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Akhdar H, Alshehri M. Geant4 Simulation of Photon- and Neutron-Shielding Capabilities of Biopolymer Blends of Poly(lactic acid) and Poly(hydroxybutyrate). Polymers (Basel) 2023; 15:4257. [PMID: 37959937 PMCID: PMC10648397 DOI: 10.3390/polym15214257] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 10/09/2023] [Revised: 10/26/2023] [Accepted: 10/27/2023] [Indexed: 11/15/2023] Open
Abstract
Simulation is used by scientists to imitate a real-life experimental setup in order to save time, costs and effort. Geant4, a toolkit based on the Monte Carlo method, has been widely used in investigating the radiation-shielding properties of different materials. In many recent studies, researchers have focused on polymers and their shielding capabilities. Poly(lactic acid) (PLA) is a widely used biopolymer in many applications due to its excellent mechanical properties. However, it has limitations related to its degree of crystallinity and molecular characteristics, which could be improved through blending with other biodegradable polymers such as poly(hydroxybutyrate) (PHB). Previous published studies have shown that the mechanical properties of such blends can be improved further. In this work, the effect of blending PHB with PLA on the photon- and neutron-shielding capabilities will be investigated using Geant4 over a wide energy range, as well as the effect of doping those blends with metal oxides. The results show that the shielding properties of the polymers are affected by blending with other polymers and by doping the polymer blends with different metal oxides, and they confirm that Geant4 is a very reliable tool that can simulate any material's shielding properties against photons and neutrons.
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Affiliation(s)
- Hanan Akhdar
- Department of Physics, Faculty of Science, Imam Mohammad Ibn Saud Islamic University (IMSIU), P.O. Box 90950, Riyadh 11623, Saudi Arabia;
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Akhdar H, Alotaibi R. Geant4 Simulation of the Effect of Different Composites on Polyimide Photon and Neutron Shielding Properties. Polymers (Basel) 2023; 15:polym15081973. [PMID: 37112120 PMCID: PMC10145152 DOI: 10.3390/polym15081973] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 03/24/2023] [Revised: 04/18/2023] [Accepted: 04/20/2023] [Indexed: 04/29/2023] Open
Abstract
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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Affiliation(s)
- Hanan Akhdar
- Department of Physics, Faculty of Science, Imam Mohammad Ibn Saud Islamic University (IMSIU), Riyadh 11623, Saudi Arabia
| | - Rawan Alotaibi
- Department of Physics, Faculty of Science, Imam Mohammad Ibn Saud Islamic University (IMSIU), Riyadh 11623, Saudi Arabia
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Oğul H, Agar O, Bulut F, Kaçal MR, Dilsiz K, Polat H, Akman F. A comparative neutron and gamma-ray radiation shielding investigation of molybdenum and boron filled polymer composites. Appl Radiat Isot 2023; 194:110731. [PMID: 36812766 DOI: 10.1016/j.apradiso.2023.110731] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 12/18/2022] [Revised: 02/05/2023] [Accepted: 02/15/2023] [Indexed: 02/19/2023]
Abstract
This work presents a detailed radiation shielding study for polymer composites filled with Boron and Molybdenum additives. The chosen novel polymer composites were produced at different percentages of the additive materials to provide a proper evaluation of their neutron and gamma-ray attenuation abilities. The effect of additive particle size on the shielding characteristics was further investigated. On the gamma-ray side, simulation, theoretical and experimental evaluations were performed in a wide range of photon energies varying from 59.5 keV to 1332.5 keV with help of MC simulations (GEANT4 and FLUKA), WinXCOM code, a High Purity Germanium Detector, respectively. A remarkable consistency was reported between them. On the neutron shielding side, the prepared samples produced with nano and micron particle size additives were additionally examined by providing fast neutron removal cross-section (ΣR) and the simulated neutron transmissions through the prepared samples. The samples filled with nano sized particles show better shielding capability than the one filled with micron sized particles. In other words, a new polymer shielding material that does not contain toxic content is introduced: the sample codded N-B0Mo50 exhibits superior radiation attenuation.
