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V Zaconte - One of the best experts on this subject based on the ideXlab platform.
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performances of kevlar and polyethylene as Radiation Shielding on board the international space station in high latitude Radiation environment
Scientific Reports, 2017Co-Authors: L Narici, M Casolino, Luca Di Fino, Marianna Larosa, Piergiorgio Picozza, A Rizzo, V ZaconteAbstract:Passive Radiation Shielding is a mandatory element in the design of an integrated solution to mitigate the effects of Radiation during long deep space voyages for human exploration. Understanding and exploiting the characteristics of materials suitable for Radiation Shielding in space flights is, therefore, of primary importance. We present here the results of the first space-test on Kevlar and Polyethylene Radiation Shielding capabilities including direct measurements of the background baseline (no shield). Measurements are performed on-board of the International Space Station (Columbus modulus) during the ALTEA-shield ESA sponsored program. For the first time the Shielding capability of such materials has been tested in a Radiation environment similar to the deep-space one, thanks to the feature of the ALTEA system, which allows to select only high latitude orbital tracts of the International Space Station. Polyethylene is widely used for Radiation Shielding in space and therefore it is an excellent benchmark material to be used in comparative investigations. In this work we show that Kevlar has Radiation Shielding performances comparable to the Polyethylene ones, reaching a dose rate reduction of 32 ± 2% and a dose equivalent rate reduction of 55 ± 4% (for a shield of 10 g/cm2).
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Performances of Kevlar and Polyethylene as Radiation Shielding on-board the International Space Station in high latitude Radiation environment
Scientific Reports, 2017Co-Authors: L Narici, M Casolino, Luca Di Fino, Marianna Larosa, Piergiorgio Picozza, A Rizzo, V ZaconteAbstract:Passive Radiation Shielding is a mandatory element in the design of an integrated solution to mitigate the effects of Radiation during long deep space voyages for human exploration. Understanding and exploiting the characteristics of materials suitable for Radiation Shielding in space flights is, therefore, of primary importance. We present here the results of the first space-test on Kevlar and Polyethylene Radiation Shielding capabilities including direct measurements of the background baseline (no shield). Measurements are performed on-board of the International Space Station (Columbus modulus) during the ALTEA-shield ESA sponsored program. For the first time the Shielding capability of such materials has been tested in a Radiation environment similar to the deep-space one, thanks to the feature of the ALTEA system, which allows to select only high latitude orbital tracts of the International Space Station. Polyethylene is widely used for Radiation Shielding in space and therefore it is an excellent benchmark material to be used in comparative investigations. In this work we show that Kevlar has Radiation Shielding performances comparable to the Polyethylene ones, reaching a dose rate reduction of 32 ± 2% and a dose equivalent rate reduction of 55 ± 4% (for a shield of 10 g/cm^2).
Shams A.m. Issa - One of the best experts on this subject based on the ideXlab platform.
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Novel HMO-Glasses with Sb2O3 and TeO2 for Nuclear Radiation Shielding Purposes: A Comparative Analysis with Traditional and Novel Shields
'MDPI AG', 2021Co-Authors: Ghada Almisned, Huseyin Ozan Tekin, Shams A.m. Issa, Hesham M H Zakaly, Miray Çelikbilek Ersundu, Ali Erçin Ersundu, Gokhan Kilic, Antoaneta EneAbstract: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
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optical and nuclear Radiation Shielding properties of zinc borate glasses doped with lanthanum oxide
Journal of Non-crystalline Solids, 2020Co-Authors: Hesham M H Zakaly, Shams A.m. Issa, A S Abouhaswa, Mostafa Y A Mostafa, Mariia Pyshkina, R ElmallawanyAbstract:Abstract In this study, structure, optical and nuclear Radiation Shielding behaviors of (50-x)B2O3-30PbO-20ZnO-xLa2O3, (x = 0, 1.5, 3, 4.5, and 6) wt% glasses with various La2O3 concentrations were measured for their nuclear Radiation Shielding applications. Moreover, UV–visible absorption spectrum and the glass optical parameters were measured. The band gaps of optical energy for direct transition decreased from 3.90 eV for BPZLa1 glass sample to 2.78 eV for BPZLa5 glass, while it decreased from 2.58 eV to 1.83 eV glass for the indirect transition. The mass attenuation coefficient (μm) was experimentally measured using the HPGe spectrometer. The experimental results of Shielding parameters were compared with values obtained using the XCOM program and FLUKA simulation code. The nuclear Radiation Shielding properties such as μm, HVL, Zeff, EBF and EABF were calculated for all glasses with various La2O3 concentrations. The results showed that μm and Zeff increased as the La2O3 concentration increased. The BPZLa5 glass sample had the minimum HVL, EBF and EABF. The BPZLa5 sample had the largest μm, Zeff.
