Ray Attenuation Research Articles

Three-phase flow measurement by dual-energy gamma ray technique and static-equivalent multi-phase flow simulator

There is a strong desire to use three-phase flowmeters in upstream operations because of their small size, portability, and cost-effectiveness. Traditional three-phase flowmeterstypically employ two main strategies: fully separating the flow into liquid and gas streams and measuring them using common two- and single-phase meters, or simplifying the direct measurement requirements by homogenization.In order to achieve accurate measurements with these meters, it is necessary to first create a suitable simulator for generating various multiphase flow regimes with minimal systematic error. Developing such a simulator on a laboratory scale, rather than using expensive test loops is a crucial and practical option.In this research, SEMPF as a Static-Equivalent Multi-Phase Flow with flexibility in creating different multi-phase flow regimes is introduced. In the following, the mechanism of action is validated for both homogenous two- and three-phase mixtures by using dual-energy gamma ray attenuation technique in the Monte Carlo simulator environment. Finally, the three-phase component fraction measurement accuracy by dual-energy gamma meter in three different modes of gasoil-, water-, and air-continuous mixtures were investigated. The experimental results show the maximum accuracy of 2.03 %, 7.23 %, and 5.09 % for gasoil phase measurement in three different conditions that the carrier phase is air, gasoil and water respectively.

Zinc boro-aluminosilicate glass for infrared and gamma sensing applications: Physical properties and gamma ray attenuation aspects

The demand for more materials for efficient shielding of radiation has been on the rise day by day due to some witnessed progress in applications of radiations in science and technology. In this research, we investigated the gamma ray shielding capacity of zinc boro-aluminosilicate (ZBASi) glass by varying concentrations of B2O3. Fundamentally, experimental and theoretical means were both adopted to evaluate photon shielding characteristics of the studied glasses. Additionally, amorphous nature and crystalline sizes of the glass sample were determined using XRD technique and Debye Scherrer equation respectively. The results show that as the B2O3 content increased from 55 to 70 wt %, the optical bandgap, and packing density decreased. However, the density, and molar volume were found to increase accordingly. Using Phy-x/PSD and genat4, the maximum values of mass attenuation coefficient (MAC) for ZBASi-4, ZBASi-3, ZBASi-2, and ZBASi-1 were found to be 20.2, 17.5, 16.3, and 9.6 cm2/g at 20 KeV, respectively. With respect to exposure rate, the exposure buildup factor (EBF) is low in the region where density is high, meaning that photon attenuation power is high in the region of low EFB (high density). The production of aluminosilicate glass poses fewer environmental risks than that of traditional lead-based shielding materials. It is therefore a more environmentally friendly option since harmful heavy metals are not involved.

Experimental and theoretical results of gamma shielding features for copper based shape memory alloys

In this study, the gamma ray attenuation characteristics for CuAlNi shape memory alloys with different proportions of Sn doping was investigated. We determined the mass attenuation coefficient (μ/ρ) of CuAlNiSn alloys both experimentally and theoretically within an energy range of 59.5–1332.5 keV. The experimental measurements were made using a high purity Germanium detector (HPGe) and theoretical calculations were made using WinXCOM program. To evaluate the gamma radiation shielding abilities of the alloy samples, the obtained (μ/ρ) values were used to determine the gamma protection parameters μ, HVL, TVL, MFP, and Zeff. In addition, the radiation protection efficiency (RPE) parameter was determined using gamma ray intensities in the absence and presence of the attenuator. Further analysis of the samples was conducted using a Rigaku Miniflex 600 model computer-controlled X-ray diffractometer (CuKα & λ = 1.5405 A0). The crystallographic structure of the alloys before and after irradiation was investigated. Other analysis which include EDX analysis (to investigate the chemical content) and SEM analysis (to investigate the microstructure) were conducted. According to result outcomes, gamma ray radiation did not affect the shape memory properties of structure. Another interesting observation is that, the radiation attenuation properties increase with increasing Sn concentration. Finally, we discovered that the CuAlNiSn4 alloy (which has the highest doping rate) provides good protection especially at low energy levels.

