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 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 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 Optimizing the shielding properties of strength-enhanced concrete containing marble

2020 ◽  
Vol 12 ◽  
pp. 120005
Author(s):  
Ahmed ABDEL-LATIF ◽  
Maged Kassab ◽  
M. I. Sayyed ◽  
H. O. Tekin
Keyword(s):  
Compressive Strength ◽  
Gamma Ray ◽  
Low Cost ◽  
Effective Atomic Number ◽  
Neutron Radiation ◽  
Mean Free Path ◽  
Strength Properties ◽  
Radiation Shielding ◽  
Removal Cross Section ◽  
Shielding Properties

The purpose of this study is to develop a low cost, locally produced concrete mixture with optimum marble content. The resulting mixture would have enhanced strength properties compared to the non-marble reference concrete, and improved radiation shielding properties. To accomplish these goals five concrete mixtures were prepared, containing 0, 5, 10, 15, and 20% marble waste powder as a cement replacement on the basis of weight.These samples were subjected to a compressive strength test. The shielding parameters such as mass attenuation coefficients μm, mean free path MFP, effective atomic number $Z_{eff}$ and exposure build-up factors EBF were measured, and results were compared with those obtained using the WinXcom program and MCNPX code in the photon energy range of 0.015 - 3 MeV. Moreover, the macroscopic fast neutron removal cross-section (neutron attenuation coefficient) was calculated and the results presented. The results show that the sample which contains 10% marble has the highest compressive strength and potentiallygood gamma ray and neutron radiation shielding properties.

scholarly journals Detailed Inspection of γ-ray, Fast and Thermal Neutrons Shielding Competence of Calcium Oxide or Strontium Oxide Comprising Bismuth Borate Glasses

Materials ◽  
2021 ◽  
Vol 14 (9) ◽  
pp. 2265
Author(s):  
Gandham Lakshminarayana ◽  
Youssef Elmahroug ◽  
Ashok Kumar ◽  
Huseyin Ozan Tekin ◽  
Najeh Rekik ◽  
...  
Keyword(s):  
Atomic Number ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Intermediate Energy ◽  
Fast Neutrons ◽  
Attenuation Coefficients ◽  
Neutron Attenuation ◽  
Removal Cross Section ◽  
Γ Ray ◽  
Buildup Factors

For both the B2O3-Bi2O3-CaO and B2O3-Bi2O3-SrO glass systems, γ-ray and neutron attenuation qualities were evaluated. Utilizing the Phy-X/PSD program, within the 0.015–15 MeV energy range, linear attenuation coefficients (µ) and mass attenuation coefficients (μ/ρ) were calculated, and the attained μ/ρ quantities match well with respective simulation results computed by MCNPX, Geant4, and Penelope codes. Instead of B2O3/CaO or B2O3/SrO, the Bi2O3 addition causes improved γ-ray shielding competence, i.e., rise in effective atomic number (Zeff) and a fall in half-value layer (HVL), tenth-value layer (TVL), and mean free path (MFP). Exposure buildup factors (EBFs) and energy absorption buildup factors (EABFs) were derived using a geometric progression (G–P) fitting approach at 1–40 mfp penetration depths (PDs), within the 0.015–15 MeV range. Computed radiation protection efficiency (RPE) values confirm their excellent capacity for lower energy photons shielding. Comparably greater density (7.59 g/cm3), larger μ, μ/ρ, Zeff, equivalent atomic number (Zeq), and RPE, with the lowest HVL, TVL, MFP, EBFs, and EABFs derived for 30B2O3-60Bi2O3-10SrO (mol%) glass suggest it as an excellent γ-ray attenuator. Additionally, 30B2O3-60Bi2O3-10SrO (mol%) glass holds a commensurably bigger macroscopic removal cross-section for fast neutrons (ΣR) (=0.1199 cm−1), obtained by applying Phy-X/PSD for fast neutrons shielding, owing to the presence of larger wt% of ‘Bi’ (80.6813 wt%) and moderate ‘B’ (2.0869 wt%) elements in it. 70B2O3-5Bi2O3-25CaO (mol%) sample (B: 17.5887 wt%, Bi: 24.2855 wt%, Ca: 11.6436 wt%, and O: 46.4821 wt%) shows high potentiality for thermal or slow neutrons and intermediate energy neutrons capture or absorption due to comprised high wt% of ‘B’ element in it.

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.

scholarly journals Investigations of gamma ray and fast neutron shielding properties of tellurite glasses with different oxide compositions

2016 ◽  
Vol 94 (11) ◽  
pp. 1133-1137 ◽  
Author(s):  
M.I. Sayyed
Keyword(s):  
Photon Energy ◽  
Gamma Ray ◽  
Effective Atomic Number ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Fast Neutrons ◽  
Tellurite Glasses ◽  
Neutron Shielding ◽  
Shielding Properties ◽  
Mass Attenuation

In the present paper, the basic radiation parameters of tellurite glasses with different forming oxides (B2O3, BaO, K2O, V2O5, WO3, and ZnO) have been studied over a wide photon energy range from 1 keV to 100 GeV, using WinXCom program. These parameters are the mass attenuation coefficient (μ/ρ), effective atomic number (Zeff), and electron density (Ne,eff). In addition, the macroscopic effective removal cross sections (ΣR) for fast neutrons have been calculated. The dependence of different parameters on incident photon energy and chemical content has been discussed. Among the selected glass systems TeO2–WO3 and TeO2–B2O3 showed superior shielding properties for gamma-ray and neutrons, respectively. It is shown that the selected glass systems have higher values of the mass attenuation coefficients (μ/ρ) than concretes and 0.7SiO2:0.3BaO glass. These results indicate that tellurite glasses can be used as radiation shielding materials.