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Lead borate glasses and synergistic impact of lanthanum oxide additive: optical and nuclear Radiation Shielding behaviors
Journal of Materials Science: Materials in Electronics, 2020Co-Authors: A S Abouhaswa, Shams A.m. Issa, Hesham M H Zakaly, Mariia Pyshkina, R. El-mallawany, Mostafa Y A MostafaAbstract:Composition of (50 − x ) B_2O_3–30PbO–20ZnO– x La_2O_3 ( x = 0, 1.5, 3, 4.5, and 6) wt% glass system were synthesized using quench melt technique and simulated for their nuclear Radiation Shielding properties. Moreover, UV–visible absorption spectrum among 190–1100 nm and the glass optical parameters were measured. The optical energy gap ( E _g), the single-oscillator energy ( E _o), the dispersion energy parameter ( E _d), refractive index ( n ), and refractive dispersion index (no) were estimated. The obtained results indicated that ( E _g) was decreased with increasing La_2O_3 content, but the refractive index ( n ) was increased. The addition of La_2O_3 to glass network could provide preferable Shielding features. The chosen amount of La and another metal oxide has been added to the glass. Shielding parameters such as half-value layer (HVL), mean free path (MFP), mass attenuation coefficient (MAC), and exposure rate in the photon energy range 15–300 keV have been simulated by MicroShield software. These results illustrate that the La5 glass sample has the best Radiation Shielding properties, among other investigated glasses. This type of glass sample can utilize for the construction of the monitoring screening windows in Radiation areas, plats, or screening windows in X-ray diagnostic and for the walls of CT-scanner rooms.
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newly developed bgo glasses synthesis optical and nuclear Radiation Shielding properties
Ceramics International, 2020Co-Authors: Huseyin Ozan Tekin, Luciana R. P. Kassab, Shams A.m. Issa, M M Martins, L Bontempo, Guilherme Rodrigues Da Silva MattosAbstract:Abstract In this research paper, we studied the optical and nuclear Shielding efficiency of newly developed BGO glasses with the following compositions (in wt%): 32Bi2O3–68GeO2, 42Bi2O3–58GeO2, 47Bi2O3–53GeO2, 52Bi2O–48GeO2, 62Bi2O3–38GeO2. BGO glasses were prepared by traditional melt quenching method. To obtain the band gap values of fabricated BGO glasses, optical absorption spectra were used for evaluation of optical properties. The mass attenuation coefficients (μ/ρ) were achieved for prepared glasses at 0.015–15 MeV photon energies employing MCNPX Monte Carlo code and WinXcom program. Moreover, broad-range of nuclear Shielding parameters for gamma ray, neutrons and charged particles such as mass attenuation coefficient, half value layer, effective atomic number, buildup factors, mass stopping powers, projected ranges, fast neutron removal cross sections and damage factors were calculated. The refractive index is calculated from Eopt, As Bi2O3 concentration is enhanced, Eopt is also increased as well as the optical electronegativity and consequently the refractive index. In addition, the results showed that BIGE5 glass sample with highest Bi2O3 contribution has excellent nuclear Radiation Shielding ability among the other fabricated glass samples.
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enhancement of nuclear Radiation Shielding and mechanical properties of ybibo3 glasses using la2o3
Nuclear Engineering and Technology, 2020Co-Authors: H.o. Tekin, Shams A.m. Issa, Atif Mossad Ali, Yasser B Saddeek, Ali Alhajry, H Algarni, G SusoyAbstract:Abstract In this study, nuclear Radiation Shielding and rigidity parameters of Y (0.1-x)B0.6Bi1.8O3La2x glassy system were investigated in order to determine it's suitability for use as nuclear Radiation Shielding materials. Therefore, a group of bismuth borate glass samples with La2O3 additive were synthesized using the technique of melt quenching. According to the results, the increase of the La2O3 additive increases the density of the glass samples and the mass attenuation coefficient (μm) values, whereas the half-value layer (HVL) and mean free path (MFP) values decrease. The effective atomic number (Zeff) is also enhanced with an increment of both mass removal cross section for neutron (∑R) and absorption neutron scattering cross section (σabs). In addition to the other parameters, rigidity parameter values were theoretically examined. The increase of La2O3 causes some other important magnitudes to increase. These are the average crosslink density, the number of bonds per unit volume, as well as the stretching force constant values of these glass samples. These results are in concordance with the increase of elastic moduli in terms of the Makishima-Mackenzie model. This model showed an increase in the rigidity of the glass samples as a function of La2O3.
