Gamma-ray Shielding Research Articles

X-ray/gamma radiation shielding properties of zinc ferrite nanoparticles synthesised via solution combustion method.

Zinc ferrite (ZnFe2O4) nanoparticles were synthesised via solution combustion method using urea as a fuel. The synthesised samples were characterised with various techniques. The cubic structure with Fd-3m space group is confirmed by Powder X-ray Diffraction and Bragg's reflection. The crystallite size estimated from Scherrer's method was found to be 40nm. The agglomerated irregular shape and sized surface morphology was confirmed by Scanning Electron Microscopy image. The direct energy band gap determined from Wood and Tauc's relation was found to be 5.25eV. Using a NaI (Tl) detector and multi-channel analyser, the described sample was examined for X-ray and gamma ray shielding characteristics in the energy range of 0.081-1.332MeV. The measured shielding values are in good agreement with the theory, however below 356keV, there is a little variation of up to 10%. The current work offers up new possibilities for using this simple, affordable, effective and low temperature approach to create nanomaterials for X-ray and gamma ray shielding.

Mössbauer spectroscopy and gamma-ray shielding performance for iron phosphate glasses containing various heavy metals oxides

Mössbauer spectroscopy analysis and gamma (γ)-ray shielding performance for some iron phosphate glasses with composition 50 %P2O5 + 20 %Na2O + 20 %Fe2O3 + 10 %X, whereX = As2O3, SrO, BaO, CdO, and Sb2O3 w.t.% were investigated. The melt quenching technique was used for glass sample preparation, where the XRD patterns investigated the amorphous nature of the prepared glasses. Moreover, SEM and EDS mapping were used to provide information on the element distribution of the added heavy metals. Mössbauer spectroscopy showed that, most of the iron is present in the glass as Fe3+oxidation state, which is composed of tetrahedral and octahedral coordination states. The remaining iron ions have the form Fe2+ which occupied the tetrahedral coordination state. The γ-ray attenuation parameters like, mass attenuation coefficient (MAC), half value layer (HVL) and the effective atomic number (Zeff) were experimentally measured at different γ-ray energies using 133Ba, 137Cs, and 60Co radioactive sources. Results indicated that the sample containing Sb2O3 is the best-modified glass for gamma radiation protection.

The role of Nb2O5 on structural, mechanical, and gamma-ray shielding characteristics of lithium molybdenum borate glasses

A series of glasses with the formula 64B2O3–16MoO3- (20-x) Li2O- xNb2O5 where x = 0 to 12, were synthesized. Utilizing XRD profiles, the amorphous state of the investigated glasses has been established. With an increase in Nb2O5 it is found that the gradual replacement of Li2O by Nb2O5 increases the density from 2.43 to 3.09 g/cm3 and the molar volume of the studied glasses decreases from 30.27 × 10−6 m3 mol−1 to 24.91 × 10−6 m3 mol−1. The addition of Nb2O5 increases the number of bridge oxygens and alters the coordination number of the glasses by forming BO4 structural units, according to the FTIR results. As the Nb2O5 increased ultrasonic velocities VL&VT also increased. VL increased from 4780 to 5150, and VT increased from 2295 to 2715 m/s. Ultrasonic velocity and elastic moduli increase as a result of structural changes brought on by an increase in BO4 at the expense of BO3. It is noted that the theoretically predicted elastic moduli utilizing Makishima-Mackenzie models (MMM) and the experimental elastic moduli indicate a very good agreement. The features of gamma-ray shielding were evaluated using the Phy-X/PSD program. It has been noted that the greatest mass & linear attenuation coefficient (MAC) & (LAC) occurred at 0.02 MeV. With an increase in energy, the half- and tenth-value layers HVL and TVL increased, while decreasing with an increase in Nb2O5. These observations suggest that the synthesized glasses are better candidates for gamma radiation shielding.

