scholarly journals Shielding Properties of Some Marble Types: A Comprehensive Study of Experimental and XCOM Results

Materials ◽  
2021 ◽  
Vol 14 (15) ◽  
pp. 4194
Author(s):  
Mohamed Elsafi ◽  
Mohamed A. El-Nahal ◽  
M. F. Alrashedi ◽  
O. I. Olarinoye ◽  
M. I. Sayyed ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Fast Neutrons ◽  
Linear Attenuation Coefficient ◽  
Protective Shield ◽  
Removal Cross Section ◽  
The Mean ◽  
Good Agreement

In this work, some marble types were collected from Egypt, and their shielding characteristics were estimated. Their rigidity, in addition to their elegant shape, led us to consider their use as a protective shield, in addition to making the workplace more beautiful. The mass attenuation coefficient (μ/ρ) was calculated for three types of marble (Breshia, Galala, and Trista) experimentally, using a narrow gamma ray source and sodium iodide scintillation detector (NaI). The results obtained were compared with the XCOM program and indicated a very good agreement between the two methods. The linear attenuation coefficient (μ) was evaluated to calculate the half and tenth value layers. The maximum value of 1.055, 1.041, and 1.024 cm−1 was obtained for Breshia, Galala, and Trista, respectively, at 0.06 MeV. The mean free path for studying the materials was compared with other shielding materials and showed good results at different energy scales. The energy absorption (EABF) and exposure buildup factors (EBF) were determined at different mean free paths. The fast neutron removal cross section ∑R was calculated and expresses the ability of the marbles to slow down fast neutrons through multiple scattering. This is the ability of the marbles to shield fast neutrons.

scholarly journals Enhancement of the Shielding Capability of Soda–Lime Glasses with Sb2O3 Dopant: A Potential Material for Radiation Safety in Nuclear Installations

2020 ◽  
Vol 11 (1) ◽  
pp. 326
Author(s):  
M.I. Sayyed ◽  
K.A. Mahmoud ◽  
O.L. Tashlykov ◽  
Mayeen Uddin Khandaker ◽  
M.R.I. Faruque
Keyword(s):  
Attenuation Coefficient ◽  
Elastic Moduli ◽  
Gamma Ray ◽  
Radiation Safety ◽  
Soda Lime ◽  
Mass Attenuation Coefficient ◽  
Transmission Factor ◽  
Linear Attenuation Coefficient ◽  
Neutron Shielding ◽  
Removal Cross Section

Elastic moduli were theoretically computed using the Makishima–Mackenzie model for SiO2–Na2O–CaO glasses doped with Sb2O3 contents. The calculated elastic moduli (Young’s, bulk, shear, and longitudinal modulus) were observed to increase with an increase in the Sb2O3 contents. The microhardness showed an increase, while Poisson’s ratio decreased with the rise of the Sb2O3 contents. In addition, gamma-ray and neutron shielding parameters were evaluated for the investigated glasses. The linear attenuation coefficient (LAC) was simulated using the Monte Carlo N-particle transport code (MCNP-5). Other parameters, such as the mass attenuation coefficient (MAC), transmission factor (TF), and half-value layer, were calculated based on the simulated LAC. The addition of Sb2O3 content was observed to enhance the investigated glasses’ shielding parameters, where the highest LAC was achieved for the SCNSb10 glass with 10 mol% Sb2O3 and decreased from 0.441 to 0.154 cm−1 at gamma energies between 0.248 and 1.406 MeV. Furthermore, the fast neutron effective removal cross-section (∑R) was computed theoretically. The calculated results showed that the highest ∑R was equal to 0.0341 cm2g−1 and was obtained for the SCNSb0 glass, which had no Sb2O3 content, while the lowest ∑R was equal to 0.0286 cm2 g−1 for the SCNSb10 glass sample. The present work was carried out to examine the advantages of the soda–lime glasses with different Sb2O3 contents in several photon shielding applications, especially for radiation safety in nuclear installations.

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  

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.