L Narici - One of the best experts on this subject based on the ideXlab platform.
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performances of kevlar and polyethylene as Radiation Shielding on board the international space station in high latitude Radiation environment
Scientific Reports, 2017Co-Authors: L Narici, M Casolino, Luca Di Fino, Marianna Larosa, Piergiorgio Picozza, A Rizzo, V ZaconteAbstract:Passive Radiation Shielding is a mandatory element in the design of an integrated solution to mitigate the effects of Radiation during long deep space voyages for human exploration. Understanding and exploiting the characteristics of materials suitable for Radiation Shielding in space flights is, therefore, of primary importance. We present here the results of the first space-test on Kevlar and Polyethylene Radiation Shielding capabilities including direct measurements of the background baseline (no shield). Measurements are performed on-board of the International Space Station (Columbus modulus) during the ALTEA-shield ESA sponsored program. For the first time the Shielding capability of such materials has been tested in a Radiation environment similar to the deep-space one, thanks to the feature of the ALTEA system, which allows to select only high latitude orbital tracts of the International Space Station. Polyethylene is widely used for Radiation Shielding in space and therefore it is an excellent benchmark material to be used in comparative investigations. In this work we show that Kevlar has Radiation Shielding performances comparable to the Polyethylene ones, reaching a dose rate reduction of 32 ± 2% and a dose equivalent rate reduction of 55 ± 4% (for a shield of 10 g/cm2).
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Performances of Kevlar and Polyethylene as Radiation Shielding on-board the International Space Station in high latitude Radiation environment
Scientific Reports, 2017Co-Authors: L Narici, M Casolino, Luca Di Fino, Marianna Larosa, Piergiorgio Picozza, A Rizzo, V ZaconteAbstract:Passive Radiation Shielding is a mandatory element in the design of an integrated solution to mitigate the effects of Radiation during long deep space voyages for human exploration. Understanding and exploiting the characteristics of materials suitable for Radiation Shielding in space flights is, therefore, of primary importance. We present here the results of the first space-test on Kevlar and Polyethylene Radiation Shielding capabilities including direct measurements of the background baseline (no shield). Measurements are performed on-board of the International Space Station (Columbus modulus) during the ALTEA-shield ESA sponsored program. For the first time the Shielding capability of such materials has been tested in a Radiation environment similar to the deep-space one, thanks to the feature of the ALTEA system, which allows to select only high latitude orbital tracts of the International Space Station. Polyethylene is widely used for Radiation Shielding in space and therefore it is an excellent benchmark material to be used in comparative investigations. In this work we show that Kevlar has Radiation Shielding performances comparable to the Polyethylene ones, reaching a dose rate reduction of 32 ± 2% and a dose equivalent rate reduction of 55 ± 4% (for a shield of 10 g/cm^2).
M I Sayyed - One of the best experts on this subject based on the ideXlab platform.
