scholarly journals Gamma Irradiation and the Radiation Shielding Characteristics: For the Lead Oxide Doped the Crosslinked Polystyrene-b-Polyethyleneglycol Block Copolymers and the Polystyrene-b-Polyethyleneglycol-Boron Nitride Nanocomposites

Polymers ◽  
2021 ◽  
Vol 13 (19) ◽  
pp. 3246
Author(s):  
Zehra Merve Cinan ◽  
Burcu Erol ◽  
Taylan Baskan ◽  
Saliha Mutlu ◽  
Sevil Savaskan Yilmaz ◽  
...  
Keyword(s):  
Block Copolymers ◽  
Boron Nitride ◽  
Gamma Irradiation ◽  
Gamma Rays ◽  
Lead Oxide ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Polymer Mixture ◽  
Crosslinked Polystyrene

This work aimed to research the efficiency of gamma irradiation and shielding characteristics on the lead oxide (PbO) doped the crosslinked polystyrene-b-polyethyleneglycol (PS-b-PEG) block copolymers and polystyrene-b-polyethyleneglycol-boron nitride (PS-b-PEG-BN) nanocomposites materials. The crosslinked PS-b-PEG block copolymers and PS-b-PEG-BN nanocomposites mixed with different percentage rates of PbO were used to research gamma-ray shielding characteristics. The synthesis of the copolymer was done by emulsion polymerization methods. The characterization and morphological analyses of irradiated samples were explored handling with the Nuclear Magnetic Resonance (NMR), Fourier Transform Infrared Spectroscopy (FTIR), Gel Permeation Chromatography (GPC), Thermogravimetric Analysis (TGA), and Scanning Electron Microscope (SEM) methods. The gamma-rays that were emitted from the E 152u source were observed with a High Purity Germanium (HPGe) detector system and examined with a GammaVision computer program. Our samples, including the different percentage rates of the PS-b-PEG (1000, 1500, 10,000), BN, and PbO, were irradiated in various gamma-ray photon energy regions (from 121.78 keV to 1408.01 keV). Then, Linear-Mass Attenuation Coefficients (LACs-MACs), Half-Tenth Value Layer (HVL), Mean Free Path (MFP), and Radiation Protection Efficiency (RPE) values of the samples were calculated. Via crosschecking the acquired data from samples with and without PbO and BN, it was observed that, if the different percentage rates by weight nano-powder of PbO and BN are added in the polymer mixture, it can be used as a convenient shielding material against gamma rays.

New high temperature resistant heavy concretes for fast neutron and gamma radiation shielding

2019 ◽  
Vol 107 (4) ◽  
pp. 359-367 ◽  
Author(s):  
Bünyamin Aygün ◽  
Erdem Şakar ◽  
Turgay Korkut ◽  
Mohammed Ibrahim Sayyed ◽  
Abdülhalik Karabulut
Keyword(s):  
High Temperature ◽  
Cross Sections ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Normal Weight ◽  
Radiation Shielding ◽  
Equivalent Dose Rate ◽  
Normal Weight Concrete ◽  
Geant4 Code

Abstract In the present work, we developed three new high temperature resistant heavy concretes as novel radiation shielding materials. For this purpose, chrome ore (FeCr2O4), hematite (Fe2O3), titanium oxide (TiO2), aluminum oxide (Al2O3), limonite [FeO (OH) nH2O], siderite (FeCO3), barite (BaSO4), nickel oxide (NiO) materials and alumina cement were used. Mass combination ratios of components and total macroscopic cross sections (scattering, absorption, capture, fission) of the samples were calculated by using GEANT4 code. The resistances of the prepared samples were evaluated in terms of compression strength after exposure at the 1000 °C temperature. Neutron equivalent dose rate measurements were carried out by using 4.5 MeV 241Am-Be neutron source and BF3 detector. All results were compared with normal weight concrete and paraffin. The results of neutron dose indicate that neutron absorption ability of the new heavy concretes is higher than normal weight concrete and paraffin. In addition to neutron measurements, different γ-ray shielding parameters such as mass attenuation coefficient (MAC), effective atom numbers (Zeff), half value layer (HVL) and mean free path (MFP) have been calculated using WinXCOM software in order to investigate the effectiveness of using the prepared concretes as a radiation shielding materials. Gamma-ray results were compared with concretes and Pb-based glass.

