Calculation of Linear Attenuation Coefficients of Algerian Silica Sand (ASS)

2020 ◽  
Vol 12 (10) ◽  
pp. 1300-1302
Author(s):  
Iskender Akkurt ◽  
Sabiha Anas Boussaa ◽  
Kadir Gunoglu
Keyword(s):  
Construction Materials ◽  
Computer Code ◽  
Radiation Shielding ◽  
Silica Sand ◽  
Attenuation Coefficients ◽  
Decorative Material

Radiation is an important phoneme and thus radiation shielding is one of the most popular subjects for researchers. Sand is the main materials to produce besides many things also construction materials. It may also be used as a decorative material and therefore it is important to know its radiation shielding parameters. In this study, linear attenuation coefficients of Algerian Silica Sand (ASS) were calculated using computer code of XCOM for 1 keV—100 GeV gamma energies.

Determination of Photon Attenuation Coefficients of Steel Doped Barite Plasters

2019 ◽  
Vol 11 (11) ◽  
pp. 1075-1078
Author(s):  
İskender Akkurt ◽  
Kadir Günoğlu ◽  
Şemsettin Kılınçarslan
Keyword(s):  
Experimental Measurement ◽  
Computer Code ◽  
Gamma Spectrometer ◽  
Attenuation Coefficients ◽  
Photon Attenuation ◽  
Decorative Material ◽  
Radioactive Sources

The plaster is used as a flattening of the interior and exterior surfaces of the buildings and as decorative material. In this study, photon attenuation coefficients of barite plaster containing steel were measured. The measurements performed at 511, 835 and 1275 keV which are obtained from 22Na and 54Mn radioactive sources, using a gamma spectrometer that contains a NaI(Tl) detector and MCA. The measured results were compared with the calculation obtained using computer code of XCOM for 1 keV–1 GeV gamma energies. Also, half value layer (HVL) and tenth value layer (TVL) were calculated using the results obtained from the experimental measurement.

scholarly journals The Role of La2O3 in Enhancement the Radiation Shielding Efficiency of the Tellurite Glasses: Monte-Carlo Simulation and Theoretical Study

Materials ◽  
2021 ◽  
Vol 14 (14) ◽  
pp. 3913
Author(s):  
Aljawhara H. Almuqrin ◽  
Mohamed Hanfi ◽  
K. G. Mahmoud ◽  
M. I. Sayyed ◽  
Hanan Al-Ghamdi ◽  
...  
Keyword(s):  
Monte Carlo Simulation ◽  
Theoretical Study ◽  
Radiation Shielding ◽  
Photon Flux ◽  
Transmission Factor ◽  
Tellurite Glasses ◽  
Attenuation Coefficients ◽  
Binary Glass ◽  
Buildup Factors

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.

scholarly journals Technological and organizational problems in the construction of the radiation shielding concrete and suggestions to solve: A case study

2021 ◽  
Vol 11 (1) ◽  
pp. 1122-1129
Author(s):  
Aleksandra Radziejowska ◽  
Joanna Sagan ◽  
Anna Sobotka
Keyword(s):  
Occupational Safety ◽  
Construction Materials ◽  
Radiation Shielding ◽  
Health Administration ◽  
Supply Logistics ◽  
Problems And Solutions ◽  
Analysis Of Alternatives ◽  
Heavyweight Concrete ◽  
The University

Abstract Protection of buildings against the pernicious radiation types can be achieved by simultaneous structural and shielding parameters. Those shields are mainly made of heavyweight concrete, which causes many serious problems in the areas of technology, supply logistics, financial supply, Occupational Safety & Health Administration, and substitutions of structural and material solutions. This work presents a case study of the construction of the university building with rooms requiring protection against malicious radiations. Apart from that, it presents the problems and solutions that occurred during the construction from the perspective of the works contractor. This study was also expanded to include the analysis of alternatives for construction-materials. The obtained results were used to develop a generalized scheme, which will be helpful in the preparation and implementation of any facilities requiring fixed radiation shields.

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 Radiation Shielding Properties Comparison of Pb-Based Silicate, Borate, and Phosphate Glass Matrices

2014 ◽  
Vol 2014 ◽  
pp. 1-5 ◽  
Author(s):  
Suwimon Ruengsri
Keyword(s):  
Phosphate Glass ◽  
Theoretical Calculations ◽  
Visible Region ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Attenuation Coefficients ◽  
Total Attenuation ◽  
Shielding Properties ◽  
Glass Matrices ◽  
Mass Attenuation

Theoretical calculations of mass attenuation coefficients, partial interactions, atomic cross-section, and effective atomic numbers of PbO-based silicate, borate, and phosphate glass systems have been investigated at 662 keV. PbO-based silicate glass has been found with the highest total mass attenuation coefficient and then phosphate and borate glasses, respectively. Compton scattering has been the dominate interaction contributed to the different total attenuation coefficients in each of the glass matrices. The silicate and phosphate glass systems are more appropriate choices as lead-based radiation shielding glass than the borate glass system. Moreover, comparison of results has shown that the glasses possess better shielding properties than standard shielding concretes, suggesting a smaller size requirement in addition to transparency in the visible region.

