scholarly journals Impact of Ag2O on the mechanical and shielding features of ZnO- Er2O3-TeO2 glasses

2022 ◽  
Author(s):  
Jamila S. Alzahrani ◽  
NAZIRUL NAZRIN SHAHROL NIDZAM ◽  
M. K. Halimah ◽  
K. Mahmoud ◽  
M. I. Sayyed ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Attenuation Coefficient ◽  
Tellurite Glass ◽  
Transmission Rate ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Maximum Value ◽  
Removal Cross Section ◽  
Substitution Ratio ◽  
Comprehensive Study

Abstract The investigation involves a comprehensive study on the mechanical and shielding features of the zinc erbium tellurite glasses as a function of doped Ag2O content. The mechanical features are estimated for the examined glasses by utilizing the Makishima-Makinzie model. The results showed the mechanical moduli of Young (E), bulk (B), Shear (K), and longitudinal (L) increased with the increment of the Ag2O substitution ratio. Besides, the radiation shielding properties were also studied and discussed. Among the shielding parameters, the linear attenuation coefficient (LAC), half-value layer (HVL), the lead equivalent and transmission rate (TR) were estimated. The linear attenuation coefficient results illustrated that the TZEAg glasses are better compared to the commercial marketing glasses, especially TZEAg5 glasses. Doping of Ag2O content in zinc erbium tellurite glass improves its ability to attenuate the gamma photons. Also, this study revealed the effectiveness of the examined glasses on the fast neutron, where the fast neutron mass removal cross-section ∑R (cm2/g) computed theoretically. The results offered the maximum value of ∑R = 0.019 cm2/g attained for TZEAg1 while the minimum value ∑R = 0.01884 cm2/g for TZEAg5 glass.

scholarly journals Enhancement of the Shielding Capability of Soda–Lime Glasses with Sb2O3 Dopant: A Potential Material for Radiation Safety in Nuclear Installations

2020 ◽  
Vol 11 (1) ◽  
pp. 326
Author(s):  
M.I. Sayyed ◽  
K.A. Mahmoud ◽  
O.L. Tashlykov ◽  
Mayeen Uddin Khandaker ◽  
M.R.I. Faruque
Keyword(s):  
Attenuation Coefficient ◽  
Elastic Moduli ◽  
Gamma Ray ◽  
Radiation Safety ◽  
Soda Lime ◽  
Mass Attenuation Coefficient ◽  
Transmission Factor ◽  
Linear Attenuation Coefficient ◽  
Neutron Shielding ◽  
Removal Cross Section

Elastic moduli were theoretically computed using the Makishima–Mackenzie model for SiO2–Na2O–CaO glasses doped with Sb2O3 contents. The calculated elastic moduli (Young’s, bulk, shear, and longitudinal modulus) were observed to increase with an increase in the Sb2O3 contents. The microhardness showed an increase, while Poisson’s ratio decreased with the rise of the Sb2O3 contents. In addition, gamma-ray and neutron shielding parameters were evaluated for the investigated glasses. The linear attenuation coefficient (LAC) was simulated using the Monte Carlo N-particle transport code (MCNP-5). Other parameters, such as the mass attenuation coefficient (MAC), transmission factor (TF), and half-value layer, were calculated based on the simulated LAC. The addition of Sb2O3 content was observed to enhance the investigated glasses’ shielding parameters, where the highest LAC was achieved for the SCNSb10 glass with 10 mol% Sb2O3 and decreased from 0.441 to 0.154 cm−1 at gamma energies between 0.248 and 1.406 MeV. Furthermore, the fast neutron effective removal cross-section (∑R) was computed theoretically. The calculated results showed that the highest ∑R was equal to 0.0341 cm2g−1 and was obtained for the SCNSb0 glass, which had no Sb2O3 content, while the lowest ∑R was equal to 0.0286 cm2 g−1 for the SCNSb10 glass sample. The present work was carried out to examine the advantages of the soda–lime glasses with different Sb2O3 contents in several photon shielding applications, especially for radiation safety in nuclear installations.

