Investigation of gamma radiation shielding properties of polyethylene glycol in the energy range from 8.67 to 23.19 keV

Akhdar, Hanan; Marashdeh, M.W.; Alaqeel, Muneerah A.

doi:10.1016/j.net.2021.08.028

Cited by 12 publications

(9 citation statements)

References 16 publications

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“…Many of these studies showed that the gamma attenuation performances of polymers are promising, and the ability of polymers to attenuate gamma rays may be increased by adding different composites with high atomic numbers to these polymers [1][2][3][4][5].…”

Section: Introductionmentioning

confidence: 99%

Theoretical Investigation of Gamma- and Neutron-Shielding Properties of Polysulfone (PSU) Polymer Material Using Geant4

Akhdar

2022

Polymers

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Polymers are widely used materials that have many medical and industrial applications. Some polymers have even been introduced as radiation-shielding materials; therefore, many studies are focusing on new polymers and their interactions with photons and neutrons. Research has focused on theoretical estimation of the shielding effectiveness of different materials. It is well known that theoretical studies on the shielding properties of different materials through modeling and simulation have many benefits, as they help scientists to choose the right shielding material for a specific application, and they are also much more cost-effective and take much less time compared to experimental studies. In this study, polysulfone (PSU) was investigated. PSU is a high-temperature, amber-colored, semi-transparent plastic material with good mechanical properties. It is resistant to degradation from hot water and steam and is often used in medical and food preparation applications, where repeated sterilization is required. The interactions of photons and neutrons with PSU were investigated using a Monte Carlo-based simulation toolkit, Geant4, within a wide range of energies of both photons and neutrons. The mass attenuation coefficients (µm), the half-value layers (HVL), the effective atomic numbers (Zeff), and the effective electron densities (Neff) of gammas were investigated. In addition, the effective removal cross-sections (ΣR) and the mean free paths (λ) of neutrons were also studied. The results were then compared to other commonly used polymer materials.

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Section: Introductionmentioning

confidence: 99%

Theoretical Investigation of Gamma- and Neutron-Shielding Properties of Polysulfone (PSU) Polymer Material Using Geant4

Akhdar

2022

Polymers

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“…The details of the experimental setup are shown in Figure 1. The same principle of the XRF system was used in previous work [26,27]. A Si-PIN photodiode XR-100 CR detector with an active area of 7 mm 2 and thickness of 300 µm was used to detect the intensities of X-ray fluorescence (XRF) energies.…”

Section: Methodsmentioning

confidence: 99%

Evaluation of Gamma Radiation Properties of Four Types of Surgical Stainless Steel in the Energy Range of 17.50–25.29 keV

Marashdeh

Al-Hamarneh

2021

Materials

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In this study, the gamma radiation properties of four types of surgical-grade stainless steel (304, 304L, 316 and 316L) were investigated. The effective atomic number Zeff, effective electron density Neff and half-value layer (HVL) of four types of surgical-grade stainless steel were determined via the mass attenuation coefficient (μ/ρ). The μ/ρ coefficients were determined experimentally using an X-ray fluorescence (XRF) technique and theoretically via the WinXCOM program. The Kα1 of XRF photons in the energy range between 17.50 and 25.29 keV was used from pure metal plates of molybdenum (Mo), palladium (Pd), silver (Ag) and tin (Sn). A comparison between the experimental and theoretical values of μ/ρ revealed that the experimental values were lower than the theoretical calculations. The relative differences between the theoretical and experimental values were found to decrease with increasing photon energy. The lowest percentage difference between the experimental and theoretical values of μ/ρ was between −6.17% and −9.76% and was obtained at a photon energy of 25.29 keV. Sample 316L showed the highest value of μ/ρ at the energies 21.20, 22.19 and 25.29 keV. In addition, the measured results of Zeff and Neff for all samples behaved similarly in the given energy range and were found to be in good agreement with the calculations. The equivalent atomic number (Zeff) of the investigated stainless-steel samples was calculated using the interpolation method to compare the samples at the same source energy. The 316L stainless steel had higher values of μ/ρ, Zeff and Zeq and lower values of HVL compared with the other samples. Therefore, it is concluded that the 316L sample is more effective in absorbing gamma radiation.

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“…The fast neutron removal cross-section of any element can be calculated using the empirical formulas indicated by Equations ( 12) and ( 13) [2]:…”

Section: Neutron Attenuationmentioning

confidence: 99%

“…Much of this research demonstrated that polymers' photon attenuation capabilities are promising, and their capacity to attenuate photons be boosted by combining them with various composites with high atomic numbers. Numerous investigated polymers also have high thermal neutron cross-sections and high neutron particle sensitivity, making them excellent neutron-shielding materials [1][2][3][4][5].…”

Section: Introductionmentioning

confidence: 99%

Geant4 Simulation of the Effect of Different Composites on Polyimide Photon and Neutron Shielding Properties

Akhdar

Alotaibi

2023

Polymers

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Polymers are widely used materials that have many medical and industrial applications. Some polymers have even been introduced as radiation-shielding materials; therefore, many studies are focusing on new polymers and their interactions with photons and neutrons. Research has recently focused on the theoretical estimation of the shielding effectiveness of Polyimide doped with different composites. It is well known that theoretical studies on the shielding properties of different materials through modeling and simulation have many benefits, as they help scientists to choose the right shielding material for a specific application, and they are also much more cost-effective and take much less time compared to experimental studies. In this study, Polyimide (C35H28N2O7) was investigated. It is a high-performance polymer, well known for its outstanding chemical and thermal stability, as well as for its high mechanical resistance. Because of its exceptional properties, it is used in high-end applications. The performance of Polyimide and Polyimide doped with different weight fractions of composites (5, 10, 15, 20 and 25 wt.%) as a shielding material against photons and neutrons were investigated using a Monte Carlo-based simulation toolkit Geant4 within a wide range of energies of both photons and neutrons from 10 to 2000 KeVs. Polyimide can be considered a good neutron shielding material, and its photon shielding abilities could be further enhanced when adding different high atomic number composites to it. The results showed that Au and Ag gave the best results in terms of the photon shielding properties, while ZnO and TiO2 had the least negative effect on the neutron shielding properties. The results also indicate that Geant4 is a very reliable tool when it comes to evaluating the shielding properties against photons and neutrons of any material.

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Investigation of gamma radiation shielding properties of polyethylene glycol in the energy range from 8.67 to 23.19 keV

Cited by 12 publications

References 16 publications

Theoretical Investigation of Gamma- and Neutron-Shielding Properties of Polysulfone (PSU) Polymer Material Using Geant4

Theoretical Investigation of Gamma- and Neutron-Shielding Properties of Polysulfone (PSU) Polymer Material Using Geant4

Evaluation of Gamma Radiation Properties of Four Types of Surgical Stainless Steel in the Energy Range of 17.50–25.29 keV

Geant4 Simulation of the Effect of Different Composites on Polyimide Photon and Neutron Shielding Properties

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