La/Nd-doped zirconium oxide: Impact of zirconia phase transition on gamma-ray shielding properties

We investigate the effect of neodymium and lanthanum on zirconia radiation shielding and structural properties. To achieve this, new La/Nd-doped ZrO2 nanomaterials were synthesized and analyzed via various experimental techniques, including energy-dispersive X-ray spectroscopy, scanning electron microscopy, transmission electron microscopy, and X-ray diffraction, to determine the fabricated materials' structure, chemical composition, and morphology. Additionally, to enable the estimation of the effect of the ZrO2 phase transition on the synthesized La/Nd-doped ZrO2 nanomaterials' γ-ray shielding properties, Monte Carlo simulation was used. The simulated data revealed that the fabricated materials' linear attenuation coefficient decreased slightly from 17.584 cm−1–17.442 cm−1 at 0.059 MeV, from 0.382 cm−1 to 0.375 cm−1 at 0.662 MeV, from 0.253 cm−1 to 0.248 cm−1 at 1.408 MeV, and from 0.180 cm−1 to 0.176 cm−1 at 15 MeV with decrease of the fraction of the tetragonal phase from 84 % to 57 %. The reduction in the linear attenuation coefficient is associated with increased thickness in terms of the fabricated materials' Pb equivalent and half values.

Electrical and gamma ray shielding properties of phospho-tellurite glasses doped with alkali and transition metal oxides

This article presents investigated results on physical, electrical and gamma radiation shielding properties of glasses of composition, (P2O5)0.25-(TeO2)0.5-x-(Na2O)0.1- (ZnO)0.15-(CoO)x (x= 0.10, 0.15, 0.20, 0.25, 030 and 0.35) were synthesized by melt quenching procedure. After confirming non-crystallinity, density was measured and found it to be decreased with increase of CoO concentration in the range 4.0370 gm/cm3 - 3.5673 gm/cm3. Molar volume, mean distance between TMIs, small polaron radius, oxygen packing density and field strength were estimated. Conductivity was measured in the temperature range 303K -663K. High temperature conductivity is found to be varied as per Mott’s (SPH) model. High temperature activation energy is found to be increased with CoO content. Low temperature conductivity variation has been analyzed using Mott’s (VRH) model. Gamma ray shielding parameters were evaluated using Phy-X/PSD software for the energy range 0.005 MeV-15 MeV. The mass and linear attenuation coefficients were found to decrease with CoO content and photon energy. Half and tenth value layers increased with increase of mole fractions of CoO. All the observed shielding parameters are superior to those reported previously for other glasses. The glass with x=0.10 is best suited for the utility of gamma shielding at low energy.

A comprehensive microstructural and transmission analysis on oxide dispersion-strengthened (ODS) alloys: Impact of erbium oxide (Er2O3) concentration on physical, structural, gamma-ray, and neutron attenuation properties

This study explores the impact of integrating varying concentrations of Erbium Oxide (Er2O3) into Oxide Dispersion Strengthened (ODS) alloys, specifically focusing on gamma-ray and neutron attenuation properties. Utilizing a 316L stainless steel matrix, Er2O3 was methodically incorporated in concentrations ranging from 1 % to 21 % by weight. The structural and radiation attenuation properties of the resultant alloys were comprehensively analyzed using techniques such as X-ray diffraction (XRD), Scanning Electron Microscopy (SEM), and experimental gamma-ray transmission studies. The results demonstrate a significant enhancement in gamma-ray shielding with increased Er2O3 content. This enhancement is quantitatively evidenced by increased linear attenuation coefficient, elevated effective Electron Density (Neff), reduced Half-Value Layers (HVL), and higher effective atomic numbers (Zeff). These findings are crucial for nuclear applications where efficient gamma-ray shielding is paramount. Conversely, a decrease in the effective removal cross section (ΣR) for neutron attenuation was observed with higher Er2O3 concentrations. This suggests a potential compromise in neutron shielding efficiency, attributed to the dilution of neutron-absorbing base elements in the alloy. Additionally, the study reveals notable changes in the microstructural properties of the alloys, including alterations in particle size, distribution, and agglomeration, influenced by varying Er2O3 concentrations. In conclusion, this research provides valuable insights into the design of ODS alloys for nuclear radiation shielding, highlighting the balance between gamma-ray attenuation and neutron shielding properties. The study's findings contribute to the development of advanced materials for safer and more efficient nuclear technology applications.