Study on gamma ray shielding performance of concretes doped with natural sepiolite mineral

2018 ◽  
Vol 106 (12) ◽  
pp. 1009-1016 ◽  
Author(s):  
Osman Agar
Keyword(s):  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Morphological Structure ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Linear Attenuation Coefficient ◽  
Attenuation Coefficients ◽  
X Ray ◽  
Edx Analyses ◽  
Gamma Ray Attenuation

Abstract Gamma ray attenuation coefficients for various concrete types containing natural sepiolite mineral and B4C have been experimentally investigated at different gamma energies. In order to obtain the gamma rays, the four radioactive point-isotropic sources 133Ba, 137Cs, 60Co and 22Na which energies ranged from 80.9 to 1332.5 keV have been utilized. The measurements have been carried out by using HPGe detector and MCA equipped with a personal computer. The morphological structure and elemental compositions of the concretes have been measured with scanning electron microscope (SEM) and energy-dispersive X-ray (EDX) analyses. Linear attenuation coefficient (μ), mass attenuation coefficient (μm), half value layer (HVL) and mean free path (MFP) have been calculated for all concretes. The obtained results have been compared to the other materials such as Pb and Al.

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.

scholarly journals Calculate the Attenuation of X-ray radiation for low density polyethylene composites with oyster shells powder extracted from the Caspian Sea in Iran: حساب الحجب الإشعاعي للأشعة السينية لبوليمر البولي اثيلين واطئ الكثافة والمطعم بمسحوق قشور المحار المستخرج من بحر قزوين

2019 ◽  
Vol 3 (1) ◽  
Author(s):  
Ahmed Jassim Mohammed, Riad Manadi Ramadan, Raed Muslim Shab
Keyword(s):  
Free Path ◽  
Attenuation Coefficient ◽  
Caspian Sea ◽  
Mean Free Path ◽  
Low Density Polyethylene ◽  
Linear Attenuation Coefficient ◽  
Low Density ◽  
The Caspian Sea ◽  
X Ray ◽  
The Mean

In this research, Calculation the Attenuation of X-ray radiation for low density polyethylene composites with oyster shells powder (extracted from the Caspian Sea in Iran), low density polyethylene production in the form of powder by the State Company for Petrochemical Industries (Basra-Iraq), the range of the added of oyster shells powder (extracted from the Caspian sea in Iran) has the values (0%, 2.5%, 5%, 10%, 15%, 20%, and 25%) for low density polyethylene weight and the added oyster shells powder with the particular size (≤ 250 μm). were investigated through several variables, such as, linear attenuation coefficient(μ) and mean free path(λ). The obtained results were appeared that the added oyster to reduce the spaces between the polymer chains, which reflects the high ability of the polymer as (10%-20%), and this increase will give further property that increase the attenuation x-ray of the prepared specimens. Where the practical study and the beam of intensity of energy (30 kv) and)VG.M = 600 voit(. The results showed that when increasing filler content, the total linear attenuation coefficient increases while the mean free path decreases. The mean free path (λ) at (2.5%) is (2.1 cm (, while at (20%) is (0.40 cm). The value of the linear attenuation coefficient (μ) at (20%) is)2.44 cm-1(, while at (2.5%) is) 0.49 cm-1(.

Improvement of Gamma Radiation Shielding Features for Fluorophosphate Glasses Doping with Sm2O3 (PZBKNA)

2020 ◽  
Vol 15 (11) ◽  
pp. 1374-1380
Author(s):  
H. Almohiy ◽  
M. Saad ◽  
Y. M. AbouDeif ◽  
Iwona Grelowska ◽  
M. Reben ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Cross Sections ◽  
Radiation Safety ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Ordinary Concrete ◽  
Materials Used

This research reported on the radiation safety characteristics of doped fluorophosphate glasses with heavy rare earth lanthanide (Sm2O3) in the composition 40P2O5/30ZnO/20BaF2/3.8K2TeO3/1.2Al2O3/5.0Nb2O5/30000 ppm Sm2O3 and 40P2O5/30ZnO/20BaF2/3.8K2TeO3/1.2Al2O3/5.0Nb2O5/40000 ppm Sm2O3 in mol%. The parameters for shielding like that mass attenuation coefficient, MAC, linear attenuation coefficient, LAC, tenth value layers, TVL, half-value layers, HVL, effective atomic number, (Zeff), mean free path, MFP, electron density, Neff, electronic cross-sections, ECS, and total atomic cross-sections, ACS, were calculated between 0.015 and 15 MB of preparation glasses. The protection parameters of the current glasses are good in comparison to industrial materials used for nuclear shieldings, such as glass RS 253, ordinary concrete (OC), hematite serpenite (HS), or basalt magnet (BM). From the above mention results, the prepared glasses can be used as radiation safety materials.

