scholarly journals In Silicon Monte Carlo Simulation Trials for Investigation of V2O5 Reinforcement Effect on Ternary Zinc Borate Glasses: Nuclear Radiation Shielding Dynamics

Materials ◽  
2021 ◽  
Vol 14 (5) ◽  
pp. 1158
Author(s):  
Huseyin O. Tekin ◽  
Shams A. M. Issa ◽  
Gokhan Kilic ◽  
Hesham M. H. Zakaly ◽  
Mohamed M. Abuzaid ◽  
...  
Keyword(s):  
Effective Atomic Number ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Zinc Borate ◽  
Linear Attenuation Coefficient ◽  
Buildup Factor ◽  
Glass Composites ◽  
Mcnpx Code ◽  
Negative Effect

In the current study, promising glass composites based on vanadium pentoxide (V2O5)-doped zinc borate (ZnB) were investigated in terms of their nuclear-radiation-shielding dynamics. The mass and linear attenuation coefficient, half-value layer, mean free path, tenth-value layer, effective atomic number, exposure-buildup factor, and energy-absorption-buildup factor were deeply simulated by using MCNPX code, Phy-X PSD code, and WinXcom to study the validation of ZBV1, ZBV2, ZBV3, and ZBV4 based on (100−x)(0.6ZnO-0.4B2O3)(x)(V2O5) (x = 1, 2, 3, 4 mol%) samples against ionizing radiation. The results showed that attenuation competencies of the studied glasses slightly changed while increasing the V2O5 content from 1 mol% to 4 mol%. The domination of ZnO concentration in the composition compared to B2O3 makes ZnO substitution with V2O5 more dominant, leading to a decrease in density. Since density has a significant role in the attenuation of gamma rays, a negative effect was observed. It can be concluded that the aforementioned substitution can negatively affect the shielding competencies of studied glasses.

scholarly journals Newly Developed Vanadium-Based Glasses and Their Potential for Nuclear Radiation Shielding Aims: A Monte Carlo Study on Gamma Ray Attenuation Parameters

Materials ◽  
2021 ◽  
Vol 14 (14) ◽  
pp. 3897
Author(s):  
Huseyin Ozan Tekin ◽  
Ghaida Bilal ◽  
Hesham M. H. Zakaly ◽  
Gokhan Kilic ◽  
Shams A. M. Issa ◽  
...  
Keyword(s):  
Glass Sample ◽  
Gamma Ray ◽  
Effective Conductivity ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Buildup Factor ◽  
Doped Glass

This study aimed to investigate different types of glasses based on the 46V2O5-46P2O5-(8-x) B2O3-xCuO system in terms of their nuclear radiation shielding properties. Accordingly, five different CuO-doped vanadate glasses were investigated extensively to determine the necessary gamma shielding parameters along with effective conductivity at 300,000 and buildup factors. Phy-x PSD software was used for determination of these vital parameters. Furthermore, these parameters, such as half value layer, tenth value layer, and mean free path were investigated in a broad energy range between 0.015 and 15 MeV. The results revealed that the amount of CuO reinforced in each sample plays an essential role in determination of the shielding abilities of the samples. The sample with the highest CuO content had the highest linear attenuation coefficient and mass attenuation coefficient values. Additionally, the lowest mean free path, half value layer, and tenth value layer values were recorded for glass sample VPCu8. There was an inverse relation between the effective conductivity and effective atomic number and photon energy; that is, as energy increases, the effective conductivity and effective atomic number decreased rapidly, especially in the regions of low energy. Glass sample VPCu8 reported the highest values for both parameters. Moreover, glass sample VPCu8 had the lowest exposure buildup factor and energy absorption buildup factor values. Our findings showed that CuO-reinforced vanadate glass composition, namely 46V2O5-46P2O5-8CuO, with a glass density of 2.9235 g/cm3, was reported to have superior gamma ray attenuation properties. These results would be helpful for scientists in determining the most appropriate additive rare earth type, as well as the most appropriate glass composition, to offer shielding characteristics similar to those described above, taking into consideration the criteria for usage and the needs of the community. The results of this research will be useful to the scientific community in evaluating the prospective characteristics of CuO-doped glass systems and related glass compositions. CuO-doped glass systems and associated glass compositions have a wide range of properties.

scholarly journals The Potentials of Egyptian and Indian Granites for Protection of Ionizing Radiation

Materials ◽  
2021 ◽  
Vol 14 (14) ◽  
pp. 3928
Author(s):  
Mohamed Elsafi ◽  
M. F. Alrashedi ◽  
M. I. Sayyed ◽  
Ibrahim F. Al-Hamarneh ◽  
M. A. El-Nahal ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Atomic Number ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
High Energy ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Buildup Factor ◽  
Practical Applications ◽  
Wide Range