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Affiliation(s)
- H Oğul
- Department of Nuclear Engineering, Faculty of Engineering and Architecture, Sinop University, Sinop, Turkiye; Sinop University Energy Research and Application Center, Sinop, Turkiye.
| | - O Agar
- Karamanoğlu Mehmetbey University, Department of Medical Imaging Techniques, 70100, Karaman, Turkiye
| | - F Bulut
- Sinop University Energy Research and Application Center, Sinop, Turkiye; Scientific and Technological Research Applications and Research Center, Sinop University, Sinop, Turkiye
| | - M R Kaçal
- Giresun University, Arts and Sciences Faculty, Department of Physics, 28100, Giresun, Turkiye
| | - K Dilsiz
- Bingöl University, Faculty of Art and Science, Department of Physics, 12000, Bingöl, Turkiye
| | - H Polat
- Bingöl University, Vocational School of Technical Sciences, Department of Architecture and Urban Planning, 12000, Bingöl, Turkiye
| | - F Akman
- Bingöl University, Vocational School of Social Sciences, Department of Property Protection and Security, Program of Occupational Health and Safety, 12000, Bingöl, Turkiye
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Gultekin B, Ogul H. Evaluation of Acrylonitrile Butadiene Styrene (ABS) polymer reinforced with Bi and TiO 2 nanopowders for gamma and neutron shielding. RADIOCHIM ACTA 2022. [DOI: 10.1515/ract-2022-0081] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/12/2022]
Abstract
Abstract
3D printer technology has recently become easily reachable technology and are used to create simple or complex structures with high-quality. Its superior advantages could also be useful on the production of effective radiation shielding materials. On this purpose, the presented work studies the gamma and neutron shielding effectiveness of Acrylonitrile Butadiene Styrene (ABS) sample, a 3D printing material, reinforced with Bi and TiO2 nanopowders at various gamma and neutron energies. The gamma shielding properties were evaluated using experimental (High Purity Germanium detector system), theoretical (WinXCOM computer program) and simulation techniques (GEANT4 and FLUKA) in a wide gamma energy region ranging from 59.5 to 1332.5 keV. The investigation on neutron attenuation capabilities of the printed composites were performed with help of simulation and theoretical approaches for various sample thickness and neutron energies. The half value layer of ABS-Bi10 sample is found to be as 4.9565 cm, which is much smaller than some commercial polymers: polyvinylidenechloride, polyamide, polyacrylonitrile, polyphenylenesulfide, and unsaturated polyester. With the usage of 3D printing technology, significant enhancements in neutron and gamma shielding were reported.
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Affiliation(s)
- Batuhan Gultekin
- Department of Nuclear Engineering , Faculty of Engineering and Architecture, Sinop University , Sinop , Turkey
| | - Hasan Ogul
- Department of Nuclear Engineering , Faculty of Engineering and Architecture, Sinop University , Sinop , Turkey
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Akhdar H. Theoretical Investigation of Fast Neutron and Gamma Radiation Properties of Polycarbonate-Bismuth Oxide Composites Using Geant4. NANOMATERIALS (BASEL, SWITZERLAND) 2022; 12:nano12203577. [PMID: 36296770 PMCID: PMC9609593 DOI: 10.3390/nano12203577] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Subscribe] [Scholar Register] [Received: 09/18/2022] [Revised: 10/10/2022] [Accepted: 10/10/2022] [Indexed: 05/14/2023]
Abstract
The gamma mass (µm) and linear (µ) attenuation coefficients of polycarbonate-bismuth oxide composites (PC-Bi2O3) with different bismuth oxide weight factors were investigated theoretically using EpiXS and a Monte Carlo simulation-based toolkit and Geant4 within an energy range between 0.1 and 2 MeV. The wide energy ranges of gamma rays and neutrons were chosen to cover as many applications as possible. The attenuation coefficients were then used to compute the half-value layers. The effective atomic numbers and effective electron densities of the studied samples obtained by EpiXS were compared as well. In order to further evaluate the shielding effectiveness of the studied samples, the thicknesses of all the investigated samples equivalent to 0.5 mm lead at a gamma energy of 511 keV were compared using a Geant4 code simulating a female numerical phantom with a gamma source placed facing the chest and a cylinder-shaped shield wrapped around the trunk area. The fast neutron removal cross sections of the investigated samples were studied to evaluate the effect of the weight factor of nanocomposites on the neutron shielding capabilities of the polymer as well.