Clay-based bricks’ rich illite mineral for gamma-ray shielding applications: An experimental evaluation of the effect of pressure rates on gamma-ray attenuation parameters

Abstract The objective of this study is to increase the natural clay mineral-based bricks’ ability to shield γ-rays without the use of external doping materials. Six brick samples were consequently developed at various pressure rates (PRs). The chemical composition and structure of the manufactured bricks are unaffected by the PR applied. The main constituents in the clay used to make bricks are illite and quartz minerals, according to an X-ray diffraction pattern. Additionally, scanning electron microscopy and energy dispersion X-rays have demonstrated the morphology and chemical composition of the used clay. Besides, the Mh-300A density meter shows an increase in the fabricated bricks’ density by increasing the PR, where the brick’s density increased by 32.92% by increasing the PR from 7.61 to 114.22 MPa, respectively. Also, the effects of the PR on the radiation shielding properties of the fabricated bricks were investigated using a NaI (Tl) detector. The data reveal that increasing the PR between 7.61 and 114.22 MPa improved the linear attenuation coefficient by 44.5, 23.8, 24.2, and 24.8%, respectively, for gamma-ray energies of 0.662, 1.173, 1.252, and 1.332 MeV. The capacity of fabricated bricks to shield against radiation increases as the linear attenuation coefficient increases. The lead’s equivalent thickness and half-value thickness of the fabricated clay-based bricks, on the other hand, decreased. As a result, the compacted natural clay brick, which is a lead-free material, provides a suitable alternative for gamma-ray shielding in radioactive locations.

Sodium metaphosphate-tungsten trioxide glasses: a characterization study on gamma-ray shielding properties and transmission factors (TFs)

Sodium metaphosphate-tungsten trioxide glasses: a characterization study on gamma-ray shielding properties and transmission factors (TFs)

Fabrication of a Gd2O3-Based Film to Shield from Space Radiation inside Aircraft and Its Effectiveness

Aircraft are exposed to cosmic radiation depending on their flight altitude and latitude. Therefore, flight attendants are exposed to radiation for long periods. In this study, a 0.3 mm thick fabric was designed with which to manufacture crew clothes to shield them against external exposure to space radiation, and the shielding performance was analyzed based on empirical experiments in a real environment. Gadolinium oxide, which has a high neutron reaction cross-section, and tungsten, which is useful for gamma-ray shielding, were proposed as the main raw materials for the shielding fabric, and the shielding performance was evaluated using detectors on Arctic flight routes. Composite (KG-01) and single (KG-02) shielding materials were used. In the case of KG-01, the transmission dose rate was 90.7 ± 5.6% compared with the unshielded case, showing an average space-radiation dose reduction of 9.3%. With KG-02, the transmission dose rate was 103.1 ± 2.0% compared with the unshielded case, and the average dose rate increased by 3.1%; therefore, there was no shielding effect against space radiation. Considering the statistical error of the environmental radiation at aircraft flight altitudes, KG-01 had a shielding effect of at least 5%; however, KG-02 yielded no significant shielding effects.

Gamma-ray shielding analysis on natural rubber composites fortified with barium tungstate (BaWO4)

