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).

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.

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 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 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.

scholarly journals Evaluation of Gamma Radiation Attenuation Characteristics of Different Type Shielding Materials used in Nuclear Medicine Services

2019 ◽  
Vol 21 (2) ◽  
pp. 108-114
Author(s):  
Abdus Sattar Mollah
Keyword(s):  
Nuclear Medicine ◽  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Lead Glass ◽  
Storage Container ◽  
Absorbing Materials

Gamma-ray radiation shielding properties such as linear attenuation coefficient (m), mass attenuation coefficient (m/r), half- value thickness (HVT), tenth value thickness (TVL) and mean free path (MFP) were calculated for different types of radiation absorbing materials such as Concrete, Aluminum, Iron, Copper, Lead, Lead-glass and Tungsten. These materials are being widely used as radiation shielding materials in different areas of nuclear medicine facilities for different purposes. The XCOM and in-house developed computer program were used to calculate the above mentioned parameters for gamma-ray energies of 100 keV, 200 keV and 511 keV. The gamma-ray energy range used in nuclear medicine is between 100 keV and 511 keV. Results show that attenuation coefficient decreases with increase of gamma-ray energy, and attenuation coefficient increases with increase of density and shows significant variation for different materials. Linear attenuation coefficient depends on the energy of incident gamma-rays and the nature of the absorbing materials. These gamma-ray attenuation parameters of different absorbing materials can be used for proper shielding design of syringe shield, isotope storage container, isotope transport container, personnel protective shield barrier, radioactive waste storage facility etc.  in nuclear medicine services. Bangladesh J. Nuclear Med. 21(2): 108-114, July 2018  

The Effect of Iron Fillings Waste Contents on the Attenuation Level of Anti-Radiation Shielding Concrete

2013 ◽  
Vol 795 ◽  
pp. 195-200
Author(s):  
Ali Basheer Azeez ◽  
Kahtan S. Mohammed ◽  
Mohd Mustafa Al Bakri Abdullah ◽  
Azmi B. Rahmat
Keyword(s):  
Energy Levels ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Gamma Spectrometer ◽  
Radioactive Elements ◽  
Attenuation Coefficients ◽  
Radiation Attenuation ◽  
Attenuation Level ◽  
The Mean

Shielding concretes of different iron filling contents were assessed for their anti radiation attenuation properties. The measurements have been performed by using gamma spectrometer of NaI (Tl) detector, the sources were Cs137 and Co60 radioactive elements with photon energies of o.662 MeV, for Cs137 and the two 1.17MeV, 1.33 MeV energy levels for the Co60. Likewise, the mean free path of the tested samples was obtained as well. From the measurement of the linear attenuation coefficients for these different shielding materials, it was found that as the iron filings within the concrete are increased the linear attenuation coefficient is increased also. It can be concluded from this work that the Iron filings content in concrete is very effective in augmentation of the anti-radiation shielding capability. It can be used as shelters material for secure storing of the nuclear wastes.

scholarly journals Investigation of Gamma and Neutron Shielding Parameters for Borate Glasses Containing NiO and PbO

2014 ◽  
Vol 2014 ◽  
pp. 1-7 ◽  
Author(s):  
Vishwanath P. Singh ◽  
N. M. Badiger
Keyword(s):  
Photon Energy ◽  
Cross Sections ◽  
Borate Glass ◽  
Gamma Ray ◽  
Radiation Shielding ◽  
Interaction Parameters ◽  
Neutron Shielding ◽  
Attenuation Coefficients ◽  
Effective Electron ◽  
Weight Percentage