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Affiliation(s)
- Hanan Akhdar
- Physics Department, Faculty of Sciences, Imam Mohammad Ibn Saud Islamic University (IMSIU), Riyadh 13318, Saudi Arabia
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Akhdar H. Theoretical Investigation of Gamma- and Neutron-Shielding Properties of Polysulfone (PSU) Polymer Material Using Geant4. Polymers (Basel) 2022; 14:polym14163374. [PMID: 36015631 PMCID: PMC9416465 DOI: 10.3390/polym14163374] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 07/06/2022] [Revised: 08/15/2022] [Accepted: 08/17/2022] [Indexed: 11/16/2022] Open
Abstract
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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Affiliation(s)
- Hanan Akhdar
- Department of Physics, Faculty of Science, Imam Mohammad Ibn Saud Islamic University (IMSIU), P.O. Box 90950, Riyadh 11623, Saudi Arabia
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Cheewasukhanont W, Limkitjaroenporn P, Sayyed M, Kothan S, Kim H, Kaewkhao J. High density of tungsten gadolinium borate glasses for radiation shielding material: Effect of WO3 concentration. Radiat Phys Chem Oxf Engl 1993 2022. [DOI: 10.1016/j.radphyschem.2021.109926] [Citation(s) in RCA: 9] [Impact Index Per Article: 4.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 02/07/2023]
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Sangwaranatee N, Cheewasukhanont W, Limkitjaroenporn P, Borisut P, Wongdamnern N, Khrongchaiyaphum F, Kothan S, Kaewkhao J. Development of bismuth alumino borosilicate glass for radiation shielding material. Radiat Phys Chem Oxf Engl 1993 2021. [DOI: 10.1016/j.radphyschem.2021.109542] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 02/07/2023]
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Abstract
Abstract
The goal of this study is to examine theoretically radiation absorption properties of zinc alumino bismuth borate (BZnAlBiSm) glasses with chemical formula 60B2O3-9ZnO-(30-x)Al2O3-xBi2O3-1Sm2O3 where x = 5, 10, 15 and 20 mol%. The linear and mass attenuation coefficents of BZnAlBiSm glasses turn out as this trend BZnAlBiSm-1<BZnAlBiSm-2<BZnAlBiSm-3<BZnAlBiSm-4. The BZnAlBiSm-4 with the smallest half value layers, tenth value layers and mean free paths in the examined energy ranges has the superior radiation shielding characteristics among the BZnAlBiSm glasses. The BZnAlBiSm-4 glass has the highest radiation protection efficiency among the BZnAlBiSm glasses. The transmission factors increase as photon energy range enhances from 0.015 to 15 MeV and thickness declines from 2.5 to 0.5 cm. The energy buildup factors and energy absorption buildup factors of BZnAlBiSm glasses reduce from 15 to 1 mfp. Variation of the effective atomic number and effective electron density as a function of photon energy for BZnAlBiSm glasses are similar. The projected ranges of electron, proton, alpha and carbon for the BZnAlBiSm glasses increase as photon energy enlarges. The fast neutron removal cross sections of the BZnAlBiSm glasses vary in order of BZnAlBiSm-4<BZnAlBiSm-3<BZnAlBiSm-2<BZnAlBiSm-1. Thus, it can be concluded that BZnAlBiSm-1 has the highest neutron absorption ability among the BZnAlBiSm glasses.