Emission of radiation is a significant phenomenon having impacts on various fields, and its harmful effects must be minimized. To achieve this, radiation protection and dosimetry have been developed to ensure safe radiation limits. In this experimental study, we investigated the gamma-ray shielding properties of a composite material made from natural rubber with six different proportions of Barium Tungstate (ranging from 0 to 100 phr). The study revealed that the addition of Barium Tungstate (BaWO4) to natural rubber significantly improved the characteristics of gamma radiation shielding. The composite containing maximum proportion of BaWO4 (NRBW-100) exhibited the highest linear attenuation coefficient (LAC) value, measuring 0.307 cm-1 at an energy of 662 keV. At the same energy value, the LAC values were found to vary from 0.137 to 0.307 cm-1 across samples having different concentrations of BaWO4 (0 to 100 phr). To further assess the shielding properties, simulations were conducted using the Phy-X/PSD code, and the characteristic parameters such as mass attenuation coefficient (MAC), mean free path (MFP), half-value length (HVL), tenth-value length (TVL), effective atomic number (Zeff), effective electron density (Neff), effective conductivity (Ceff), and fast neutron removal cross-section (FNRCS) were theoretically evaluated. FNRC values range from 0.068 cm-1 to 0.108 cm-1 across concentrations of BaWO4 from 0 to 100 phr. Experimental measurements showed good agreement with theoretical calculations obtained from simulation results. We have also compared the shielding characteristics of these samples with that of other commonly used materials.

Outstanding effect of cost-saving heavy nano-ferrites on the physico-mechanical properties, morphology, and gamma radiation shielding of hardened cement pastes

The purpose of this study is to synthesize heavy nano-ferrites (e.g. nano-CaFe2O4 and nano-CuFe2O4) using facile and economical sol–gel method to investigate their effect on the physico-mechanical, morphological, and gamma radiation shielding of hardened cement pastes. After the synthesis process, the nano-ferrites were characterized using transmission electron microscopy (TEM), scanning electron microscopy/energy dispersive X-ray (SEM/EDX), X-ray diffraction (XRD) and particle size distribution analyses and then admixed to ordinary Portland cement (OPC) with different doses (e.g., 0, 0.25, 0.5, 1, and 2 mass%). The physico-mechanical characteristics of the cement pastes containing different ratios of heavy nano-materials were investigated at various hydration times. SEM/EDX and FTIR techniques were employed in addition to TGA/DTG to describe the microstructure and phase composition of the different hardened pastes. Gamma linear attenuation coefficients for Cs137 (662 keV) and Co60 (1173 and 1332 keV), as well as the most essential gamma transmission characteristics (half-value layer, HVL; tenth-value layer, TVL; and mean free path, MFP), were determined for selected pastes. The results revealed that the EDX spectrum of nano-CaFe2O4 clarifies that the Fe, Ca, and O elements are clearly observed at their corresponding keV values. Moreover, EDX spectrum of nano-CuFe2O4 properly reveals the presence of Cu, Fe, and O elements. These results confirm that the obtained product was of high purity. In addition, TEM photos indicate that the particle size of nano-CaFe2O4 is in the range of 7–22 nm, while the particle size range of nano-CuFe2O4 is 8–27 nm. It was found that the cement pastes containing 1% nano-CaFe2O4 and 1% nano-CuFe2O4 were the pastes that improved the physico-mechanical properties and high gamma ray shielding properties compared to the other prepared pastes. These nano-materials have high efficiency and economic feasibility.

Novel bricks based lightweight Vietnam's white clay minerals for gamma ray shielding purposes: An extensive experimental study

In the present work, a new brick series based on the Vietnamese white clay minerals from the Bat Trang was fabricated to be applied in the radiation protection applications during the decommissioning of the nuclear power reactors. The bricks were constructed under various pressure rates varied from 7.61 MPa to 114.22 MPa. The influence of pressure rate on the physical and γ-ray shielding properties were investigated in the study. The experimental measurement for the material's density using the MH-300A density meter showed an enhancement in the prepared bricks' density by 22.5 % with increasing the applied pressure rate while the bricks' porosity reduced by 31.2 % when the pressure rate increased from 7.61 MPa to 114.22 MPa. The increase in the fabricated bricks density and the reduction in their porosities enhances the bricks' linear attenuation coefficients as measured by the NaI (Tl) detector along the energy range extended from 0.662 MeV to 1.332 MeV. The linear attenuation coefficient increased by 13.8 %, 17.6 %, 17.0 %, and 17.1 % at gamma ray energies of 0.662 MeV, 1.173 MeV, 1.252 MeV, and 1.332 MeV, respectively. The enhancement in the linear attenuation coefficient increases the bricks' radiation protection efficiency by 10.22 %, 14.48 %, 14.09 %, and 14.26 % at gamma ray energies of 0.662 MeV, 1.173 MeV, 1.252 MeV, and 1.332 MeV, respectively.