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Nuclear Radiation Shielding Characteristics of Some Natural Rocks by Using EPICS2017 Library
'MDPI AG', 2021Co-Authors: Mohammed Sultan Al-buriahi, M I Sayyed, Rashad A. R. Bantan, Yas Al-hadeethiAbstract:Radiation leakage is a serious problem in various technological applications. In this paper, Radiation Shielding characteristics of some natural rocks are elucidated. Mass attenuation coefficients (µ/ρ) of these rocks are obtained at different photon energies with the help of the EPICS2017 library. The obtained µ/ρ values are confirmed via the theoretical XCOM program by determining the correlation factor and relative deviation between both of these methods. Then, effective atomic number (Zeff), absorption length (MFP), and half value layer (HVL) are evaluated by applying the µ/ρ values. The maximum μ/ρ values of the natural rocks were observed at 0.37 MeV. At this energy, the Zeff values of the natural rocks were 16.23, 16.97, 17.28, 10.43, and 16.65 for olivine basalt, jet black granite, limestone, sandstone, and dolerite, respectively. It is noted that the Radiation Shielding features of the selected natural rocks are higher than that of conventional concrete and comparable with those of commercial glasses. Therefore, the present rocks can be used in various Radiation Shielding applications, and they have many advantages for being clean and low-cost products. In addition, we found that the EPICS2017 library is useful in determining the Radiation Shielding parameters for the rocks and may be used for further calculations for other rocks and construction building materials
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Effect of rare earth dopants on the Radiation Shielding properties of barium tellurite glasses
'Elsevier BV', 2021Co-Authors: P. Vani, M I Sayyed, G. Vinitha, Maha M. Alshammari, N. ManikandanAbstract:Rare earth doped barium tellurite glasses were synthesised and explored for their Radiation Shielding applications. All the samples showed good thermal stability with values varying between 101 °C and 135 °C based on dopants. Structural properties showed the dominance of matrix elements compared to rare earth dopants in forming the bridging and non-bridging atoms in the network. Bandgap values varied between 3.30 and 4.05 eV which was found to be monotonic with respective rare earth dopants indicating their modification effect in the network. Various Radiation Shielding parameters like linear attenuation coefficient, mean free path and half value layer were calculated and each showed the effect of doping. For all samples, LAC values decreased with increase in energy and is attributed to photoelectric mechanism. Thulium doped glasses showed the highest value of 1.18 cm−1 at 0.245 MeV for 2 mol.% doping, which decreased in the order of erbium, holmium and the base barium tellurite glass, while half value layer and mean free paths showed an opposite trend with least value for 2 mol.% thulium indicating that thulium doped samples are better attenuators compared to undoped and other rare earth doped samples. Studies indicate an increased level of thulium doping in barium tellurite glasses can lead to efficient Shielding materials for high energy Radiation
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Experimental investigation of zinc sodium borate glass systems containing barium oxide for gamma Radiation Shielding applications
'Elsevier BV', 2021Co-Authors: A. Aboalatta, M I Sayyed, J. Asad, M. Humaid, H. Musleh, S.k.k. Shaat, Kh Ramadan, Y. Alajerami, N. AldahoudiAbstract:Sodium zinc borate glasses doped with dysprosium and modified with different concentrations of barium oxide (0–50 mol %) were fabricated using the melting quenching technique. The structural properties of the prepared glass systems were characterized using XRD and FTIR methods. The absorption spectra of the prepared glasses were measured to determine their energy gap and their related optical properties. The density of the glasses and other physical parameters were also reported. Additionally, with the help of Photon Shielding and Dosimetry (PSD) software, we investigated the Radiation Shielding parameters of the prepared glass systems at different energy values. It was found that an increase in the density of the glasses by increasing the concentration of BaO significantly improved the gamma ray Shielding ability of the samples. For practical results, a compatible irRadiation set up was designed to check the Shielding capability of the obtained glasses using a gamma ray source at 662 keV. The experimentally obtained results strongly agreed with the data obtained by PDS software at the same energy. These results demonstrated that the investigated glass system is a good candidate for several Radiation Shielding applications when comparing it with other commercial Shielding glasses and concretes
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Experimental and Theoretical Study of Radiation Shielding Features of CaO-K2O-Na2O-P2O5 Glass Systems
