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Calculation of Attenuation Parameter for Ir-192 Gamma Source in Shielding Materials

PURPOSE: Calculation of photon attenuation is necessary for the selection of shielding materials for an irradiation facility. METHODS AND MATERIALS: In this work, a Monte Carlo simulation was utilized to assess the effectiveness of clay-polyethylene mixture and clay as the radiation shielding materi...

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Autores principales: Sabri, Adila Hanim Aminordin, Abdul Aziz, M. Z., Olukotun, S. F., Tajudin, S. M.
Formato: Online Artículo Texto
Lenguaje:English
Publicado: Wolters Kluwer - Medknow 2022
Materias:
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9084575/
https://www.ncbi.nlm.nih.gov/pubmed/35548040
http://dx.doi.org/10.4103/jmp.jmp_86_21
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author Sabri, Adila Hanim Aminordin
Abdul Aziz, M. Z.
Olukotun, S. F.
Tajudin, S. M.
author_facet Sabri, Adila Hanim Aminordin
Abdul Aziz, M. Z.
Olukotun, S. F.
Tajudin, S. M.
author_sort Sabri, Adila Hanim Aminordin
collection PubMed
description PURPOSE: Calculation of photon attenuation is necessary for the selection of shielding materials for an irradiation facility. METHODS AND MATERIALS: In this work, a Monte Carlo simulation was utilized to assess the effectiveness of clay-polyethylene mixture and clay as the radiation shielding materials for high-energy gamma sources (Ir-192). Ordinary concrete was also studied as the benchmark. RESULTS: The calculated linear attenuation values for ordinary concrete are within 0.44% of the standard XCOM value for 380 keV photon. In the case of a multienergy Ir-192 gamma source, the calculated linear attenuation coefficient (μ) for ordinary concrete is 15.5% and 7.25% higher than clay and fabricated clay-polyethylene, respectively. Meanwhile, the μ value for fabricated clay-polyethylene is 8.3% higher than that of clay. CONCLUSION: In conclusion, a 10 cm thickness of clay and clay-polyethylene mixture is sufficient to attenuate 87% and 89% of photons from Ir-192 source. The calculated linear attenuation coefficients for the three shielding materials are also consistently higher, about 7.5%, than that of the XCOM value for 380 keV photon.
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spelling pubmed-90845752022-05-10 Calculation of Attenuation Parameter for Ir-192 Gamma Source in Shielding Materials Sabri, Adila Hanim Aminordin Abdul Aziz, M. Z. Olukotun, S. F. Tajudin, S. M. J Med Phys Original Article PURPOSE: Calculation of photon attenuation is necessary for the selection of shielding materials for an irradiation facility. METHODS AND MATERIALS: In this work, a Monte Carlo simulation was utilized to assess the effectiveness of clay-polyethylene mixture and clay as the radiation shielding materials for high-energy gamma sources (Ir-192). Ordinary concrete was also studied as the benchmark. RESULTS: The calculated linear attenuation values for ordinary concrete are within 0.44% of the standard XCOM value for 380 keV photon. In the case of a multienergy Ir-192 gamma source, the calculated linear attenuation coefficient (μ) for ordinary concrete is 15.5% and 7.25% higher than clay and fabricated clay-polyethylene, respectively. Meanwhile, the μ value for fabricated clay-polyethylene is 8.3% higher than that of clay. CONCLUSION: In conclusion, a 10 cm thickness of clay and clay-polyethylene mixture is sufficient to attenuate 87% and 89% of photons from Ir-192 source. The calculated linear attenuation coefficients for the three shielding materials are also consistently higher, about 7.5%, than that of the XCOM value for 380 keV photon. Wolters Kluwer - Medknow 2022 2022-03-31 /pmc/articles/PMC9084575/ /pubmed/35548040 http://dx.doi.org/10.4103/jmp.jmp_86_21 Text en Copyright: © 2022 Journal of Medical Physics https://creativecommons.org/licenses/by-nc-sa/4.0/This is an open access journal, and articles are distributed under the terms of the Creative Commons Attribution-NonCommercial-ShareAlike 4.0 License, which allows others to remix, tweak, and build upon the work non-commercially, as long as appropriate credit is given and the new creations are licensed under the identical terms.
spellingShingle Original Article
Sabri, Adila Hanim Aminordin
Abdul Aziz, M. Z.
Olukotun, S. F.
Tajudin, S. M.
Calculation of Attenuation Parameter for Ir-192 Gamma Source in Shielding Materials
title Calculation of Attenuation Parameter for Ir-192 Gamma Source in Shielding Materials
title_full Calculation of Attenuation Parameter for Ir-192 Gamma Source in Shielding Materials
title_fullStr Calculation of Attenuation Parameter for Ir-192 Gamma Source in Shielding Materials
title_full_unstemmed Calculation of Attenuation Parameter for Ir-192 Gamma Source in Shielding Materials
title_short Calculation of Attenuation Parameter for Ir-192 Gamma Source in Shielding Materials
title_sort calculation of attenuation parameter for ir-192 gamma source in shielding materials
topic Original Article
url https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9084575/
https://www.ncbi.nlm.nih.gov/pubmed/35548040
http://dx.doi.org/10.4103/jmp.jmp_86_21
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