Optimization of structure, optical, magnetic, and radiation shielding properties of ZnO@xSrFe12O19 nanocomposites

In this work, the pristine ZnO, SrFe12O19 (SFO), and their nanocomposites (ZnO/x SFO: x = 1, 3 and 5%) were synthesized by co-precipitation and sonomechanical method. The x-ray diffraction data validate the preparation of ZnO, SFO, and nanocomposite samples with high phase purity. The optical band gap was calculated from UV–vis-NIR diffuse reflectance measurements, and it was modified by increasing SFO content. Adding 1, 3, and 5 wt% of SFO to the ZnO matrix showed ferromagnetic characteristics for the nanocomposites with a squareness ratio of around 0.49, which considered these nanocomposites as a magnetic semiconductor suitable for digital memory and spintronic applications. Additionally, the radiation shielding features of the prepared samples were evaluated. The shielding parameters for the studied samples were obtained using the Phy-X/PSD program. The fast neutron removal cross-section of SFO was 0.094 cm−1, the highest among the investigated samples, while the composites had similar values, about 0.083 cm−1. The results indicated that the γ--ray attenuation ability and the values of exposure buildup factor for the prepared samples were close. Therefore, ZnO, SFO, and their nanocomposites compared to stationary shielding materials (SMs), can be candidates for applications where radiation protection is needed.

Investigation on radiation shielding potentials of barium calcium aluminosilicate glass material using silicon carbide nanotubes reinforcement

This work investigated the gamma ray attenuation power of barium calcium aluminosilicate glass by using silicon carbide nanotube modifiers. Shielding efficiency of BaO–15CaO–5Al2O3–10B2O3–35SiO2 was investigated by adding different concentrations of silicon carbide nanotubes (10, 15, 20, 25 mol %). Amorphous and fine characteristics of the prepared glass materials were analyzed using XRD and FTIR techniques. In the results obtained, absence of sharp peaks in the XRD pattern revealed that the prepared glass was amorphous. Analysis of the radiation shielding properties was tested against gamma radiation by using PHY-X/PSD software. Various shielding parameters such as linear attenuation coefficient, mass attenuation coefficient, half value layer, tenth value layer, mean free path, and effective atomic number were determined to access the radiation shielding strength of the prepared samples. From the obtained results, composites of barium calcium aluminosilicate and silicon carbide nanotubes (sample 1) with higher values of mass attenuation coefficient (32.92 cm2/g) and effective atomic number (52.02) provided superior gamma ray attenuation. Results also revealed that the density and chemical composition of the prepared glass samples strongly influence photon interactions and weakly influence electronic interactions during the photon attenuation process. The results demonstrated that increasing the weight fractions of silicon carbide nanotubes in the glass samples increases the shielding properties.

Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement

Due to the high demand for protective materials against ionizing radiations such as gamma rays, X-rays and charged particles, it is necessary to focus more attention on several ways to improve the efficiency of the already existing radiation shielding materials. In the present study, experimental and theoretical approaches were followed to investigate the gamma ray attenuation performance of the bismuth tellurite glass composed of molybdenum oxide. 20MoO3-xBi2O3-(80-x)TeO2 was prepared by melt-quenching process with various compositions of Bi2O3. Absence of sharp peak in the XRD spectra revealed the amorphous nature of the 20MoO3-xBi2O3-(80-x)TeO2. Densities of the prepared 20MoO3-xBi2O3-(80-x)TeO2 was found to vary directly with Bi2O3 content. Additionally, Zeff significantly improved as a result of increase in mol% of Bi2O3 from 10 mol% to 25 mol%. Lowest values of MFP was obtained with MoBiTe4 which has the highest density of 4.819 g/cm3, hence demonstrated better gamma ray attenuation than other three samples. The current study found Bi2O3 in the 20MoO3-xBi2O3-(80-x)TeO2 good for gamma ray attenuation in the lower energy range.

Impact of bismuth oxide on structural, optical and gamma-ray shielding properties of calcium-sodium-borate glasses.