scholarly journals Investigation of Er3+ Ions Reinforced Zinc-Phosphate Glasses for Ionizing Radiation Shielding Applications

Materials ◽  
2021 ◽  
Vol 14 (22) ◽  
pp. 6769
Author(s):  
Hesham M. H. Zakaly ◽  
Antoaneta Ene ◽  
Oyeleke I. Olarinoye ◽  
Samir Y. Marzouk ◽  
Shams H. Abdel-Hafez ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Glass Sample ◽  
Photoelectric Effect ◽  
Absorption Efficiency ◽  
Radiation Shielding ◽  
Phosphate Glasses ◽  
Photon Absorption ◽  
Buildup Factor ◽  
Slowing Down ◽  
Removal Cross Section

Melt quenching technique is used for preparing glasses with chemical formula (70P2O5)−(16−x)CdO−(14ZnO)−(xEr2O3), (x = 1–6 mol%) . These glasses were named Er1, Er2, Er3, Er4, Er5, and Er6, respectively. Photon buildup factors, fast neutron absorption, and electron stopping of the prepared glasses were examined. Glasses’ density was varied from 3.390 ± 0.003 for the Er1 glass sample to 3.412 ± 0.003 for the Er6 glass sample. The Buildup factor (BUF) spectra have relatively higher values in the Compton Scattering (CS) dominated areas compared to both Photoelectric effect (PE), and Pair Production (PP) dominated energy regions. The highest BUF appeared at the Er atom K-absorption edge, whose intensity increases as the molar concentration of Er2O3 in the glasses increases. The photon absorption efficiency (PAE) of the glasses increases according to the trend (PAE)Er1 < (PAE)Er2 < (PAE)Er3 < (PAE)Er4 < (PAE)Er5 < (PAE)Er6. Fast neutron removal cross-section, FNRC values of the glasses obtained via calculation varied from 0.1045–0.1039 cm−1 for Er1–Er6. Furthermore, the continuous slowing down approximation mode (CSDA) range enhances the kinetic energy of electrons for all glasses. Generally, results revealed that the investigated glasses could be applied for radiation shielding and dosimetric media.

Investigation and Characterization of Gamma Radiation Shielding Capacity of Heavy Minerals-Based Composite Materials

2020 ◽  
Vol 6 (4) ◽  
Author(s):  
Mohammad Asaduzzaman Chowdhury ◽  
Md. Bengir Ahmed Shuvho ◽  
Md Azizul Islam ◽  
Muhammad Borhan Uddin ◽  
Ruhul Amin Khan
Keyword(s):  
Composite Materials ◽  
Gamma Radiation ◽  
Attenuation Coefficient ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Integrated System ◽  
Heavy Minerals ◽  
Linear Attenuation Coefficient ◽  
Density Surface ◽  
Effects Of Radiation

Abstract Radiation shielding is an indispensable ingredient in the design of an integrated system to attenuate the effects of radiation during various operations such as space, aircraft, and nuclear plant. Discerning and exploiting the properties of composite materials compatible for radiation shielding in those applications are therefore primary obligation. In this study, we present here the results of control, ilmenite-, and garnet-based composites radiation shielding capabilities. The gamma radiation shielding competency of control, ilmenite-, and garnet-based composite materials has been examined by using linear attenuation coefficient, mass attenuation coefficient (MAC), tenth value layer (TVL), and half value layer (HVL). A comparison among those composite materials has been studied to find out the best one for radiation shielding material. Factors influencing the radiation shielding capabilities such as mechanical properties, thermal properties, density, surface morphology, and Fourier-transform infrared spectroscopy (FTIR) analysis have been studied in comparative investigations. In this work, we show that garnet-based composite material has viable radiation shielding performances as compared to the control and ilmenite-based composites. Garnet-based composite exhibits lower impact energy to withstand against gamma radiation as compared to the other tested shielding materials.