'MDPI AG', 2021Co-Authors: M I Sayyed, Ashok Kumar, Badriah Albarzan, Aljawhara H. Almuqrin, Ahmed M. El-khatib, Daria I. Tishkevich, Alex V. Trukhanov, Mohamed ElsafiAbstract:The gamma Radiation Shielding ability for CaO-K2O-Na2O-P2O5 glasses were experimentally determined between 0.0595 and 1.41 MeV. The experimental MAC results were compared with theoretical results obtained from the XCOM software to test the accuracy of the experimental values. Additionally, the effect of increasing the P2O5 in the glass composition, or reducing the Na2O content, was evaluated at varying energies. For the fabricated glasses, the experimental data strongly agreed with the XCOM results. The effective atomic number (Zeff) of the fabricated glasses was also determined. The Zeff values start out at their maximum (12.41–12.55) at the lowest tested energy, 0.0595 MeV, and decrease to 10.69–10.80 at 0.245 MeV. As energy further increases, the Zeff values remain almost constant between 0.344 and 1.41 MeV. The mean free path (MFP) of the fabricated glasses is investigated and we found that the lowest MFP value occurs at the lowest tested energy, 0.0595 MeV, and lies within the range of 1.382–1.486 cm, while the greatest MFP can be found at the highest tested energy, 1.41 MeV, within the range of 8.121–8.656 cm. At all energies, the KCNP40 sample has the lowest MFP, while the KCNP60 sample has the greatest. The half value layer (HVL) for the KCNP-X glasses is determined. For all the selected energies, the HVL values follow the order of KCNP40 2O5 content in the glasses improves the Radiation Shielding ability of the samples. Thus, the KCNP40 sample has the best potential for photon attenuation applications
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The Role of La2O3 in Enhancement the Radiation Shielding Efficiency of the Tellurite Glasses: Monte-Carlo Simulation and Theoretical Study
'MDPI AG', 2021Co-Authors: Aljawhara H. Almuqrin, M I Sayyed, Mohamed Hanfi, K. G. Mahmoud, Hanan Al-ghamdi, Dalal Abdullah AlorainiAbstract:The Radiation Shielding competence was examined for a binary glass system xLa2O3 + (1 − x) TeO2 where x = 5, 7, 10, 15, and 20 mol% using MCNP-5 code. The linear attenuation coefficients (LACs) of the glasses were evaluated, and it was found that LT20 glass has the greatest LAC, while LT5 had the least LAC. The transmission factor (TF) of the glasses was evaluated against thicknesses at various selected energies and was observed to greatly decrease with increasing thickness; for example, at 1.332 MeV, the TF of the LT5 glass decreased from 0.76 to 0.25 as the thickness increased from 1 to 5 cm. The equivalent atomic number (Zeq) of the glasses gradually increased with increasing photon energy above 0.1 MeV, with the maximum values observed at around 1 MeV. The buildup factors were determined to evaluate the accumulation of photon flux, and it was found that the maximum values for both can be seen at around 0.8 MeV. This research concluded that LT20 has the greatest potential in Radiation Shielding applications out of the investigated glasses due to the glass having the most desirable parameters
H.o. Tekin - One of the best experts on this subject based on the ideXlab platform.
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enhancement of nuclear Radiation Shielding and mechanical properties of ybibo3 glasses using la2o3
Nuclear Engineering and Technology, 2020Co-Authors: H.o. Tekin, Shams A.m. Issa, Atif Mossad Ali, Yasser B Saddeek, Ali Alhajry, H Algarni, G SusoyAbstract:Abstract In this study, nuclear Radiation Shielding and rigidity parameters of Y (0.1-x)B0.6Bi1.8O3La2x glassy system were investigated in order to determine it's suitability for use as nuclear Radiation Shielding materials. Therefore, a group of bismuth borate glass samples with La2O3 additive were synthesized using the technique of melt quenching. According to the results, the increase of the La2O3 additive increases the density of the glass samples and the mass attenuation coefficient (μm) values, whereas the half-value layer (HVL) and mean free path (MFP) values decrease. The effective atomic number (Zeff) is also enhanced with an increment of both mass removal cross section for neutron (∑R) and absorption neutron scattering cross section (σabs). In addition to the other parameters, rigidity parameter values were theoretically examined. The increase of La2O3 causes some other important magnitudes to increase. These are the average crosslink density, the number of bonds per unit volume, as well as the stretching force constant values of these glass samples. These results are in concordance with the increase of elastic moduli in terms of the Makishima-Mackenzie model. This model showed an increase in the rigidity of the glass samples as a function of La2O3.
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the impact of cr2o3 additive on nuclear Radiation Shielding properties of lif sro b2o3 glass system
Materials Chemistry and Physics, 2020Co-Authors: G Susoy, O. Kilicoglu, E Altunsoy E Guclu, M Kamislioglu, M S Alburiahi, Mohamed M Abuzaid, H.o. TekinAbstract:Abstract This study aimed to investigate the Shielding performance of SrO-LiF-B2O3 glasses glass system for nuclear security applications. The MCNPX code (version 2.6.0) and GEANT4 are used to determine the Shielding parameters and the dependence with the composition of each glass, as well as the influence of Cr2O3 additive. A wide-range of nuclear Radiation Shielding investigation for gamma-ray, proton particles, fast neutrons have been studied for five different types of glasses. The calculated values for mass attenuation coefficients (μm) were utilized to determine other vital Shielding properties against gamma-ray Radiation. Furthermore, some of the investigated parameters have been determined by using SRIM code and special calculation methods such as G-P fitting parameters for EBF and EABF calculation. The results showed that C25 glass with the highest Cr2O3 additive had a satisfactory capacity in nuclear Radiation Shielding.