Effect of different size of PbWO4 particles on EPDM composite for gamma-ray shielding

2020 ◽  
Vol 34 (07) ◽  
pp. 2050046
Author(s):  
Jinghui Fan ◽  
Juying Wu ◽  
Yan Ma
Keyword(s):  
Gamma Rays ◽  
Gamma Ray ◽  
Mechanical Test ◽  
Radiation Shielding ◽  
Reinforced Composites ◽  
Sem Images ◽  
Elongation At Break ◽  
Roll Mill ◽  
The Matrix ◽  
Shielding Properties

Ethylene Propylene Diene Monomer (EPDM) composites filled with 0–400 phr [Formula: see text] (PWO) were prepared by conventional process using a two-roll mill. Surface treatment of the fillers coated with KH570 was conducted to enhance the wettability and lubrication of fillers in the polymer matrix. According to SEM images and mechanical test, both micro- and submicro-fillers disperse homogeneously in the matrix, and adhesion of submicro-fillers to the matrix is stronger than that of micro-fillers. The submicro-PWO composites had better tensile strength and elongation at break than those composites containing micro-PWO powder, but a relatively higher hardness. The photon shielding test was performed to determine the radiation shielding properties of these composites, which showed that attenuation of gamma-rays for the submicro-PWO composites was substantially enhanced compared to micro-PWO reinforced composites.

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 Optimizing the shielding properties of strength-enhanced concrete containing marble

2020 ◽  
Vol 12 ◽  
pp. 120005
Author(s):  
Ahmed ABDEL-LATIF ◽  
Maged Kassab ◽  
M. I. Sayyed ◽  
H. O. Tekin
Keyword(s):  
Compressive Strength ◽  
Gamma Ray ◽  
Low Cost ◽  
Effective Atomic Number ◽  
Neutron Radiation ◽  
Mean Free Path ◽  
Strength Properties ◽  
Radiation Shielding ◽  
Removal Cross Section ◽  
Shielding Properties

The purpose of this study is to develop a low cost, locally produced concrete mixture with optimum marble content. The resulting mixture would have enhanced strength properties compared to the non-marble reference concrete, and improved radiation shielding properties. To accomplish these goals five concrete mixtures were prepared, containing 0, 5, 10, 15, and 20% marble waste powder as a cement replacement on the basis of weight.These samples were subjected to a compressive strength test. The shielding parameters such as mass attenuation coefficients μm, mean free path MFP, effective atomic number $Z_{eff}$ and exposure build-up factors EBF were measured, and results were compared with those obtained using the WinXcom program and MCNPX code in the photon energy range of 0.015 - 3 MeV. Moreover, the macroscopic fast neutron removal cross-section (neutron attenuation coefficient) was calculated and the results presented. The results show that the sample which contains 10% marble has the highest compressive strength and potentiallygood gamma ray and neutron radiation shielding properties.

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.

scholarly journals A Systematical Characterization of TeO2–V2O5 Glass System Using Boron (III) Oxide and Neodymium (III) Oxide Substitution: Resistance Behaviors against Ionizing Radiation

2021 ◽  
Vol 11 (7) ◽  
pp. 3035
Author(s):  
H. O. Tekin ◽  
Shams A. M. Issa ◽  
G. Kilic ◽  
Hesham M. H. Zakaly ◽  
N. Tarhan ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Glass System ◽  
Buildup Factor ◽  
Attenuation Coefficients ◽  
Gamma Ray Attenuation ◽  
Buildup Factors

This study aimed to perform an extensive characterization of a 74.75TeO2–0.25V2O5–(25 − x)B2O3-xNd2O3 glass system with (x = 0, 0.5, 1.0, and 1.5 mol%) for radiation shielding properties. Linear and mass attenuation coefficients were determined using Phy-X PSD software and compared with the simulation using Monte Carlo software MCNPX (version 2.7.0). Half value layer, mean free path, tenth value layer, effective atomic number, exposure buildup factor, and energy absorption buildup factors of VTBNd0.0, VTBNd0.5, VTBNd1.0, and VTBNd1.5 glasses were determined, respectively. The results showed that boron (III) oxide and neodymium (III) oxide substitution has an obvious impact on the gamma ray attenuation properties of the studied glasses. It can be concluded that the VTBNd1.5 sample with the highest content of neodymium (III) oxide (1.5 mol%) is the superior sample for shielding of gamma radiation in the investigated energy range.

Sign in / Sign up

Export Citation Format

Share Document