Design and optimization of a shield for Am-Be source to reduce radiation hazards using MCNPX code
Aim: Protection against nuclear radiation is one of the most important issues in nuclear technology and industries that use this technology. Among the types of radiation emitted from radioactive sources, neutron and gamma rays are among the most dangerous radiations due to lack of electrical charge...
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
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Wolters Kluwer Medknow Publications
2022-01-01
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| Series: | International Journal of Environmental Health Engineering |
| Subjects: | |
| Online Access: | http://www.ijehe.org/article.asp?issn=2277-9183;year=2022;volume=11;issue=1;spage=17;epage=17;aulast=Nasrabadi |
| _version_ | 1797902716283912192 |
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| author | Mohsen Nasri Nasrabadi Farhad Forouharmajd Mehdi Nasri Nasrabadi |
| author_facet | Mohsen Nasri Nasrabadi Farhad Forouharmajd Mehdi Nasri Nasrabadi |
| author_sort | Mohsen Nasri Nasrabadi |
| collection | DOAJ |
| description | Aim: Protection against nuclear radiation is one of the most important issues in nuclear technology and industries that use this technology. Among the types of radiation emitted from radioactive sources, neutron and gamma rays are among the most dangerous radiations due to lack of electrical charge and serious damage to living tissues. The principal challenge in radiation protection is the proper design of a shield against neutron and gamma radiations. Hence, this study has investigated the improvement of the protection against these radiations. Materials and Methods: This study is of applied-developmental and quantitative type. Calculations have been performed using the MCNPX code in this study, which is one of the strongest nuclear calculation codes. The data were analyzed using quantitative statistics and ORIGIN software (OriginLab company, 1992, Northampton, Massachusetts, USA). Results: Based on the results, utilizing the spherical geometry had a better performance to increase the neutron fluxes in comparison with the cylindrical and cubic geometries. Moreover, polyethylene with high density was selected as the best moderator. Ultimately, it was dealt with the comparison and selection of the best protection to minimize the produced gamma rays due to the absorption of neutrons in different materials used by the source and neutrons that run away from the outer surface of the source configuration. Conclusion: Using the composite sphere of paraffin and polyethylene with high density up to a radius of 12 cm and tungsten with a thickness of 1 cm was suggested as the final configuration for the aim of this study. In comparison to the no-protection mode, this protection is effective to 74% in reducing the neuron dosage and 55% in reducing the primary gamma-ray, while the mentioned protection is about 72%–73% effective in reducing the general dose. |
| first_indexed | 2024-04-10T09:22:06Z |
| format | Article |
| id | doaj.art-5ae1f1820d74414099ac276788ab6c7b |
| institution | Directory Open Access Journal |
| issn | 2277-9183 |
| language | English |
| last_indexed | 2024-04-10T09:22:06Z |
| publishDate | 2022-01-01 |
| publisher | Wolters Kluwer Medknow Publications |
| record_format | Article |
| series | International Journal of Environmental Health Engineering |
| spelling | doaj.art-5ae1f1820d74414099ac276788ab6c7b2023-02-20T09:41:31ZengWolters Kluwer Medknow PublicationsInternational Journal of Environmental Health Engineering2277-91832022-01-01111171710.4103/ijehe.ijehe_7_22Design and optimization of a shield for Am-Be source to reduce radiation hazards using MCNPX codeMohsen Nasri NasrabadiFarhad ForouharmajdMehdi Nasri NasrabadiAim: Protection against nuclear radiation is one of the most important issues in nuclear technology and industries that use this technology. Among the types of radiation emitted from radioactive sources, neutron and gamma rays are among the most dangerous radiations due to lack of electrical charge and serious damage to living tissues. The principal challenge in radiation protection is the proper design of a shield against neutron and gamma radiations. Hence, this study has investigated the improvement of the protection against these radiations. Materials and Methods: This study is of applied-developmental and quantitative type. Calculations have been performed using the MCNPX code in this study, which is one of the strongest nuclear calculation codes. The data were analyzed using quantitative statistics and ORIGIN software (OriginLab company, 1992, Northampton, Massachusetts, USA). Results: Based on the results, utilizing the spherical geometry had a better performance to increase the neutron fluxes in comparison with the cylindrical and cubic geometries. Moreover, polyethylene with high density was selected as the best moderator. Ultimately, it was dealt with the comparison and selection of the best protection to minimize the produced gamma rays due to the absorption of neutrons in different materials used by the source and neutrons that run away from the outer surface of the source configuration. Conclusion: Using the composite sphere of paraffin and polyethylene with high density up to a radius of 12 cm and tungsten with a thickness of 1 cm was suggested as the final configuration for the aim of this study. In comparison to the no-protection mode, this protection is effective to 74% in reducing the neuron dosage and 55% in reducing the primary gamma-ray, while the mentioned protection is about 72%–73% effective in reducing the general dose.http://www.ijehe.org/article.asp?issn=2277-9183;year=2022;volume=11;issue=1;spage=17;epage=17;aulast=Nasrabadiam-be sourcemixed radiation fieldmonte-carlo computationsprotection |
| spellingShingle | Mohsen Nasri Nasrabadi Farhad Forouharmajd Mehdi Nasri Nasrabadi Design and optimization of a shield for Am-Be source to reduce radiation hazards using MCNPX code International Journal of Environmental Health Engineering am-be source mixed radiation field monte-carlo computations protection |
| title | Design and optimization of a shield for Am-Be source to reduce radiation hazards using MCNPX code |
| title_full | Design and optimization of a shield for Am-Be source to reduce radiation hazards using MCNPX code |
| title_fullStr | Design and optimization of a shield for Am-Be source to reduce radiation hazards using MCNPX code |
| title_full_unstemmed | Design and optimization of a shield for Am-Be source to reduce radiation hazards using MCNPX code |
| title_short | Design and optimization of a shield for Am-Be source to reduce radiation hazards using MCNPX code |
| title_sort | design and optimization of a shield for am be source to reduce radiation hazards using mcnpx code |
| topic | am-be source mixed radiation field monte-carlo computations protection |
| url | http://www.ijehe.org/article.asp?issn=2277-9183;year=2022;volume=11;issue=1;spage=17;epage=17;aulast=Nasrabadi |
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