This paper aims to study the radiation shielding characteristics and buildup factor of some types of granite in Egypt. The mass attenuation coefficient (MAC) for three types of granite (gandola, white halayeb, and red aswani) was experimentally determined, and the experimental results were validated by XCOM software. The relative deviation between the two methods does not exceed 3% in all discussed granite samples, which means that MAC calculated through the experimental and XCOM are in suitable agreement. The effective atomic number (Zeff) varies from 13.64 to 10.69, 13.68 to 10.59, and 13.45 and 10.66 for gandola, white halayeb, and red aswani, respectively. As well as the equivalent atomic number (Zeq) was calculated in a wide range of energy to deduce the exposure (EBF) and energy absorption (EABF) buildup factors for the studied granite materials. The linear attenuation coefficient (LAC), half-value layer (HVL), mean free path (MFP) were calculated at each investigated energy and showed that the most effective shielding ability at high energy was red aswani, while at low energy, the shielding ability was nearly constant for studied granites. The present study forms the first endeavor to obtain the radiation shielding properties of the studied materials to be used in practical applications.

scholarly journals Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability

Materials ◽  
2021 ◽  
Vol 14 (16) ◽  
pp. 4697
Author(s):  
Ahmed M. El-Khatib ◽  
Mohamed Elsafi ◽  
Mohamed N. Almutiri ◽  
R. M. M. Mahmoud ◽  
Jamila S. Alzahrani ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Point Sources ◽  
Linear Attenuation Coefficient ◽  
Buildup Factor ◽  
Chemical Compositions ◽  
Attenuation Coefficients ◽  
Water Holding ◽  
Mixed Samples

The gamma-ray shielding ability of various Bentonite–Cement mixed materials from northeast Egypt have been examined by determining their theoretical and experimental mass attenuation coefficients, μm (cm2g−1), at photon energies of 59.6, 121.78, 344.28, 661.66, 964.13, 1173.23, 1332.5 and 1408.01 keV emitted from 241Am, 137Cs, 152Eu and 60Co point sources. The μm was theoretically calculated using the chemical compositions obtained by Energy Dispersive X-ray Analysis (EDX), while a NaI (Tl) scintillation detector was used to experimentally determine the μm (cm2g−1) of the mixed samples. The theoretical values are in acceptable agreement with the experimental calculations of the XCom software. The linear attenuation coefficient (μ), mean free path (MFP), half-value layer (HVL) and the exposure buildup factor (EBF) were also calculated by knowing the μm values of the examined samples. The gamma-radiation shielding ability of the selected Bentonite–Cement mixed samples have been studied against other puplished shielding materials. Knowledge of various factors such as thermo-chemical stability, availability and water holding capacity of the bentonite–cement mixed samples can be analyzed to determine the effectiveness of the materials to shield gamma rays.

scholarly journals Novel HMO-Glasses with Sb2O3 and TeO2 for Nuclear Radiation Shielding Purposes: A Comparative Analysis with Traditional and Novel Shields

Materials ◽  
2021 ◽  
Vol 14 (15) ◽  
pp. 4330
Author(s):  
Ghada ALMisned ◽  
Huseyin Ozan Tekin ◽  
Shams A. M. Issa ◽  
Miray Çelikbilek Ersundu ◽  
Ali Erçin Ersundu ◽  
...  
Keyword(s):  
Effective Atomic Number ◽  
Mean Free Path ◽  
General Purpose ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Monte Carlo Code ◽  
Energy Factors ◽  
Effective Removal ◽  
Removal Cross Section ◽  
Detrimental Impact

The radiation shielding characteristics of samples from two TeO2 and Sb2O3-based basic glass groups were investigated in this research. TeO2 and Sb2O3-based glasses were determined in the research as six samples with a composition of 10WO3-(x)MoO3-(90 − x)(TeO2/Sb2O3) (x = 10, 20, 30). A general purpose MCNPX Monte Carlo code and Phy-X/PSD platform were used to estimate the radiation shielding characteristics. Accordingly, the linear and mass attenuation coefficients, half value layer, mean free path, variation of the effective atomic number with photon energy, exposure and built-up energy factors, and effective removal cross-section values were determined. It was determined that the results that were produced using the two different techniques were consistent. Based on the collected data, the most remarkable findings were found to be associated with the sample classified as T80 (10WO3 + 10MoO3 + 80TeO2). The current study showed that material density was as equally important as composition in modifying radiation shielding characteristics. With the T80 sample with the greatest density (5.61 g/cm3) achieving the best results. Additionally, the acquired findings were compared to the radiation shielding characteristics of various glass and concrete materials. Increasing the quantity of MoO3 additive, a known heavy metal oxide, in these TeO2 and Sb2O3-based glasses may have a detrimental impact on the change in radiation shielding characteristics.

scholarly journals Tailoring bismuth borate glasses by incorporating PbO/GeO2 for protection against nuclear radiation