Replacement of Lead by Green Tungsten-Brass Composites as a Radiation Shielding Material

2014 ◽  
Vol 679 ◽  
pp. 39-44 ◽  
Author(s):  
Ali Basheer Azeez ◽  
Kahtan S. Mohammed ◽  
Mohd Mustafa Al Bakri Abdullah ◽  
Andrei Victor Sandhu ◽  
Azmi Rahmat ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Energy Levels ◽  
Developed Countries ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Attenuation Coefficients ◽  
Structural Characterisation ◽  
Weight Percentage ◽  
Suitable Material

Lead metal proved to be toxic. Its lethal effect became eminent. Many developed countries have banned lead usage in various applications. Seeking alternative material to replace lead is a crucial goal. As density concerns, tungsten-brass composite is a good candidate for lead replacement. In this study the radiation shielding effects of tungsten-brass composites were evaluated. To attain this goal, four tungsten-brass sets were prepared. The tungsten (W) wt. % in these specimens was ranged from 50 to 80, the balance is brass. The specimens were sintered at 10500C in alumina tube furnace under protective environment. To evaluate the radiation shielding performance of these specimens, two gamma ray sources, 137Cs and 60Co were utilized. The photon energy levels for these sources were of o.662MeV and 1.25MeV respectively. The measurements were performed using gamma spectrometer contains NaI (Tl) detector. The anti-radiation performance of the tungsten-brass was correlated to that of lead under similar conditions. Vickers micro hardness, relative sintered density, micro structural characterisation and linear attenuation coefficient (μ) were carried out. Samples with the highest Weight percentage of W has the highest hardness value while the one with the lowest Weight percentage of W. The linear attenuation coefficients of the specimens were significantly improved by increasing the W wt. % of the specimen. The linear attenuation coefficients of the tested specimens ranged from 0.85±0.010cm-1 to 1.12±0.049cm-1for 60Co and0.73±0.012 cm-1 to 0.97±0.027 cm-1 for 137Cs. This result indicates that W-brass composites are suitable material for lead replacement as a shielding barrier.Keywords: Attenuation coefficient, radiation shielding, lead, tungsten-brass composites, NaI (Tl).

Radiation Shielding Characteristics of Concretes Incorporates Different Waste Materials

2013 ◽  
Vol 594-595 ◽  
pp. 1015-1019
Author(s):  
Ali Basheer Azeez ◽  
Kahtan S. Mohammed ◽  
Abdullah Mohd Mustafa Al Bakri ◽  
Hana Ihsan Hasan
Keyword(s):  
Attenuation Coefficient ◽  
Energy Levels ◽  
Radiation Shielding ◽  
Shielding Effect ◽  
Waste Materials ◽  
Linear Attenuation Coefficient ◽  
Radioactive Elements ◽  
Radiation Sources ◽  
The Mean ◽  
Particulate Distribution

Samples of concrete incorporate different waste materials such as iron filings, iron balls of used ball bearings and slags from steel industry were assessed for their anti-radiation attenuation coefficient properties. The attenuation measurements were performed using gamma spectrometer of NaI (Tl) detector. The utilized radiation sources comprised Cs137and Co60radioactive elements with photon energies of o.662 MeV for Cs137and two1.17 and 1.33 MeV energy levels for the Co60. Likewise the mean free paths for the tested samples were obtained. The maximum linear attenuation coefficient values of 0.92±1.12×10-3for CS137and 1.12±1.57×10-3for CO60attained, in this study were for concrete incorporate iron filling wastes of 30 wt. %. The iron balls and the steel slags gave much inferior values. The concrete incorporates iron filings provided the best shielding effect. The microstructure, concretefillings composite density, the homogeneity and particulate distribution were examined and evaluated using different metallographic, microscopic and measurement facilities.