In the present study, we have prepared six glass samples of bismuth borate using the melt-quenching method with the composition (70-x)B2O3-10CaO-20Na2O-xBi2O3; x=0, 3, 6, 9, 12 and 15mol%. The density of the prepared glasses was determined using Archimedes principle. The X-ray diffraction patterns provide confirmation of the amorphous nature of the prepared samples, whereas the Fourier transform infrared measurements pointed to the existence of structural units like BO3, BO4, BiO3 and BiO6 within the glass network. An assessment of the optical absorption spectra unveiled that with the increase in the bismuth oxide content, there was a decrease observed in both the direct and indirect band gap energies. Specifically, they decreased from 3.40 to 2.79eV and from 3.10 to 2.46eV, respectively. The properties related to gamma ray attenuation, including the mass attenuation coefficient (μm), effective atomic number (Zeff), half-value layer (HVL) and mean free path (MFP), were examined for all the glass samples. This investigation was carried out using the Phy-X/PSD software, covering the energy range from 0.511 to 1.332MeV. Out of all the samples, Bi-15, featuring the highest Bi2O3 content, demonstrated the highest μm, Zeff, the smallest HVL and MFP. These results suggest that the glass with 15mol% of Bi2O3 offers the most effective gamma radiation shielding performance. Moreover, the glasses examined in this study exhibit superior radiation shielding characteristics compared with specific concrete types, namely, ordinary concrete, Hematite serpentine concrete and barite concrete, as well as commercial glasses such as RS-360 and RS-253.

Zirconium tungstate (Zr4W8O32)-doped zirconium dioxide (ZrO2) for gamma ray shielding: an in-depth examination of fabrication, characterizations, and gamma ray attenuation properties

Zirconium tungstate (Zr4W8O32)-doped zirconium dioxide (ZrO2) for gamma ray shielding: an in-depth examination of fabrication, characterizations, and gamma ray attenuation properties

Evaluation of technical and gamma radiation shielding properties of sustainable ultra-high performance geopolymer concrete

This study proposed to use barite-enhanced ultra-high performance geopolymer concrete (UHPGC) as the composite matrix to develop high-strength, cement-free, and sustainable radiation shielding materials. The physical properties, γ ray attenuation capacity, microstructure, and environmental and economic impacts of prepared barite-enhanced radiation shielding UHPGC were determined and compared with normal concrete and ultra-high performance concrete (UHPC). The combination of steel fibers and barite aggregate increased the density of UHPGC, thereby enhancing its γ ray attenuation capacity. Multi-scale γ ray shielding simulation results demonstrated that although thickness was the more decisive factor of γ ray attenuation capacity of composites, the enhancement of the shielding capacity of the material helps reduce the floor area and the cost of radiation shielding structure. The micro-analysis results revealed that barite-enhanced UHPGC exhibited compact microstructure and excellent interfacial performance. Furthermore, life cycle assessment results demonstrated that UHPGC was more suitable as a composite matrix than UHPC to develop sustainable and low-cost radiation shielding materials.

Valorization of steel slag into sustainable high-performance radiation shielding concrete

The disposal of steel slag (SS) has become a serious ecological problem due to the waste of massive land resources. This study reveals the huge potential of recycling SS as heavy aggregates to develop radiation shielding concrete (RSC). The physical characteristics, radiation attenuation capabilities, microstructure, and environmental and ecological impacts of SS-based RSC are comprehensively evaluated and compared with those of normal concrete and the commonly used heavy concrete. The test results indicate that SS-based RSC is prospective to substitute the commonly used heavy concrete, emerging as a sustainable and efficient material for radiation shielding in nuclear energy engineering. Specifically, due to the reaction of cementitious active substances in the surface of SS, the developed SS-based RSC exhibits a fantastic interfacial transition zone (ITZ), and a compact pore structure, thereby showing excellent mechanical properties. The maximum compressive strength of developed SS-based RSC reaches 47.4 MPa. In terms of gamma ray attenuation property, due to the introduction of heavy nuclei and the increase in density, the gamma ray attenuation capacity of developed SS-based RSC is 17.2 % higher than that of normal concrete. The neutron attenuation property is also slightly enhanced due to the refinement effect of SS on pore structure of RSC. Life cycle assessment and unit cost evaluation results demonstrate that compared with barite based-RSC, SS-based RSC can save 97.6 % in cost, 52.0 % in energy consumption, and 70.4 % in carbon emission. The developed SS-based RSC exhibits excellent mechanical properties and radiation attenuation capacities, contributing to the further application of radiation shielding materials. Besides, this approach achieves the high-value recycling of SS, providing new insights for the utilization of high-density solid wastes.

