Theoretical Ionizing Radiation Shielding Parameters of Thulium Doped Zinc Borotellurite Glass

Ionizing radiation is considered hazardous to human health but it is very crucial for many applications such as nuclear fuel processing and medical radiography. Glass has played a huge role as a shielding material for ionizing radiation in the application that requires line of sight. Nowadays, lead...

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Main Authors: Rusni Nur Arina Mat, Laoding Hasnimulyati, Amat Azuraida
Format: Article
Language:English
Published: EDP Sciences 2024-01-01
Series:E3S Web of Conferences
Online Access:https://www.e3s-conferences.org/articles/e3sconf/pdf/2024/11/e3sconf_icschem2024_03009.pdf
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author Rusni Nur Arina Mat
Laoding Hasnimulyati
Amat Azuraida
author_facet Rusni Nur Arina Mat
Laoding Hasnimulyati
Amat Azuraida
author_sort Rusni Nur Arina Mat
collection DOAJ
description Ionizing radiation is considered hazardous to human health but it is very crucial for many applications such as nuclear fuel processing and medical radiography. Glass has played a huge role as a shielding material for ionizing radiation in the application that requires line of sight. Nowadays, lead glass is commonly used in industry due to its properties of high density. However, lead toxicity can give harmful effects on humans’ health and the environment. As for concrete, it takes a lot of space, blocks the line of sight and the density of concrete may reduce due to prolonged exposure to radiation. To cater these problems, this study proposed a glass composition that is thulium doped zinc borotellurite glass. Thulium is used due to its potential such as resistance to corrosion and oxidation, good ductility and does not pose any environmental threat. In this study, Phy-X and WinXCom software is used. The main goal of this research is to study the theoretical radiation shielding parameters of thulium doped zinc borotellurite glass. Based on the results, it is found that the best glass sample is the sample composition with 5% thulium oxide whereby it has the highest value for mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), atomic cross section (ACS), electronic cross section (ECS) and effective atomic number (Zeff). The best glass sample with 5% thulium oxide also yields the results of the lowest half-value layer (HVL) and mean free path (MFP). Comparing the results of Phy-X and WinXCom, it is found that the deviation between the software is less than 5%. Also, when the results for each radiation shielding parameter of 5% thulium oxide are compared with other radiation shielding materials, significant results are found where the proposed glass sample provides better shielding against gamma radiation.
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spelling doaj.art-3dbaf4f9c99a4f5a9452be3f7b15e8fe2024-02-02T07:56:08ZengEDP SciencesE3S Web of Conferences2267-12422024-01-014810300910.1051/e3sconf/202448103009e3sconf_icschem2024_03009Theoretical Ionizing Radiation Shielding Parameters of Thulium Doped Zinc Borotellurite GlassRusni Nur Arina Mat0Laoding Hasnimulyati1Amat Azuraida2Faculty of Applied Science, Universiti Teknologi MARA Cawangan Pahang, Kampus JengkaFaculty of Applied Science, Universiti Teknologi MARA Cawangan Pahang, Kampus JengkaDepartment of Physics, Centre for Defence Foundation Studies, Universiti Pertahanan Nasional Malaysia, Kem Sungai BesiIonizing radiation is considered hazardous to human health but it is very crucial for many applications such as nuclear fuel processing and medical radiography. Glass has played a huge role as a shielding material for ionizing radiation in the application that requires line of sight. Nowadays, lead glass is commonly used in industry due to its properties of high density. However, lead toxicity can give harmful effects on humans’ health and the environment. As for concrete, it takes a lot of space, blocks the line of sight and the density of concrete may reduce due to prolonged exposure to radiation. To cater these problems, this study proposed a glass composition that is thulium doped zinc borotellurite glass. Thulium is used due to its potential such as resistance to corrosion and oxidation, good ductility and does not pose any environmental threat. In this study, Phy-X and WinXCom software is used. The main goal of this research is to study the theoretical radiation shielding parameters of thulium doped zinc borotellurite glass. Based on the results, it is found that the best glass sample is the sample composition with 5% thulium oxide whereby it has the highest value for mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), atomic cross section (ACS), electronic cross section (ECS) and effective atomic number (Zeff). The best glass sample with 5% thulium oxide also yields the results of the lowest half-value layer (HVL) and mean free path (MFP). Comparing the results of Phy-X and WinXCom, it is found that the deviation between the software is less than 5%. Also, when the results for each radiation shielding parameter of 5% thulium oxide are compared with other radiation shielding materials, significant results are found where the proposed glass sample provides better shielding against gamma radiation.https://www.e3s-conferences.org/articles/e3sconf/pdf/2024/11/e3sconf_icschem2024_03009.pdf
spellingShingle Rusni Nur Arina Mat
Laoding Hasnimulyati
Amat Azuraida
Theoretical Ionizing Radiation Shielding Parameters of Thulium Doped Zinc Borotellurite Glass
E3S Web of Conferences
title Theoretical Ionizing Radiation Shielding Parameters of Thulium Doped Zinc Borotellurite Glass
title_full Theoretical Ionizing Radiation Shielding Parameters of Thulium Doped Zinc Borotellurite Glass
title_fullStr Theoretical Ionizing Radiation Shielding Parameters of Thulium Doped Zinc Borotellurite Glass
title_full_unstemmed Theoretical Ionizing Radiation Shielding Parameters of Thulium Doped Zinc Borotellurite Glass
title_short Theoretical Ionizing Radiation Shielding Parameters of Thulium Doped Zinc Borotellurite Glass
title_sort theoretical ionizing radiation shielding parameters of thulium doped zinc borotellurite glass
url https://www.e3s-conferences.org/articles/e3sconf/pdf/2024/11/e3sconf_icschem2024_03009.pdf
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