scholarly journals Experimental Investigation of Radiation Shielding Competence of Bi2O3-CaO-K2O-Na2O-P2O5 Glass Systems

Materials ◽  
2021 ◽  
Vol 14 (17) ◽  
pp. 5061
Author(s):  
Dalal Abdullah Aloraini ◽  
Aljawhara H. Almuqrin ◽  
M. I. Sayyed ◽  
Hanan Al-Ghamdi ◽  
Ashok Kumar ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Effective Atomic Number ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
The Other ◽  
Linear Attenuation Coefficient ◽  
Attenuation Coefficients ◽  
Positive Effect ◽  
Theoretical Results

The gamma-ray shielding features of Bi2O3-CaO-K2O-Na2O-P2O5 glass systems were experimentally reported. The mass attenuation coefficient (MAC) for the fabricated glasses was experimentally measured at seven energy values (between 0.0595 and 1.33 MeV). The compatibility between the practical and theoretical results shows the accuracy of the results obtained in the laboratory for determining the MAC of the prepared samples. The mass and linear attenuation coefficients (MACs) increase with the addition of Bi2O3 and A4 glass possesses the highest MAC and LAC. A downward trend in the linear attenuation coefficient (LAC) with increasing the energy from 0.0595 to 1.33 MeV is found. The highest LAC is found at 1.33 MeV (in the range of 0.092–0.143 cm−1). The effective atomic number (Zeff) follows the order B1 > A1 > A2 > A3 > A4. This order emphasizes that increasing the content of Bi2O3 has a positive effect on the photon shielding proficiencies owing to the higher density of Bi2O3 compared with Na2O. The half value layer (HVL) is also determined and the HVL for the tested glasses is computed between 0.106 and 0.958 cm at 0.0595 MeV. The glass with 10 mol% of Bi2O3 has lower HVL than the glasses with 0, 2.5, 5, and 7.5 mol% of Bi2O3. So, the A4 glass needs a smaller thickness than the other glasses to shield the same radiation. As a result of the reported shielding parameters, inserting B2O3 provides lower values of these three parameters, which in turn leads to the development of superior photons shields.

Investigation of Gamma Radiation Shielding of Concrete Containing Blast Furnace Slag Waste via Experimental and Calculation Methods

2018 ◽  
Vol 765 ◽  
pp. 329-334 ◽  
Author(s):  
Pranpriya Phutthanet ◽  
Pithiwat Tiantong ◽  
Phongthorn Julphunthong ◽  
Panuwat Joyklad ◽  
Li Jie Wang ◽  
...  
Keyword(s):  
Blast Furnace ◽  
Chemical Composition ◽  
Attenuation Coefficient ◽  
Blast Furnace Slag ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Fine Aggregate ◽  
Study Results ◽  
Shielding Properties ◽  
Furnace Slag

This study aims to evaluate gamma-ray shielding characteristics of concrete produced from blast furnace slag. The chemical and physical properties of the aggregates including the chemical composition and specific gravity were investigated to evaluate their radiation shielding properties. The samples were prepared with a cement content of 400 kg/m3, a water to cement ratio of 0.4, and fine aggregate of 43% and coarse aggregate ratio of 57%. Blast furnace slag was replaced with sand at 25%, 50%, 75% and 100% by volume to improve the shielding properties. The compressive strengths at 3, 7 and 28 days and the unit weight of the prepared samples were determined. The linear attenuation coefficient was measured and calculated at photon energies of 0.662 MeV, 1.17 MeV and 1.33 MeV. The WinXCom program was employed to calculate the attenuation coefficient from the chemical composition of samples and the results were compared to the measured results. The study results suggest that the use of blast furnace slag is effectively in improving the compressive strength and shielding properties of concrete. The increase of blast furnace slag caused an increase in the linear attenuation from 0.190 cm-1 to 0.210 cm-1 at 0.662 MeV.

scholarly journals The Vital Role of La2O3 on the La2O3-CaO-B2O3-SiO2 Glass System for Shielding Some Common Gamma Ray Radioactive Sources