scholarly journals Structural, and Radiation Shielding Simulation of B2O3-SiO2-LiF- ZnO-TiO2 Glasses

2021 ◽  
Author(s):  
Kh. S. Shaaban
Keyword(s):  
Attenuation Coefficient ◽  
Effective Atomic Number ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
The Other ◽  
Linear Attenuation Coefficient ◽  
Gamma Photon ◽  
Density Relationship ◽  
Ft Ir ◽  
Good Agreement

Abstract Quaternary glasses with a 59B2O3-29SiO2-2LiF-(\(10-x\)) ZnO-\(x\)TiO2 composition using the melt-quench techniques were prepared. XRD examined the nature of prepared glasses. The FT-IR spectra was studied for the changes in the structure of these glasses. While the density is increased, the molar volume of the glass system is reduced. The velocities and elastic modulus of these glasses were experimentally and theoretically based on the Makishima-Mackenzie model evaluated. Besides, for the studied glasses, the radiation shielding efficiency was investigated by Phy-X/PSD and XCOM software. These glasses were found to have an abnormal attenuation, structural, and density relationship. The mass attenuation coefficient (µ/ρ), linear attenuation coefficient (LAC), half-value layer (HVL), tenth value layer (TVL), and effective atomic number (Zeff), of glasses, have been designed to simulate for gamma photon energies between 0.015 and 15 MeV. MAC values calculated using Phy-X/PSD and XCOM were compared and was observed in good agreement with the other.

scholarly journals Investigation of Gama Ray Shielding Properties of the (Al:Si) and (Al+Na):Si doped International Simple Glasses (ISG) using Phy-X/PSD and SRIM Software’s

2021 ◽  
Author(s):  
Miraç KAMIŞLIOĞLU
Keyword(s):  
Radiation Protection ◽  
Attenuation Coefficient ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Atomic Fraction ◽  
Gamma Photon ◽  
Si Doped ◽  
The Mean ◽  
Shielding Properties

Abstract In this investigation, the gamma photon shielding properties for the (Al:Si) and (Al + Na):Si dopped ISG glasses were investigated by using Photon Shielding and Dosimetry (Phy-X / PSD) software for the selected energy range. The obtained results showed that the highest MAC value belong to ISG-A00N glass. It was seen that the MAC values which were examined at all energies changed in harmony with WinXCom. Substituting an atomic fraction of (Al:Si) with (Al + Na):Si resulted in a reduction of the total atomic cross-section of the glass, which lowered the mass attenuation coefficient (MAC). In this study, computations were made for glasses with SiO2, Al2O3, B2O3, Na2O, CaO and ZrO2 content given with ISG-C, ISG-A00, ISG-A12, ISG-A22, ISG-A00N, ISG-A11N, ISG-A18N and ISG-A23N codes. MAC, LAC, HVL, TVL, Zeff, Neff, Ceff Zeq, EBF, EABF and FNRCS calculations were applied to assess the radiation protection parameters by using Phy-X/PSD software. In addition, MSP and PR values were calculated by using the SRIM code. In fact, each obtained parameter provides us very important information on radiation protection, and these methods are frequently used in the literature. ISG-A00N glasses were observed to have the highest attenuation coefficient. Thus, the MAC value gradually decreased as the Al, Na and Si contents increased. Likewise, the HVL, TVL and MFP values changed coherent with this. Moreover, Zeff and Neff values were seen in the ISG-A00N sample to take the maximum values to each other inversely. The most effective glass sample was seen as ISG-A00N glass at the mean free path penetration power of MSP and PR values. When all the results were evaluated, ISG-A00N glass which has the highest Si and Ca contents and density was found to be the glass with the best radiation shielding feature. It is also noteworthy that this glass does not contain any Al component. As the results of the investigation, it was found out that a very small doped of the Si increases the radiation shielding feature on the glass. It was seen that the ISG-A23N had the lowest ∑R value. The obtained results revealed that the ISG-A00N > ISG-A00 > ISG-C > ISG-A12 > ISG-A11N > ISG-A22 > ISG-A18N > ISG-A23N samples, in ascending order that attenuators for low energy radiations.

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