Radiation attenuation properties of B2O3-ZnO-Al2O3-Bi2O3-Sm2O3 glasses

2021 ◽  
Vol 0 (0) ◽  
Author(s):  
Canel Eke
Keyword(s):  
Photon Energy ◽  
Cross Sections ◽  
Effective Atomic Number ◽  
Radiation Shielding ◽  
Radiation Absorption ◽  
Absorption Properties ◽  
Effective Electron ◽  
Protection Efficiency ◽  
Transmission Factors ◽  
Buildup Factors

Abstract The goal of this study is to examine theoretically radiation absorption properties of zinc alumino bismuth borate (BZnAlBiSm) glasses with chemical formula 60B2O3-9ZnO-(30-x)Al2O3-xBi2O3-1Sm2O3 where x = 5, 10, 15 and 20 mol%. The linear and mass attenuation coefficents of BZnAlBiSm glasses turn out as this trend BZnAlBiSm-1<BZnAlBiSm-2<BZnAlBiSm-3<BZnAlBiSm-4. The BZnAlBiSm-4 with the smallest half value layers, tenth value layers and mean free paths in the examined energy ranges has the superior radiation shielding characteristics among the BZnAlBiSm glasses. The BZnAlBiSm-4 glass has the highest radiation protection efficiency among the BZnAlBiSm glasses. The transmission factors increase as photon energy range enhances from 0.015 to 15 MeV and thickness declines from 2.5 to 0.5 cm. The energy buildup factors and energy absorption buildup factors of BZnAlBiSm glasses reduce from 15 to 1 mfp. Variation of the effective atomic number and effective electron density as a function of photon energy for BZnAlBiSm glasses are similar. The projected ranges of electron, proton, alpha and carbon for the BZnAlBiSm glasses increase as photon energy enlarges. The fast neutron removal cross sections of the BZnAlBiSm glasses vary in order of BZnAlBiSm-4<BZnAlBiSm-3<BZnAlBiSm-2<BZnAlBiSm-1. Thus, it can be concluded that BZnAlBiSm-1 has the highest neutron absorption ability among the BZnAlBiSm 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 A Comprehensive Study on Gamma Rays and Fast Neutron Sensing Properties of GAGOC and CMO Scintillators for Shielding Radiation Applications

2017 ◽  
Vol 2017 ◽  
pp. 1-9 ◽  
Author(s):  
Shams A. M. Issa ◽  
M. I. Sayyed ◽  
M. H. M. Zaid ◽  
K. A. Matori
Keyword(s):  
Energy Range ◽  
Fast Neutron ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Nuclear Radiation ◽  
Space Technology ◽  
Effective Electron ◽  
Geometrical Progression ◽  
Broad Energy Range ◽  
Removal Cross Section

The WinXCom program has been used to calculate the mass attenuation coefficients (μm), effective atomic numbers (Zeff), effective electron densities (Nel), half-value layer (HVL), and mean free path (MFP) in the energy range 1 keV–100 GeV for Gd3Al2Ga3O12Ce (GAGOC) and CaMoO4 (CMO) scintillator materials. The geometrical progression (G-P) method has been used to compute the exposure buildup factors (EBF) and gamma ray energy absorption (EABF) in the photon energy range 0.015–15 MeV and up to a 40 penetration depth (mfp). In addition, the values of the removal cross section for a fast neutron ∑R have been calculated. The computed data observes that GAGOC showed excellent γ-rays and neutrons sensing a response in the broad energy range. This work could be useful for nuclear radiation sensors, detectors, nuclear medicine applications (medical imaging and mammography), nuclear engineering, and space technology.

scholarly journals Photon Shielding Characterization of SiO2-PbO-CdO-TiO2 Glasses for Radiotheraphy Shielding Application

2021 ◽  
pp. 32-38
Author(s):  
Idris M. Mustapha ◽  
Atimga B. James ◽  
Sulayman M. Bello
Keyword(s):  
Attenuation Coefficient ◽  
Energy Region ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Photoelectric Effect ◽  
High Energy ◽  
Radiation Shielding ◽  
Sudden Increase ◽  
Mass Attenuation

In this study, photon attenuation parameters of (30-x) SiO2–15PbO–10CdO-xTiO2, with x = 0, 2, 4, 6, 8 and 10% mol, were determined and their application as shielding material were discussed. The WinXCOM software was used to determine the mass attenuation coefficient of the studied glasses for the energy range (0.015-15MeV). The mass attenuation coefficient of the glass samples first decline up to 0.09 MeV and slightly increase abruptly and then declined uniformly for all the glasses to approximately zero after about 10 MeV.   The effective atomic number (Zeff) was also calculated for the glass samples and were observe to raise from 0.015 to 0.02 MeV and then decreased between 0.02-5 MeV. On account of the dominance of the photoelectric effect in the low energy region, there was a sudden increase in Zeff at about 0.08 MeV close to the absorption edge of the Pb (0.088 MeV). The rapid increment was observed at 0.1–1.5 MeV by transcending typical Compton scattering interaction at intermediate energies for Zeff'’s and began to decrease in the same form again. The lower Zeff   values were found in low and high energy region for all SPCT glasses. The calculated mean free path, half value layer and tenth value layer values were observe to decline as the TiO2 doping of the glasses increased which accounts for the  three photon interaction mechanisms effectiveness in the variation of MFP and HVL values with energy. It can be concluded that SPCT glasses may be considered an alternative material for radiation shielding practices.

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