2021 ◽  
Vol 11 (1) ◽  
Author(s):  
Ashok Kumar ◽  
Anisha Jain ◽  
M. I. Sayyed ◽  
Farah Laariedh ◽  
K. A. Mahmoud ◽  
...  
Keyword(s):  
Radiation Protection ◽  
Photon Energy ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Neutron Shielding ◽  
Bismuth Borate ◽  
Removal Cross Section ◽  
Buildup Factors

AbstractNuclear radiation shielding capabilities for a glass series 20Bi2O3 − xPbO − (80 − 2x)B2O3 − xGeO2 (where x = 5, 10, 20, and 30 mol%) have been investigated using the Phy-X/PSD software and Monte Carlo N-Particle transport code. The mass attenuation coefficients (μm) of selected samples have been estimated through XCOM dependent Phy-X/PSD program and MCNP-5 code in the photon-energy range 0.015–15 MeV. So obtained μm values are used to calculate other γ-ray shielding parameters such as half-value layer (HVL), mean-free-path (MFP), etc. The calculated μm values were found to be 71.20 cm2/g, 76.03 cm2/g, 84.24 cm2/g, and 90.94 cm2/g for four glasses S1 to S4, respectively. The effective atomic number (Zeff)values vary between 69.87 and 17.11 for S1 or 75.66 and 29.11 for S4 over 0.05–15 MeV of photon-energy. Sample S4, which has a larger PbO/GeO2 of 30 mol% in the bismuth-borate glass, possesses the lowest MFP and HVL, providing higher radiation protection efficiency compared to all other combinations. It shows outperformance while compared the calculated parameters (HVL and MFP) with the commercial shielding glasses, different alloys, polymers, standard shielding concretes, and ceramics. Geometric Progression (G-P) was applied for evaluating the energy absorption and exposure buildup factors at energies 0.015–15 MeV with penetration depths up to 40 mfp. The buildup factors showed dependence on the MFP and photon-energy as well. The studied samples' neutron shielding behavior was also evaluated by calculating the fast neutron removal cross-section (ΣR), i.e. found to be 0.139 cm−1 for S1, 0.133 cm−1 for S2, 0.128 cm−1 for S3, and 0.12 cm−1 for S4. The results reveal a great potential for using a glass composite sample S4 in radiation protection applications.

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.

Improvement of Gamma Radiation Shielding Features for Fluorophosphate Glasses Doping with Sm2O3 (PZBKNA)

2020 ◽  
Vol 15 (11) ◽  
pp. 1374-1380
Author(s):  
H. Almohiy ◽  
M. Saad ◽  
Y. M. AbouDeif ◽  
Iwona Grelowska ◽  
M. Reben ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Cross Sections ◽  
Radiation Safety ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Ordinary Concrete ◽  
Materials Used

This research reported on the radiation safety characteristics of doped fluorophosphate glasses with heavy rare earth lanthanide (Sm2O3) in the composition 40P2O5/30ZnO/20BaF2/3.8K2TeO3/1.2Al2O3/5.0Nb2O5/30000 ppm Sm2O3 and 40P2O5/30ZnO/20BaF2/3.8K2TeO3/1.2Al2O3/5.0Nb2O5/40000 ppm Sm2O3 in mol%. The parameters for shielding like that mass attenuation coefficient, MAC, linear attenuation coefficient, LAC, tenth value layers, TVL, half-value layers, HVL, effective atomic number, (Zeff), mean free path, MFP, electron density, Neff, electronic cross-sections, ECS, and total atomic cross-sections, ACS, were calculated between 0.015 and 15 MB of preparation glasses. The protection parameters of the current glasses are good in comparison to industrial materials used for nuclear shieldings, such as glass RS 253, ordinary concrete (OC), hematite serpenite (HS), or basalt magnet (BM). From the above mention results, the prepared glasses can be used as radiation safety materials.

scholarly journals Gamma Ray Shielding Properties of Yb3+-Doped Calcium Borotellurite Glasses

2021 ◽  
Vol 11 (12) ◽  
pp. 5697
Author(s):  
Aljawhara H. Almuqrin ◽  
M. I. Sayyed
Keyword(s):  
Attenuation Coefficient ◽  
Research Work ◽  
Effective Atomic Number ◽  
Inverse Correlation ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Transmission Factor ◽  
Linear Attenuation Coefficient ◽  
Teo2 Content ◽  
Mass Attenuation