Optoelectronic and gamma ray attenuation properties of ore-based Bi and Sn-doped borosilicate glasses

Progress in glass science has given rise to innovative functional glasses, unlocking significant applications for creating cutting-edge materials such as solid-state batteries, solar cells, optical reinforcement, and medical technologies. In this study, rice husk silica, Bismuth (Bi) and Tin (Sn) oxide ores were used to fabricate a novel glass series. The electrical conductivity (i.e., dielectric constant) of the glasses increased with the dopant's gravimetric levels. The novel glass series also possesses good optical non-linearity with metallisation criteria ranging from 0.35 to 0.40, which points to a novel non-linear optical material. The non-bridging oxygen content in the new glasses exceeds the bridging oxygen, indicating high polarisation. The transmission coefficient decreased with increasing dopant concentration from 0.76 to 0.75, while the reflection loss decreased from 0.37 to 0.38. For the Caesium-137 energy, GS6 has a minimum HVL of ∼5.02 cm, which is ∼20 % lower than that of commercial Pb/Ba glass. For the two energies, GS6 has the least MFP, suggesting that the addition of dopants improved the efficiency of the glass attenuation. Process capability analysis based on Caesium-137 (661.7 keV) and overall performance analysis of the fabricated glass series revealed that GS3 glass (15 wt% dopant) is the optimal material, even outperforming the commercial Pb/Ba glass. Although Cobalt-60 (1253 keV) yielded comparable outcomes, concentrations beyond 15 wt% in GS3 showed marginal enhancements in the photon attenuation parameters of the glasses. Hence, the fabricated GS3 and the circular synthesis method of the glasses are cost-effective for low-energy gamma/X-ray shielding. The percentage deviation between the experimental data for MAC and that of Monte Carlo simulations for Cs-137 and Co-60 energies are both within 10 %, which validates the methods of this paper.

Optimization of the gamma reaction history diagnostic for double-shell pusher areal density and reaction history measurements on the National Ignition Facility.

The double-shell inertial confinement fusion campaign, which consists of an aluminum ablator, a foam cushion, a high-Z pusher (tungsten or molybdenum), and liquid deuterium-tritium (DT) fuel, aims for its first DT filled implosions on the National Ignition Facility (NIF) in 2024. The high-Z, high density pusher does not allow x-rays to escape the double-shell capsule. Therefore, nuclear diagnostics such as the Gamma Reaction History (GRH) diagnostic on the NIF are crucial for understanding high-Z implosion performance. To optimize the GRH measurement of fusion reaction history and the pusher's areal density, the MCNP6.3-based forward model of the detector was built. When calculating the neutron-induced inelastic gamma ray production, the interaction of neutrons with the compressed fuel was additionally included. By folding the calculated gamma ray spectrum output and the previously calibrated GRH detector responses, the optimum set of GRH energy thresholds for measuring the pusher areal density is determined to be 2.9 and 6.3MeV for DT double-shell experiments. In addition, the effect of the down-scattering of neutrons on the gamma ray spectrum, the minimum required yield for measurements, and the attenuation of the gamma rays through the pusher are analyzed.

Structural, mechanical, thermal, optical, and gamma rays attenuation properties of a developed sodium aluminum zinc lead borate glass

A host glass matrix of sodium aluminum zinc borate reinforced by 15, 30, and 45 mol% of PbO to serve as a shield against gamma rays. The penetration of PbO within the proposed host glass transforms the BO3 units into BO4 ones and fills the interstitial spaces, which in turn had been reflected on the mechanical, thermal, and optical properties. The harness and elastic moduli of the considered glasses improved with the augmentation of Pb2+ ions. The considered glass possessed high thermal stability and its glass transition temperature increased with the increase of PbO concentrations. Optically, the transparency of the produced glasses exceeds 75% with the inclusion of Pb2+ ions and increasing the Pb2+ ions enhancing its electrical insulating nature. Increasing PbO concentrations enhanced the glasses' ability to attenuate gamma rays of energies 661.64, 1173.23, and 1332.51 keV. A reduction in the required half-value layer by 59.697, 54.867%, and 53.460% at 45 mol% of PbO was observed. Hence, based on the suitable mechanical properties, high thermal stability and transparency, and effective ability to attenuate gamma rays, the glass containing 45 mol% PbO was nominated for use as a protective shield in various nuclear applications.

