scholarly journals Gamma Attenuation Coefficients of Nano Cadmium Oxide/High density Polyethylene Composites

2019 ◽  
Vol 9 (1) ◽  
Author(s):  
Ahmed M. El-Khatib ◽  
Mahmoud I. Abbas ◽  
Mohamed Abd Elzaher ◽  
Mohamed S. Badawi ◽  
Mahmoud T. Alabsy ◽  
...  

Abstract In the present work, high density polyethylene (HDPE) matrix mixed with micro-sized and nano-sized Cadmium oxide (CdO) particles of different concentrations were prepared by compression molding technique. The aim of the study is to investigate the effect of particle size and weight percentage of CdO particles on the gamma radiation shielding ability of CdO/HDPE composites. The mass attenuation coefficients of pure HDPE, micro-CdO/HDPE and nano-CdO/HDPE composites were evaluated at photon energies ranging from 59.53 keV to 1408.01 keV using standard radioactive point sources [241Am, 133Ba, 137Cs, 60Co and 152Eu]. Adding micro and nano CdO particles to the HDPE matrix clearly increases the mass attenuation coefficients of the composites and the improvement is more significant at low γ-ray energies. The effect of particle size of CdO filler has an important role on the shielding ability of the composite. The experimental results reveal that, the composites filled with nano-CdO have better γ-radiation shielding ability compared to that filled with micro-CdO at the same weight fraction. A relative increase rate of about 16% is obtained with nano-CdO content of 40 wt% at 59.53 keV, which attributed to the higher probability of interaction between γ-rays and nanoparticles. From this study, it can be concluded that nano-CdO has a good performance shielding characteristic than micro-CdO in HDPE based radiation shielding material.

2020 ◽  
Vol 35 (1) ◽  
pp. 42-49
Author(s):  
Gharam Alharshan ◽  
Dalal Aloraini ◽  
Mohamed Elzaher ◽  
Mohamed Badawi ◽  
Mahmoud Alabsy ◽  
...  

In this work, polymer composites of high density polyethylene reinforced by micro-sized and nanosized cadmium oxide, lead oxide, and a mixture of both with filler weight fraction of 30% were prepared by compression molding technique and characterized by scanning electron microscope. This investigation aims to present a comparative study between cadmium oxide and lead oxide according to their sizes as fillers in high density polyethylene polymeric matrix for gamma-radiation shielding applications. The mass and linear attenuation coefficients of the investigated composites were measured as a function of g-ray energies ranging from 59.53 keV to 1408.01 keV using standard radioactive point sources (241Am, 133Ba, 137Cs, 60Co, and 152Eu). The measurements were made with a narrow beam geometry setup using a well calibrated hyper pure germanium cylindrical detector. The theoretical values of the mass attenuation coefficients were evaluated using the XCOM program database. The experimental results demonstrated that, according to the filler size, cadmium oxide composite is better as a gamma absorber in the energy region less than 81 keV, while lead oxide composite is better in the energy region greater than 81 keV. Moreover, for the same chemical structure and weight fraction of the composite, nano fillers show better attenuation performance than micro fillers in high density polyethylene based radiation shielding material.


Kerntechnik ◽  
2021 ◽  
Vol 86 (1) ◽  
pp. 64-69
Author(s):  
N. U. Kockal ◽  
A. Cesur ◽  
S. F. Ozmen

Abstract In this study the radiation shielding properties of mortar samples were investigated. The samples were created by replacing heavyweight particles of iron, steel and chromium waste by calcareous sand in different volume percentages. Additionally, the effects of the physical properties of particles and samples on shielding properties is also discussed. In the scope of this work, the radiation shielding properties of mortar samples were measured by determining the values of mass attenuation coefficients by means of an experimental setup consisting of 133Ba, 137Cs and 60Co standard point sources and high purity germanium (HPGe) detector. It’s concluded that the highest mass attenuation coefficient values among the heavy particles were achieved by chromium particles. However, all the high-density particles used in the study improved the radiation shielding properties of the mortars considerably compared to ordinary mortars.


2021 ◽  
Vol 11 (21) ◽  
pp. 10168
Author(s):  
Ghada ALMisned ◽  
Huseyin O. Tekin ◽  
Hesham M. H. Zakaly ◽  
Shams A. M. Issa ◽  
Gokhan Kilic ◽  
...  