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Affiliation(s)
- Canel Eke
- Department of Mathematics and Science Education , Faculty of Education, Akdeniz University , 07058 , Antalya , Turkey
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More CV, Alavian H, Pawar PP. Evaluation of gamma ray and neutron attenuation capability of thermoplastic polymers. Appl Radiat Isot 2021; 176:109884. [PMID: 34358917 DOI: 10.1016/j.apradiso.2021.109884] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 05/14/2021] [Revised: 06/30/2021] [Accepted: 07/29/2021] [Indexed: 10/20/2022]
Abstract
The fast neutron and gamma ray attenuation capability of the most common thermoplastic polymers used in nuclear applications has been evaluated theoretically. Monte Carlo simulation has been used to compute the gamma-ray energy absorption buildup factor in the energy range 0.015-15 MeV at penetration depths up to 40 MFP. The results of MCNPX calculations have been validated against the results derived from the Geometric Progression fitting method. To evaluate neutron attenuation performance of the polymers, the fast neutron removal cross-section has been determined using theoretical database. Despite the superior ability of polysulfone and poly (ether sulfone) in gamma ray attenuation, high-density polyethylene has been found to have the best fast neutron removal ability among all. The detailed insights into the fast neutron and gamma ray shielding properties of selected polymers in the present work might have great potential applications in nuclear systems.
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Affiliation(s)
- Chaitali V More
- Department of Physics, Dr. Babasaheb Ambedkar Marathwada University, Aurangabad, 431004, Maharashtra, India.
| | - Hoda Alavian
- Faculty of Physics and Nuclear Engineering, Shahrood University of Technology, Shahrood, Iran
| | - Pravina P Pawar
- Department of Physics, Dr. Babasaheb Ambedkar Marathwada University, Aurangabad, 431004, Maharashtra, India
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Ouardi A. Neutron shielding calculations for neutron imaging facility at the Maâmora Triga reactor. Appl Radiat Isot 2021; 176:109852. [PMID: 34252750 DOI: 10.1016/j.apradiso.2021.109852] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 03/16/2020] [Revised: 02/19/2021] [Accepted: 06/28/2021] [Indexed: 11/17/2022]
Abstract
The build of neutron imaging facility is planned in the tangential beam around the TRIGA 2 MW, located in the Mâamora Nuclear Research Centre of Morocco. The design of this equipment and the plans for all operations should be evaluated in advance for the adequacy of radiation protection. Cement and concrete has been widely used as shielding material in a nuclear reactor in order to minimize exposure to individuals. In this paper GEANT4 and FLUKA simulation toolkit were used to study neutron attenuation, and optimizing the layers of shielding material to minimize thickness. Materials being studied include different types of concrete such as Hematite and Hormirad mixed borax with different boron and iron compositions. Initial studies indicate that optimized shielding material is Hematite. A total thickness of 700 mm produces the required attenuation factor. Further studies may allow optimizing the shielding enclosures. Because of the low floor load (5000 kg/m2), one solution that could be adopted is the substitution one bloc shielding by two blocks (with a half thickness) with air gap between them. The model allows studying the performance of the shielding materials in this particular space arrangement. The main goal is to maintain the total dose outside the shield boundary less than 5.0e-03 mSv/h during operation.
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Affiliation(s)
- Afaf Ouardi
- Center National de l'Energie des Sciences et des Techniques Nucléaires, Morocco.
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The effect of incorporated recycled low density polyethylene (LDPE) on the fast neutron shielding behaviour (FNSB) of clay matrix using MCNP and PHITS Monte Carlo codes. Radiat Phys Chem Oxf Engl 1993 2021. [DOI: 10.1016/j.radphyschem.2021.109351] [Citation(s) in RCA: 7] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Mann KS, Mann SS. Py-MLBUF: Development of an online-platform for gamma-ray shielding calculations and investigations. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107845] [Citation(s) in RCA: 27] [Impact Index Per Article: 9.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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