Non-destructive multi-sensor core logging allows for rapid imaging and estimation of frozen bulk density and volumetric ice content in permafrost cores

Abstract. Permafrost cores provide physical samples that can be used to measure the characteristics of frozen ground. Measurements of core physical properties, however, are typically destructive and time intensive. In this study, multi-sensor core logging (MSCL) is used to provide a rapid (∼2–3 cm core depth per minute), high-resolution, non-destructive method to image and collect the physical properties of permafrost cores, allowing for the visualization of cryostructures and estimation of frozen bulk density, magnetic susceptibility, and volumetric ice content. Six permafrost cores with differing properties were analyzed using MSCL and compared with established destructive analyses to assess the potential of this instrument both in terms of accuracy and relative rate of data acquisition. A calibration procedure is presented for gamma ray attenuation from a 137Cs source that is specific to frozen-core materials. This accurately estimates frozen bulk density over the wide range of material densities found in permafrost. MSCL frozen bulk density data show agreement with destructive analyses based on discrete-sample measurements, with an RMSE of 0.067 g cm−3. Frozen bulk density data from the gamma attenuation, along with soil dry bulk density measurements for different sediment types, are used to estimate volumetric ice content. This approach does require an estimation of the soil dry bulk density and assumption of air content. However, the averaged results for this method show good agreement with an RMSE of 6.7 %, illustrating MSCL can provide non-destructive estimates of volumetric ice contents and a digital archive of permafrost cores for future applications.

Fast neutrons and gamma rays shielding properties for some nylon composite

In this study, The removal parameters of macroscopic fast neutron cross-section, linear gamma ray attenuation, mean free path, and half-value layer (half-value thickness) were calculated for a polymer composite containing nylon 6 as a base material and starch powder, silica oxide, and calcium carbonate as reinforcement materials for different energies (0.05, 0.1, 0.3, 0.6, 0.8, 1, 3, 7, 10, 15) and for various concentrations (5, 10, 15, 20, 25). We used the x-com program to calculate gamma ray attenuation values. The results showed that the macroscopic cross-section of fast neutron attenuation and the linear attenuation coefficient for gamma rays increase with increasing reinforcement materials concentration, while the values of half-value layer decrease with increasing concentrations. When the energy increases, the half-value layer and the mean free path also increase, however, the values of the linear attenuation coefficient decrease.

Optical, thermal and gamma ray attenuation characteristics of tungsten oxide modified: B2O3–SrCO3–TeO2–ZnO glass series

The glass series modified by tungsten oxide was created using the compounds (75-x) B2O3– 10SrCO3– 8TeO2– 7ZnO - xWO3, where x = 0, 1, 5, 10, 22, 27, 34, and 40% mole percentage. A UV–visible spectrophotometer and thermogravimetric-differential thermal analysis (TG-DTA) methods were employed to characterize the specimen's optical and phase transition attributes, respectively. The mass-attenuation coefficient (AC) of all created glasses from BSTZW0 to BSTZ7 was estimated using Geant4 code from 0.05 to 3 MeV and compared to the XCOM software results, with a relative difference of less than 2% between the two results. The increase of WO3 percentage lead to an increase in the Linear-AC at each studied energy, and this is mainly due to the fact that the higher the percentage of WO3 in the glass increases its density which causes an increase in the Linear-AC, so an energy of 0.06 MeV, as an example, the values of the Linear-AC was 4.009, 4.509, 5.442, 6812, 8.564, 9.856, 10.999 and 11.628 cm−1 form BSTZW0 too BSTZW7, respectively. The Half-VL (value layer), Mean-FP (free path), Tenth-VL, and Radiation attenuation performance (RAP) were also calculated for the current BSTZW-glass samples and revealed that BSTZW7 had the best gamma ray attenuation performance at all discussed energies when compared to other studied glass samples.