Characteristics of tellurite-tungstate-antimonate glasses containing heavy metal oxide were investigated in detail using two methods: the MCNPX Monte Carlo code and the Phy-X/PSD platform. The influence of Sm2O3, translocating with TeO2 at ratios of 0.2, 0.5, 0.8, 1, and 1.5 mol% on radiation shielding properties of glasses, was set forth with five glass structures determined according to the (75-x)TeO2-15Sb2O3-10WO3-xSm2O3 glass composition. Densities of the glasses were prepared by doping a low ratio of Sm2O3 that varied between 5.834 and 5.898 g/cm3. Sample densities, which have an important role in determining radiation shielding character, increased depending on the increase in Sm2O3 concentration. Effective removal cross-section (∑R) values against fast neutrons, as well as linear and mass attenuation coefficients, half-value layer, mean free path, variation of effective atomic number against photon energy, exposure, and energy built-up factors, were simulated with the help of these two methods. As a result of these estimates, it can be concluded that values obtained using both methods are consistent with each other. From the obtained values, it can be concluded that the SM1.5 sample containing 1.5 mol% would have the most efficient role in radiation shielding. An increase of Sm2O3 resulted in a significant increase in linear and mass attenuation coefficients and effective removal cross-section values belonging to fast neutrons and, in addition, resulted in a decrease in the half value layer. Doping HMO glasses with Sm2O3 was observed to contribute directly to the development of radiation shielding properties of the glass.


2019 ◽  
Vol 107 (4) ◽  
pp. 339-348 ◽  
Author(s):  
Mohammed I. Sayyed ◽  
Ferdi Akman ◽  
Mustafa Recep Kaçal

Abstract Recently, technologists try to develop novel gamma radiation shielding materials instead of traditional materials such as lead and concrete with improved performance in gamma radiation shielding in medical applications and nuclear reactors. For this purpose, alloys such as stainless steel (SS) and carbon steel (CS) attracted much attention, these days. Preliminary results on such alloys have shown better attenuation of γ rays as compared to traditional shielding materials. This work aimed to conduct research on different alloy samples to evaluate their radiation attenuation efficiency and their suitability for radiation shielding when utilized in nuclear facilities. The mass attenuation coefficients for eight alloy samples were measured at different photon energies ranging from 80.997 to 1332.501 keV using transmission geometry. From the mass attenuation coefficients, different photon attenuation parameters such as half value layer, mean free path, effective atomic number, and radiation protection efficiency were evaluated. In addition, the equivalent atomic number and the exposure buildup factor were calculated using G-P fitting method for photon energy ranging from 0.015 MeV to 15 MeV at different penetration depth. The results showed that the Zeff values remain almost constant for all samples except W72/Cu28 in which the Zeff for this sample tends to decrease with the energy. The lowest value of half value layer is found for the alloy sample Ta97.5/W2.5 and the highest value is found for the alloy sample In50/Sn50. The Ta97.5/W2.5, Ta90/W10, Ta95/W5 samples demonstrated good radiation attenuation properties.


2021 ◽  
Vol 11 (1) ◽  
Author(s):  
Ahmed M. El-Khatib ◽  
Mahmoud I. Abbas ◽  
Mohamed Abd Elzaher ◽  
Mohamed S. Badawi ◽  
Mahmoud T. Alabsy ◽  
...  

An amendment to this paper has been published and can be accessed via a link at the top of the paper.


2019 ◽  
Vol 34 (4) ◽  
pp. 342-352 ◽  
Author(s):  
Zainab Alsayed ◽  
Mohamed Badawi ◽  
Ramadan Awad ◽  
Abouzeid Thabet ◽  
Ahmed El-Khatib

The extensive utilization of radiation is rapidly developing worldwide involving abundant fields like medical, industrial, research, and nuclear facilities. This makes the need for studying radiation shielding materials and their properties more urgent than ever. In the present study, bulk and nano ZnO were mixed by the same ratio each time (10, 20, 30, and 40 wt.%), with high-density polyethylene as a polymer matrix and characterized by X-ray diffraction. The results confirmed the good dispersion of bulk and nano ZnO particles within the polymer matrix. The prepared composite samples were used in different thicknesses as gamma ray shielding materials, and the heaviness was calculated and compared to lead. Using HPGe detector at specific energies (59.53, 356.01, 661.66, 1173.33, and 1332.50 keV) for different radioactive point sources (241Am, 133Ba, 137Cs, and 60Co), the mass attenuation coefficient for the samples was measured experimentally. Depending upon the obtained values, the linear attenuation coefficient, half-value layer, tenth value layer, heaviness and relaxation length were estimated. Using the XCOM database, the values of linear attenuation coefficient, mass attenuation coefficient, and other parameters were calculated theoretically for the bulk ZnO blended with high-density polyethylene. The obtained results were compared to the experimental values for nano and bulk ZnO blended with high density polyethylene. The radiation shielding behavior of nano ZnO blended with high density polyethylene was found to be more promising and efficient for radiation protection against gamma ray.


Kerntechnik ◽  
2017 ◽  
Vol 82 (3) ◽  
pp. 339-343 ◽  
Author(s):  
S. M. Vahabi ◽  
M. Bahreinipour ◽  
M. Shamsaie-Zafarghandi

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