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gamma Radiation Shielding properties of the hematite serpentine concrete blended with wo3 and bi2o3 micro and nano particles using mcnpx code
Radiation Physics and Chemistry, 2018Co-Authors: H.o. Tekin, Shams A.m. Issa, M I SayyedAbstract:Abstract Recently, due to the increasing applications of nano materials, among researchers, there has been great attention paid to the enhancement of the conventional concrete properties. The main aim of this work is to evaluate the influence of WO3 and Bi2O3 additives in micro and nano scales on the Radiation Shielding properties of hematite-serpentine concrete (HSC). For this purpose, the mass attenuation coefficient (µ/ρ) for the HSC concrete blended with WO3 and Bi2O3 in both micro and nano scales was calculated using MCNPX (version 2.6.0) general purpose Monte Carlo code in the photon energy range 0.142–1.33 MeV. Considering the lattice (LAT) and universe (U) features in MCNPX code, micro and nanoparticles with sizes of 50 nm and 50 µm were designed inside HSC concrete, respectively. The results showed that the values of µ/ρ of nanoparticles were higher than those of micro-particles at all selected energies. Additionally, the µ/ρ values of HSC which include Bi2O3 nano particles were higher than that of corresponding WO3 mixtures. It can be concluded that the addition of nanoparticles into HSC leads to improvement in Radiation Shielding characteristics, with potential applications in civil engineering constructions and potential usage as building material for nuclear facilities.
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investigation of structural thermal properties and Shielding parameters for multicomponent borate glasses for gamma and neutron Radiation Shielding applications
Journal of Non-crystalline Solids, 2017Co-Authors: G Lakshminarayana, H.o. Tekin, M I Sayyed, Kawa M Kaky, S O Baki, A Lira, I V Kityk, Mohd Adzir MahdiAbstract:Multicomponent borate glasses with the chemical composition (60 − x) B2O3–10 Bi2O3–10 Al2O3–10 ZnO–10 Li2O–(x) Dy2O3 or Tb4O7 (x = 0.5 mol%), and (60 − x − y) B2O3–10 Bi2O3–10 Al2O3–10 ZnO–10 Li2O–(x) Dy2O3–(y) Tb4O7 (x = 0.25, 0.5, 0.75, 1.0, 1.5, and 2.0 mol%, y = 0.5 mol%) have been fabricated by a conventional melt-quenching technique and were characterized by X-ray diffraction (XRD), Attenuated Total reflectance-Fourier transform Infrared (ATR-FTIR) spectroscopy, Raman spectroscopy, thermo-gravimetric analysis (TGA), and differential scanning calorimetry (DSC). Also, the Radiation Shielding parameters such as mass attenuation coefficient (μ/ρ), half value layer (HVL), mean free path (MFP) and exposure buildup factor (EBF) values were explored within the energy range 0.015 MeV–15 MeV using both XCOM and MCNPX code to determine the penetration of gamma and neutron Radiations in the prepared glasses. The main BO3, BO4, BiO6, and ZnO4 structural units and AlOAl bonds were confirmed by ATR-FTIR and Raman spectroscopy. Weight loss, and the glass transition (Tg), onset crystallization (Tx), and crystallization (Tc) temperatures were determined from TGA and DSC measurements, respectively. The stability of the glass against crystallization (ΔT) is varied within the temperature range 114–135 °C for the studied glasses. In addition, the Shielding parameters like the (μ/ρ) values investigated using both MCNPX Monte Carlo and XCOM software are in good agreement with each other. The (μ/ρ) values calculated using XCOM software were used to evaluate the HVL and MFP in the photon energy range 0.015 MeV–15 MeV. It is found that all the synthesized glasses possess better Shielding properties than ordinary concrete, zinc oxide soda lime silica glass and lead zinc phosphate glass indicating the high potentiality of the prepared glasses to be utilized as Radiation Shielding materials.