Influence of Lead Nanoparticles on Structural, Morphological, and Mechanical Characteristics of (SiR-PU/Micro-Pb) Composites and Radiation Shielding Applications

This research includes the manufacture of a polymeric nanocomposite consisting of silicone rubber/polyurethane as a base, with the addition of the first filler of micro-lead with a ratio of 300 pphr and the second filler of nano-lead with different ratios (0, 0.2, 0.4, 0.6, 0.8 pphr). With the addition of hexane (liquid state) to the superposition using the casting technique at room temperature. The structural properties of the surfaces of the samples were measured using Fourier transformation spectroscopy (FT-IR) and the scanning electron microscope (SEM). In addition to studying the mechanical properties represented by each hardness, tensile, elongation, and elastic modulus. (FT-IR) showed the absence of a chemical reaction for all samples. While SEM measurements showed a homogeneous distribution of micro-lead and nano-lead in the presence of hexane equally, and there were no voids in the eyes of the prepared rubber equally. For the mechanical properties, we see that the hardness, tensile strength and modulus of elasticity continue to improve with the increase in the number of lead nanoparticles. And a decrease in elongation as a result of inverse proportion to the modulus of elasticity. From the results obtained, this composite can be used in gamma ray attenuation applications in shielding, especially in medical and industrial fields.

Exploring the mechanical behavior and gamma ray attenuation properties of Bi2O3–BaO–V2O5 glasses

Exploring the mechanical behavior and gamma ray attenuation properties of Bi2O3–BaO–V2O5 glasses

X-ray/gamma radiation attenuation and cytotoxic properties of Gadolinium doped Maghemite nanoparticles

In the present work, Gadolinium doped (1–6 mol%) Maghemite nanoparticles (NPs) were synthesized via solution combustion method using Sapodilla fruit extract as a reducing agent followed by calcination at 500 °C and characterized with different techniques. The Bragg reflections consists of (hkl) planes corresponding to γ-Fe2O3 (Maghemite). Addition to this, few planes corresponding to α-Fe2O3 and Gd2O3 were also observed. The estimated crystallite size and direct energy band gap was found to decrease with increase in Gd3+ concentration. Cytotoxic properties were examined on cervical cancer cell lines HeLa cells as the Gadolinium dopant concentration increases, cell death decreases, eventually toxicity is going to reduced. Because of the non-toxicity, these NPs might be used as a drug carrier and also in the biochemical modification process called PEGylation. Theoretically, X-ray/Gamma ray attenuation parameter such as mass attenuation coefficient is studied in detail which is an essential parameter in radiation dosimetry. Gamma attenuation ion properties are increased by increase in the dopant concentration of Gadolinium. Compared to other concentrations, Gadolinium at 6 mol% shows maximum cytotoxic and mass attenuation coefficient. Thus, the present synthesized material might finds an application in biomedical field as well as in radiation dosimetry.

Synthesis and characterization determination of boric acid for gamma and neutron shielding efficiency of bio-caulk incorporated high-performance concrete (HPC)

Boron is a naturally occurring element having the ability to react with a wide range of various elements to form different compounds. Boric acid (BA) compounds will have significant applications like radiation shielding. When boron compounds are added to concrete it increases the neutron attenuation and acts as a suppressor of secondary-capture gamma rays. The High-Performance Concrete (HPC) – M40 grade has been used in most reactor constructions due to its high attenuation properties. Nano boron produced by 20 h of ball milling was mixed with uniform distribution in the concrete. This pulverized nano boron was sampled every 4 h and characterized by XRD, FTIR and FE-SEM. The setting time was determined after adding 1, 2, 3, 4 & 5% (w/w) of milled and unmilled BA materials into the HPC-M40 concrete as a replacement for cement. A significant radiation attenuation effect was observed in the 5 cm thickness of the concrete which showed up to 80% reduction in gamma rays attenuation compared to the conventional concrete. The bio-caulk, a bacterial concrete, was used as a replacement for water to increase the setting time and strength properties. 10% of Bacillus sphaericus inoculum was used to synthesize bio-Caulk which has self-healing properties at the micro-level cracks. The bio-caulk borated HPC - M40 grade has better shielding properties at 5% of boron as an admixture. The BA composite incorporated bio-caulk concrete showed less setting time, high compressive strength and better radiation shielding properties.