Fe-nanoparticle effect on polypropylene for effective radiation protection: Simulation and theoretical study

An evaluation of the gamma-neutron shielding capabilities of polymer nanocomposite materials based on polypropylene and iron nanoparticles is presented in this study. The chemical composition of the materials is (100-x) PP-Fex, (where x = 0.1, 0.3, 0.5, 1, 2 and 5 wt percent). For the proposed polymer samples with photon energies ranging from 30 to 2000 KeV, the mass attenuation coefficient (MAC), a crucial parameter for studying gamma-ray shielding capability, was calculated using the Geant4 Monte Carlo code. Results were compared with those predicted by EpiXS. The values of the Geant4 code and the EpiXS software were both found to be in excellent agreement. Using the mass attenuation coefficient values, we determined the linear attenuation coefficients, electron density, effective atomic number, and half value layer for all the samples. The shielding properties of the polymer samples were also evaluated by estimating both the fast neutron removal cross-section and the mean free path of the fast neutron at energies between 0.25 and 5.5 keV. The study's findings indicate a positive correlation between the Fe nanoparticle content and the gamma-ray shielding performance of PP-Fe polymer samples. Out of the several glasses that were evaluated, it was found that the PP-Fe5 polymer sample demonstrates the highest efficacy in terms of gamma-ray shielding. Moreover, the polymer sample PP-Fe5, which consists of 5 mol% of iron (Fe), exhibits the highest value of ∑R (1.10650 cm-1) and the lowest value of the mean free path for fast neutrons. This indicates that the PP-Fe5 possesses better gamma-neutron shielding efficiency.

Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor

The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that meets the neutron beam criteria recommended by the International Atomic Energy Agency (IAEA). The suggested BSA configuration consisted of a cylindrical geometry with 25 cm of MgF2 and 15 cm of Fluental® as a moderator, 15 cm of Pb as a reflector, two 5 cm Bi slabs as gamma-ray shields, and 4 mm of 6Li and 5 mm of borated polyethylene sheets as thermal neutron filters. The results showed that the epithermal neutron flux at the BSA exit was 2.3×109 n/cm2.s, and in-phantom dose analysis indicated that the designed beam could be used for the treatment of deep brain tumors within an allowable treatment time of 50 min.

Characterization and experimental investigation for gamma–ray shielding competence of basalt-doped polyethylene nanocomposites

Experimental investigations on gamma - rays attenuation parameters and dielectric spectroscopic properties were done on a polymeric mixture with chemical composition (100-x) polyethylene + x basalt, where x = 0, 1, 3, 5, 10, and 20 wt%. Using the melting blending technique,six nanocomposite polymeric samples were prepared. The linear attenuation coefficient μ of each prepared set of samples was measured using a gamma-ray spectrometer including High Purity Germanium detector (HPGe) at energies 662.5, 1173.24, and 1332.51 keV. Based on the measured values of (μ) and sample density, the other effective shielding parameters were calculated. the values of μ showed an increase with increasing the dopant ratios from 0.0 up to 20.0 wt%. In addition, the μ values decreased with the photon's energy. The μ values were found 0.0847 up to 0.1175 cm−1, 0.0571 up to 0.0855 cm−1, and 0.0543 up to 0.075 cm−1 at 662.5, 1173.24, and 1332.51 keV. for B0 up to B20, respectively. The ATR spectroscopy was done on the prepared samples, and a good evidence of adding the filler to the pure polyethylene (HDPE) was obtained. Besides, an enhancement in dielectric constant by insertion of basalt NPs also recorded and can be attributed to the large dielectric constant of basalt compared to pure HDPE.