scholarly journals Radiation Shielding Properties Prediction of Barite used as Small Aggregate in Mortar

2020 ◽  
Vol 10 (6) ◽  
pp. 6469-6475
Author(s):  
H. Q. Vu ◽  
V. H. Tran ◽  
P. T. Nguyen ◽  
N. T. H. Le ◽  
M. T. Le
Keyword(s):  
Radiation Resistance ◽  
Construction Materials ◽  
Cost Effective ◽  
Radiation Shielding ◽  
Nuclear Industry ◽  
Barium Compounds ◽  
Long Time ◽  
Radiation Resistant ◽  
Shielding Properties ◽  
Materials Used

Construction materials used in the nuclear industry used to be mainly heavy materials, including lead plates, radiation-resistant heavy concrete, etc. However, these materials are either toxic after a long time of use (lead) or difficult to construct (radiation-resistant heavy concrete) and their cost is rather high. Therefore, there is a need for the manufacturing of a new kind of material with good radiation resistance, which is light, easy to use, and costs less. Barium is less toxic and more cost-effective than lead. Due to the importance of barium compounds in radiation shielding, the study of gamma radiation interactions within these compounds becomes essential, so the most important part of such a study is the experimental one, which shows the effect of the barite powder in the radiation resistance of the mortar. The research results show that the higher the thickness and percentage of barite powder, the higher is the radiation resistance.

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 Fabrication of Novel (Biopolymer Blend-Lead Oxide Nanoparticles) Nanocomposites: Structural and Optical Properties for Low-Cost Nuclear Radiation Shielding

2019 ◽  
Vol 64 (2) ◽  
pp. 157 ◽  
Author(s):  
A. Hashim ◽  
K.H.H. Al-Attiyah ◽  
S. F. Obaid
Keyword(s):  
Optical Properties ◽  
Lead Oxide ◽  
Optical Constants ◽  
Low Cost ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Oxide Nanoparticles ◽  
Energy Band Gap ◽  
Structural And Optical Properties ◽  
Attenuation Coefficients

Low-cost polymer nanocomposites prepared for the nuclear radiation shielding have highly linear attenuation coefficients, light weight, and elastic, good mechanical, optical, and dielectric properties. The carboxymethyl cellulose (CMC)–polyvinyl pyrrolidone (PVP) polymeric blend is prepared with concentrations: 60 wt.% CMC and 40 wt.% PVP. The lead oxide nanoparticles are added to the CMC–PVP blend with different concentrations: 0, 2, 4, 6, and 8 wt.%. The structural and optical properties of (CMC–PVP–PbO2) nanocomposites are studied. The results show that the absorbance of the (CMC–PVP) blend increases and the energy band gap decreases, as the concentration of PbO2 nanoparticles increases. The optical constants of the (CMC–PVP) blend increase with the concentration of lead oxide nanoparticles. The (CMC–PVP–PbO2) nanocomposites have highly linear attenuation coefficients for gamma radiation.

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 protective characteristics of some selected tungstates

2019 ◽  
Vol 107 (4) ◽  
pp. 349-357 ◽  
Author(s):  
Mohammed I. Sayyed ◽  
Gandham Lakshminarayana ◽  
Mustafa R. Kaçal ◽  
Ferdi Akman
Keyword(s):  
Tungsten Oxide ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Attenuation Coefficients ◽  
Γ Radiation ◽  
Protection Efficiency ◽  
Cadmium Tungstate ◽  
Maximum Value ◽  
Lithium Tungstate ◽  
Shielding Material

Abstract The mass attenuation coefficients (μ/ρ) of calcium tungstate, ammonium tungsten oxide, bismuth tungsten oxide, lithium tungstate, cadmium tungstate, magnesium tungstate, strontium tungsten oxide and sodium dodecatungstophosphate hydrate were measured at 14 photon energies in the energy range of 81–1333 keV using 22Na, 54Mn, 57Co, 60Co, 133Ba and 137Cs radioactive sources. The measured μ/ρ values were compared with those obtained from WinXCOM program and the differences between the experimental and theoretical values were very small. The bismuth tungsten oxide has the highest μ/ρ among the present samples in the studied energy region. From the μ/ρ values, we calculated the half value layer, tenth value layer and mean free path, and the results showed that ammonium tungsten oxide (which has the lowest density) and bismuth tungsten oxide (which has the highest density) possess the highest and lowest values of these three parameters, respectively. Additionally, from the incident and transmitted photon intensities, we calculated the radiation protection efficiency (RPE). The bismuth tungsten oxide was found to have RPE 98.53 % at 81 keV, which has the maximum value among the present samples and this suggested that bismuth tungsten oxide is the best to be chosen as the γ radiation shielding material candidate among the selected samples.

Sign in / Sign up

Export Citation Format

Share Document