This research work aims to investigate the radiation shielding ability of a Yb3+-doped calcium borotellurite glass system. The system has the basic composition of CaF2–CaO–B2O3–TeO2–Yb2O3 but is denoted as TeBYbn for simplicity. The effect of increasing the TeO2 content in the glasses from 10 to 54 mol% was investigated, with five different chosen compositions and densities. The Phy-X/PSD program was used to investigate the mass attenuation coefficient (µ/ρ) of the samples. The mass attenuation coefficients were theoretically determined by using an online software for the calculation of shielding parameters. Other parameters were then calculated and analyzed, such as the linear attenuation coefficient (µ), transmission factor (TF), radiation protection efficiency (RPE), effective atomic number (Zeff), and mean free path (MFP). TeBYb5, the glass with the greatest TeO2 content, was shown to have the greatest µ/ρ; however, at greater energies, the differences between the values are practically negligible. µ was shown to increase with density, such as from 0.386 cm−1 to 0.687 cm−1 for TeBYb1 and TeBYb5 at 0.284 MeV, respectively. The least TF was found for samples with a thickness of 1.5 cm, proving an inverse correlation between the thickness of the sample and the TF. The HVL and TVL of the glasses decreased as the density of the samples increased, which means that TeBYb1 is the least effective out of the investigated glasses. The five samples proved to have a lower MFP than some other shielding glasses, demonstrating their capabilities as radiation shields. Based on the calculated parameters, TeBYb5 indicated the greatest photon attenuation ability.

scholarly journals Investigation of Radiation Shielding Efficacy of Vanadium–Tellurite–Antimonite Semiconducting Glasses

2020 ◽  
Author(s):  
Yasser Rammah ◽  
I.O. Olarinoye ◽  
F.I. El-Agawany ◽  
K A Mahmoud ◽  
Iskender Akkurt ◽  
...  
Keyword(s):  
Cross Section ◽  
Effective Atomic Number ◽  
Effective Cross Section ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Alpha Particles ◽  
Fast Neutrons ◽  
Linear Attenuation Coefficient ◽  
Antimony Trioxide ◽  
Simulation Code

Abstract Effects of antimony trioxide (Sb2O3) on neutron and gamma-radiation shielding parameters of tellurite vanadio-antimonite glasses with compositions 40TeO2-(60-x)V2O5-xSb2O3: 0 ≤ xSb2O3 ≤ 10 mol% coded as (TVS0-TVS10) were investigated. The mass attenuation coefficients (MAC) were evaluated using the Monte Carlo simulation code (MCNP-5) and WinXcom program for photon energies in the range of 15 keV to 15 MeV. The SRIM program was used to compute the stopping power and projected range of the charged particles, such as proton and alpha particles, on the investigated glass samples. Based on the theoretically evaluated MAC, some shielding parameters were computed, such as linear attenuation coefficient, electric cross-section, atomic cross-section, effective atomic number, half-value thickness (HVT), and the mean free path. The EXABCal program was applied to predict the level of the photons accumulation in the investigated glass samples (buildup factors). The effective cross-section for fast neutrons was computed theoretically based on the fast neutron effective removal cross-section (ΣR ) for the constituting components. Results revealed that the maximum values of MAC exceed in the range between 28.9-31.3 cm2/g with increasing the Sb2O3 substitution ratio between 0-10 mol %, respectively. In contrast, the HVT values decrease with an increase in the increment of Sb2O3 rate. The maximum (ΣR) was obtained for glass coded TVS0 among the investigated glasses. Results concluded that the higher Sb2O3 concentration in TVS glasses leads to an increase in their capability to apply in several radiation shielding applications.

scholarly journals A Systematical Characterization of TeO2–V2O5 Glass System Using Boron (III) Oxide and Neodymium (III) Oxide Substitution: Resistance Behaviors against Ionizing Radiation

2021 ◽  
Vol 11 (7) ◽  
pp. 3035
Author(s):  
H. O. Tekin ◽  
Shams A. M. Issa ◽  
G. Kilic ◽  
Hesham M. H. Zakaly ◽  
N. Tarhan ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Glass System ◽  
Buildup Factor ◽  
Attenuation Coefficients ◽  
Gamma Ray Attenuation ◽  
Buildup Factors

This study aimed to perform an extensive characterization of a 74.75TeO2–0.25V2O5–(25 − x)B2O3-xNd2O3 glass system with (x = 0, 0.5, 1.0, and 1.5 mol%) for radiation shielding properties. Linear and mass attenuation coefficients were determined using Phy-X PSD software and compared with the simulation using Monte Carlo software MCNPX (version 2.7.0). Half value layer, mean free path, tenth value layer, effective atomic number, exposure buildup factor, and energy absorption buildup factors of VTBNd0.0, VTBNd0.5, VTBNd1.0, and VTBNd1.5 glasses were determined, respectively. The results showed that boron (III) oxide and neodymium (III) oxide substitution has an obvious impact on the gamma ray attenuation properties of the studied glasses. It can be concluded that the VTBNd1.5 sample with the highest content of neodymium (III) oxide (1.5 mol%) is the superior sample for shielding of gamma radiation in the investigated energy range.

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