Materials ◽  
2021 ◽  
Vol 14 (17) ◽  
pp. 4776 ◽  
Author(s):  
Hanan Al-Ghamdi ◽  
Mengge Dong ◽  
M. I. Sayyed ◽  
Chao Wang ◽  
Aljawhara H. Almuqrin ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Vital Role ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Sio2 Glass

The role La2O3 on the radiation shielding properties of La2O3-CaO-B2O3-SiO2 glass systems was investigated. The energies were selected between 0.284 and 1.275 MeV and Phy-X software was used for the calculations. BLa10 glass had the least linear attenuation coefficient (LAC) at all the tested energies, while BLa30 had the greatest, which indicated that increasing the content of La2O3 in the BLa-X glasses enhances the shielding performance of these glasses. The mass attenuation coefficient (MAC) of BLa15 decreases from 0.150 cm2/g to 0.054 cm2/g at energies of 0.284 MeV and 1.275 MeV, respectively, while the MAC of BLa25 decreases from 0.164 cm2/g to 0.053 cm2/g for the same energies, respectively. At all energies, the effective atomic number (Zeff) values follow the trend BLa10 < BLa15 < BLa20 < BLa25 < BLa30. The half value thickness (HVL) of the BLa-X glass shields were also investigated. The minimum HVL values are found at 0.284 MeV. The HVL results demonstrated that BLa30 is the most space-efficient shield. The tenth value layer (TVL) results demonstrated that the glasses are more effective attenuators at lower energies, while decreasing in ability at greater energies. These mean free path results proved that increasing the density of the glasses, by increasing the amount of La2O3 content, lowers MFP, and increases attenuation, which means that BLa30, the glass with the greatest density, absorbs the most amount of radiation.

Thermal stability, mechanical properties, and gamma radiation shielding performance of polyvinyl chloride/Pb(NO3)2 composites

2021 ◽  
Vol 0 (0) ◽  
Author(s):  
Sayed A. Waly ◽  
Ahmed M. Abdelreheem ◽  
Mohamed M. Shehata ◽  
Omayma A. Ghazy ◽  
Zakaria I. Ali
Keyword(s):  
Thermal Stability ◽  
Attenuation Coefficient ◽  
Polyvinyl Chloride ◽  
Polymer Matrix ◽  
Composite Films ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Point Sources ◽  
Linear Attenuation Coefficient ◽  
Mass Attenuation

Abstract Radiation shielding composites based on polyvinyl chloride (PVC) reinforced with different weight ratios of Pb(NO3)2 (5, 10, and 20 wt%) were prepared using the solution-casting technique. Fourier-transform infrared spectroscopy (FTIR), X-ray diffraction (XRD), thermogravimetric analysis (TGA), scanning electron microscopy, and tensile testing method were used to characterize the PVC composite films. FTIR and XRD investigations illustrate the structural change and modification of the as-prepared PVC composites. The morphological analysis of the composite revealed that Pb(NO3)2 was dispersed uniformly within PVC polymer matrix. TGA revealed that the incorporation of Pb(NO3)2 improved the thermal stability of the investigated composites, whereas adding Pb(NO3)2 to the polymer matrix worsened its tensile properties. The as-prepared composite films were investigated for radiation-shielding of gamma-rays radioactive point sources (241Am, 133Ba, 137Cs, and 60Co). Linear attenuation coefficient (μ, cm−1), mass attenuation coefficient (μ/ρ, cm2/g), and half-value layer (HVL, cm) have been estimated from the obtained data using the MicroShield program. Reasonable agreement was attended between theoretical and experimental results. The deviation between the experiment and theoretical values of mass attenuation coefficient is being to be lower than 9%, and this can be correlated to the good distribution of Pb(NO3)2. The results revealed that adding Pb(NO3)2 to PVC polymer composites improved their mass attenuation coefficient.

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