track length of γ-photons inside the fabricated boro-silicate. The linear attenuation coefficient for the fabricated boro-silicate glasses was enhanced by factors of 2.56 times (at 26 keV), 2.68 (at 103 keV), and 1.05 times (at 511 keV) with raising the Pr6O11 concentration between 0 and 1 mol.%. The result depicts no considerable change in the γ-ray shielding properties observed at γ energy ≥511 keV.

Physico-mechanical and shielding properties of alkali-activated slag composites incorporating cement clinker aggregate: Effect of high temperature and particle size

The purpose of this research was to see how cement clinker aggregates (CCA) and curing temperature affected the physico-mechanical and shielding properties of alkali-activated composites (AAC) exposed to high temperature. The precursor used to create AAC was ground blast furnace slag (GBFS), which was activated using a solution of sodium silicate (Na2SiO3) and sodium hydroxide (NaOH). Quarts powder with a size range of 0–0.5 mm and CCA in two different size ranges (0–4 mm and 4–8 mm) were used as fine and coarse aggregates in the fabrication of AAC. Four different AAC mixes were produced which were cured by three curing temperatures at 25 °C (air curing), 40 °C, and 80 °C for 8 h. The impacts of curing temperature and CCA size and content were examined on the AAC's flowability, compressive strength, flexural strength, porosity, dry unit weight, and water absorption and sorptivity characteristics. The high temperature performance and shielding properties of the produced blends was also assessed. Microstructure investigations of AAC mixtures produced within the scope of the study were also carried out based on FTIR and SEM. The obtained results implied that compressive strength of up to 80.80 MPa was attained with the use of CCA at curing temperature of 80 °C. The M4 containing the highest CCA content with the sizes of 4–8 mm and the lowest CCA content with the sizes of 0–4 mm exhibited the lowest strength at all curing temperatures. All AAC mixes regardless of curing temperature lost more than 60% of their initial compressive strength after 300 °C. Finally, among the AAC mixtures, whose gamma-ray shielding properties were examined in the photon energy range of 81–661 keV and whose fast neutron dose rates were determined, 0–4 mm particle size Clinker doped M1 sample showed better nuclear shielding ability compared to other mixtures studied.

Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis

Lead is typically utilized for X/gamma ray shielding and hazard dosage diminishing. The improper recycling of lead can cause serious hazards to the environment and human beings. In contrast, the recycling of lead from gamma-ray shielding materials with high metal content can be used as a secondary metal source, which contributes to the regulated accumulation and environment protection. Therefore, primary study on lead recovery from waste flexible Vinyl-Methyl-Silicone based gamma-ray shielding materials is conducted. The effects of pyrolysis temperature and heating rate on the lead recovery rates were analyzed. With the optimized pyrolysis conditions, 57.40 wt% lead was obtained at a pyrolysis temperature of 300 °C and duration of 15 min. The solid product is mainly a mixture of lead and lead oxides.

The impact of SrO on borophosphate glasses: synthesis, structure, optical properties as well as gamma-ray shielding performance

The impact of SrO on borophosphate glasses: synthesis, structure, optical properties as well as gamma-ray shielding performance

Study of Gamma-ray Shielding of Two Different Heavy Metals and their Combination for Cs-137 and Co-60 Sources

This article presents data collected by measurements of lead (Pb) and iron (Fe) and their combination as heavy shielding materials. Measurements were performed using gamma photon energies of 662, 1173, and 1332keV for the Cs-137 and Co-60 sources. The theoretical data part was calculated using WinXCom, Phy-X, and Py-MLUBF software packages. Tables and graphs of the photon Mass Attenuation Coefficient (MAC), Linear Attenuation Coefficient (LAC), Half Value Layer (HVL), Tenth Value Layer (TVL) and Mean Free Path (MFP) are presented for both heavy metals and their combination to study the shielding properties experimentally and theoretically. The results will contribute to the ongoing research as a database for future use.

Correction to: 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

Correction to: 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

Investigation of the Influence of TeO2 on the Elastic and Radiation Shielding Capabilities of Phospho-Tellurite Glasses Doped With Sm2O3

The impact of TeO2 on the elastic and radiation shielding properties of phospho-tellurite glasses doped with varying amounts of Sm2O3 has been studied. The elastic properties, such as packing factor, packing density, Young’s modulus, bulk modulus, shear modulus, and Poisson’s ratio, were determined by using the Makashima-Mackenzie and Rocherulle models. The gamma-ray shielding parameters, such as mass attenuation coefficient, half-value layer, tenth-value layer, effective atomic number, equivalent atomic number, exposure buildup factor, and energy absorption buildup factor, were calculated using Phy-X/PSD software in the energy range from 0.015 to 15 MeV at penetration depths up to 40 mean free paths for selected glasses. The fast neutron removal cross section was also determined using Phy-X/PSD software. The results show that the mass attenuation coefficient decreases with increasing photon energy but is not influenced by the addition of Sm2O3. The exposure buildup factor values and energy absorption buildup factors have lower values in the low- and high-energy regions and higher values in the intermediate energy region. The 1.5 mol % concentration of Sm2O3 in the selected glass shows higher exposure buildup factor and energy absorption buildup factor values in the intermediate energy region. Among the selected glasses, PZBTS1.5 has the highest value of fast neutron removal cross sections. 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.

Electrical and gamma ray shielding characteristics of zinc-borovanadate glasses mixed with MnO

Electrical and gamma ray shielding characteristics of zinc-borovanadate glasses mixed with MnO

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.