The mass attenuation coefficients, μ/ρ, half-value layer, HVL, tenth-value layer, TVL, effective atomic numbers, ZPIeff, and effective electron densities, Ne,eff, of borate glass sample systems of (100-x-y) Na2B4O7 : xPbO : yNiO (where x and y=0, 2, 4, 6, 8, and 10 weight percentage) containing PbO and NiO, with potential gamma ray and neutron shielding applications, have been investigated. The gamma ray interaction parameters, μ/ρ, HVL, TVL, ZPIeff, and Ne,eff, were computed for photon energy range 1 keV–100 GeV. The macroscopic fast neutron removal cross-sections (ΣR) have also been calculated. Appreciable variations were noted for all the interaction parameters by varying the photon energy and the chemical composition of the glass samples. The better shielding properties of borate glass samples containing PbO were found. These results indicated that borate glass samples are a good radiation shielding material.

scholarly journals CALCULATION OF GAMMA-RAY ATTENUATION PARAMETERS FOR ALUMINIUM, IRON, ZIRCONIUM, AND TUNGSTEN

2020 ◽  
pp. 60-65
Author(s):  
Hiwa Mohammad Qadr
Keyword(s):  
Gamma Radiation ◽  
Free Path ◽  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Gamma Ray Attenuation ◽  
And Tungsten

The purpose of this study was to determine the linear attenuation coefficient, the mass attenuation coefficient, Half Value Layer. Tenth Value Layer and Mean Free Path for four different shielding materials such as aluminium, iron, zirconium and tungsten. By using the gamma-radiation energies emitted from 152Eu, 22Na, 137Cs, and 60Co radioactive sources. For this purpose, the attenuation measurements were performed using NaI(TI) detector. Calculated values of all parameters of the all shielding materials were compared with each other. The results of all presented parameters show that, tungsten has the best radiation shielding compared to other shielding materials. Then, the obtained parameters were compared with the theoretical values.

Radiation Shielding Characteristics of Concretes Incorporates Different Particle Sizes of Various Waste Materials

2014 ◽  
Vol 925 ◽  
pp. 190-194 ◽  
Author(s):  
Ali Basheer Azeez ◽  
Kahtan S. Mohammed ◽  
A.M. Mustafa Al Bakri ◽  
Hana Ihsan Hasan ◽  
Omar A. Abdulkareem
Keyword(s):  
Particle Size ◽  
Particulate Matter ◽  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Filler Particle ◽  
Steel Slag ◽  
Radiation Shielding ◽  
Shielding Effect ◽  
Linear Attenuation Coefficient ◽  
Steel Balls

In this study, the dependence of gamma-ray absorption coefficient on the particulate matter sizes of steel slag, iron fillings and steel balls incorporated concrete were examined. The contents of these fillers in concrete mix was kept constant to 35 wt. %. Only the filler particle size was varied during the tests. The particle size ranged from 0.2mm to 1mm for steel slags and the iron fillings and from 2.5mm to 10mm for the steel balls.The concrete samples were assessed for their anti-radiation attenuation coefficient properties. The attenuation measurements were performed using gamma spectrometer of NaI (Tl) detector. The utilized radiation source was Cs137 radioactive element with photon energy of o.662 MeV. The results showed that gamma-ray attenuation coefficient was inversely proportional to the filler particulate matter size. Likewise the mean free paths for the tested samples were obtained. Maximum linear attenuation coefficient of 1.102±0.263cm-1 was attained for the iron filling.The iron balls and the steel slags showed much inferior values. The concrete incorporates iron filings afforded the best shielding effect. The density, microstructure, homogeneity and particulate distribution of the concrete samples were examined and evaluated using different metallographic, microscopic and measurement facilities.

scholarly journals Study of some γ-ray attenuation parameters for new shielding materials composed of nano ZnO blended with high density polyethylene

2019 ◽  
Vol 34 (4) ◽  
pp. 342-352 ◽  
Author(s):  
Zainab Alsayed ◽  
Mohamed Badawi ◽  
Ramadan Awad ◽  
Abouzeid Thabet ◽  
Ahmed El-Khatib
Keyword(s):  
Attenuation Coefficient ◽  
Polymer Matrix ◽  
High Density Polyethylene ◽  
Gamma Ray ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
High Density ◽  
Linear Attenuation Coefficient ◽  
Nano Zno ◽  
Mass Attenuation

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.

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