Monte Carlo Simulation of Gamma and Neutron Shielding with High-performance Ultra-heavy Cement Composite
Purpose: As the applications of nuclear technology increase in today’s world, radiation protection becomes even more important. Radiation protection is important in medical imaging applications and radiotherapy rooms. Therefore, in this research, we have investigated features of the ionizing radiati...
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| Format: | Article |
| Language: | English |
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Wolters Kluwer Medknow Publications
2024-12-01
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| Series: | Journal of Medical Physics |
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| Online Access: | https://journals.lww.com/10.4103/jmp.jmp_91_24 |
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| author | Mohammadreza Alipoor Mahdi Eshghi Ramazan Sever |
| author_facet | Mohammadreza Alipoor Mahdi Eshghi Ramazan Sever |
| author_sort | Mohammadreza Alipoor |
| collection | DOAJ |
| description | Purpose:
As the applications of nuclear technology increase in today’s world, radiation protection becomes even more important. Radiation protection is important in medical imaging applications and radiotherapy rooms. Therefore, in this research, we have investigated features of the ionizing radiation shielding of the modified cement composite with iron, strontium, zinc, and zirconium elements in the photon energy range of 15 keV to 10 MeV.
Materials and Methods:
To extract such features, it is necessary to use a computational method. In this research, we have done all our calculations based on the Geant4 tool based on the Monte Carlo method. This tool is a multipurpose tool that can be used for particle transport calculations such as electrons, protons, neutrons, heavy charged particles, and photons in different environments such as human tissues.
Results:
The mass attenuation coefficient of the samples was calculated using the Geant4 Monte Carlo simulation tool and compared with the results of the Phy-X program, which was in good agreement. To evaluate the radiation shielding capabilities, other quantities such as the linear attenuation coefficient, the thickness of the tenth value layer, the thermal neutron cross-section, absorption rate of thermal neutrons, and the cross-section of the fast neutron removal are determined.
Conclusions:
According to the quantitative results, cement composite is more effective in absorbing and weakening gamma and neutrons. Calculations of radiation shielding quantities show that cement composites containing tungsten carbide and thallium oxide waste powder are a suitable combination and a practical material for radiation control. In addition, by returning industrial waste to the production sector, they will also be effective in reducing environmental pollution. In general, the cement composite sample containing iron, thallium, zinc, zirconium, tungsten, and carbon elements shows a high potential for radiation protection applications. This study highlights the effective radiation shielding potential of cementitious composites and demonstrates the importance of advancing safety measures in medical and industrial radiation applications. |
| format | Article |
| id | doaj-art-8281ceb3bf1148779967a64c8fe3cda3 |
| institution | Kabale University |
| issn | 0971-6203 1998-3913 |
| language | English |
| publishDate | 2024-12-01 |
| publisher | Wolters Kluwer Medknow Publications |
| record_format | Article |
| series | Journal of Medical Physics |
| spelling | doaj-art-8281ceb3bf1148779967a64c8fe3cda32025-01-07T07:19:03ZengWolters Kluwer Medknow PublicationsJournal of Medical Physics0971-62031998-39132024-12-0149466167210.4103/jmp.jmp_91_24Monte Carlo Simulation of Gamma and Neutron Shielding with High-performance Ultra-heavy Cement CompositeMohammadreza AlipoorMahdi EshghiRamazan SeverPurpose: As the applications of nuclear technology increase in today’s world, radiation protection becomes even more important. Radiation protection is important in medical imaging applications and radiotherapy rooms. Therefore, in this research, we have investigated features of the ionizing radiation shielding of the modified cement composite with iron, strontium, zinc, and zirconium elements in the photon energy range of 15 keV to 10 MeV. Materials and Methods: To extract such features, it is necessary to use a computational method. In this research, we have done all our calculations based on the Geant4 tool based on the Monte Carlo method. This tool is a multipurpose tool that can be used for particle transport calculations such as electrons, protons, neutrons, heavy charged particles, and photons in different environments such as human tissues. Results: The mass attenuation coefficient of the samples was calculated using the Geant4 Monte Carlo simulation tool and compared with the results of the Phy-X program, which was in good agreement. To evaluate the radiation shielding capabilities, other quantities such as the linear attenuation coefficient, the thickness of the tenth value layer, the thermal neutron cross-section, absorption rate of thermal neutrons, and the cross-section of the fast neutron removal are determined. Conclusions: According to the quantitative results, cement composite is more effective in absorbing and weakening gamma and neutrons. Calculations of radiation shielding quantities show that cement composites containing tungsten carbide and thallium oxide waste powder are a suitable combination and a practical material for radiation control. In addition, by returning industrial waste to the production sector, they will also be effective in reducing environmental pollution. In general, the cement composite sample containing iron, thallium, zinc, zirconium, tungsten, and carbon elements shows a high potential for radiation protection applications. This study highlights the effective radiation shielding potential of cementitious composites and demonstrates the importance of advancing safety measures in medical and industrial radiation applications.https://journals.lww.com/10.4103/jmp.jmp_91_24attenuation coefficientcementsgamma-raymonte carlo simulationsshielding |
| spellingShingle | Mohammadreza Alipoor Mahdi Eshghi Ramazan Sever Monte Carlo Simulation of Gamma and Neutron Shielding with High-performance Ultra-heavy Cement Composite Journal of Medical Physics attenuation coefficient cements gamma-ray monte carlo simulations shielding |
| title | Monte Carlo Simulation of Gamma and Neutron Shielding with High-performance Ultra-heavy Cement Composite |
| title_full | Monte Carlo Simulation of Gamma and Neutron Shielding with High-performance Ultra-heavy Cement Composite |
| title_fullStr | Monte Carlo Simulation of Gamma and Neutron Shielding with High-performance Ultra-heavy Cement Composite |
| title_full_unstemmed | Monte Carlo Simulation of Gamma and Neutron Shielding with High-performance Ultra-heavy Cement Composite |
| title_short | Monte Carlo Simulation of Gamma and Neutron Shielding with High-performance Ultra-heavy Cement Composite |
| title_sort | monte carlo simulation of gamma and neutron shielding with high performance ultra heavy cement composite |
| topic | attenuation coefficient cements gamma-ray monte carlo simulations shielding |
| url | https://journals.lww.com/10.4103/jmp.jmp_91_24 |
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