Green approach for conversion of hazardous red mud into an efficient transparent neutron and gamma-ray shield

Research into the eco-friendly utilization of red mud or bauxite residue (BR) is expanding globally.This study successfully incorporated BR into a family of glasses through the melt quenching technique. The family have a composition of xBR. (50-x) B2O3.25CaO.25BaO, where x = 0, 5, 10, and 15 wt%. X-ray diffraction (XRD) analysis confirmed the non-crystalline nature of the glasses. Physical properties were studied by measuring density, and microhardness was estimated using Vickers hardness (HV) tests. Differential scanning calorimetry (DSC) was used to evaluate the thermal behavior. Changes in various properties resulting from the presence of BR confirmed modifications in the glass network. The radiation shielding properties were measured for gamma and slow neutrons and calculated for fast neutrons. The results indicated that incorporating BR significantly enhanced the γ-ray shielding capacity, reduced the effectiveness of slow neutron shielding, and had minimal impact on shielding against fast neutrons. Additionally, the glasses were compared to standard radiation concrete mixes, demonstrating their superiority and high potential for use in shielding against gamma/X-ray.

Effect of ion implantation on physical, optical properties and gamma-ray shielding capacity of boro-zinc bismuthate glasses

Effect of ion implantation on physical, optical properties and gamma-ray shielding capacity of boro-zinc bismuthate glasses

Radiation shielding properties for 90(Se)- (10-x) (Te)-x(Ag) chalcogenide glasses

Radiation is important for daily life and it is required to shielding. Thus in this study, the radiation shielding properties of 90(Se)- (10-x) (Te)-x(Ag) where x = 0, 1, 2, 3, 4 mol% glass system have been calculated. For this purposes the Linear absorption coefficient (LAC), half-value length (HVL), tenth-value layer (TVL), mean free path (mfp) have been computed using by the Phy-X/PSD program. In these results the effect of Ag rate is also obtained on the gamma ray shielding properties.

Value-added recycling of cathode ray tube funnel glass into high-performance radiation shielding concrete

This study proposed a novel method for recycling cathode ray tube (CRT) glass as heavy aggregates to prepare radiation shielding concrete (RSC). Microstructure, physical properties, radiation shielding characteristics, as well as economic and environmental benefits of CRT glass-based RSC were evaluated. Compared to conventional RSC, the CRT glass-based RSC showed a 13.8 % higher gamma ray shielding capacity. Although the mechanical properties of CRT glass-based RSC slightly decreased by 25.7 % due to the weak interfacial transition zone, the 28-day compressive strength of CRT glass-based RSC still fulfilled the requirement of criteria (> 30 MPa). Based on the cost-benefit assessment, there was 166.7 $/m3 profit in CRT glass-based RSC. Furthermore, CRT glass-based RSC demonstrated 47.7 % and 37.0 % reduction in fossil fuel depletion and carbon emissions compared with barite-based RSC.

Estimation of gamma shielding parameters for heat resistant super alloys using inhouse IGShield code

The prediction capability of the Interactive Gamma-ray Shielding (IGShield) code is evaluated for the gamma shielding characteristics of various Co-Ni based heat resistant alloys. Important gamma shielding parameters such as the linear attenuation coefficient, mass attenuation coefficient, tenth value layer, half value layer, and mean free path are calculated for the gamma energy range of 0.03 MeV to 20 MeV. These results are compared with those obtained from the Monte Carlo (MC) code reported in the literature. Additionally, the results of XCOM analysis conducted as part of the present study are presented for further comparison. The study demonstrates the suitability of IGShield for such analysis by showing good agreement with renowned MC simulations and XCOM values. Furthermore, to evaluate the shielding performance of the heat resistant alloys, the gamma shielding parameters of the alloys of interest are compared with the values of standard shielding materials. The comparison indicates that the shielding efficacy of the super alloys is lower than that of lead but higher than that of all other standard shielding materials. The study clearly highlights the strong dependence of the gamma shielding parameters of interest on photon energy, chemical composition and density of the shielding materials, and it brings out their respective trends.