A Study on Shield Design Aspects of a Semi-Industrial Co-60 Gamma Irradiation Facility at Gamma Source Division of Institute of Food and Radiation Biology of the Bangladesh Atomic Energy Commission

S. Ahmed, Mjh Khan, A. Nahar, M.F. Mortuza, M. Hosan
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Abstract

The aim of this work is to investigate the existing shield design aspects of a semi-industrial Cobalt- 60 Gamma Irradiation Facility for 100 kCi, designed for irradiation of pharmaceutical products and daily foodstuffs as well as for research and development purposes at the Institute of Food and Radiation Biology (IFRB) of the Bangladesh Atomic Energy Commission. Earlier, the initial activity of this facility was 65 kCi and stone based reinforced concrete (SBRC) of density 2.60 g/cc and specific thicknesses were used to shield the facility for safety to operational personnel and outside public. Due to a large demand for irradiation of pharmaceutical products as well as of daily foodstuffs, IFRB has decided to increase the initial activity up to 100 kCi for this facility. For this reason, the shielding design aspects of this facility were needed to be recalculated and checked for safety. This analysis was done using the Point-kernel Shielding Code Micro-Shield 5.05 and public domain Point-kernel Shielding code QAD-CGGP2 respectively considering the radiation worker dose limit of 10 μSv/hr of the International Commission on Radiological Protection, ICRP-60, 1990. The corresponding dose limit for public at large is 0.5 μSv/hr. The calculated dose rates at different locations around the facility are far below 10 μSv/hr except in one area. This location is inside the source room. No one is allowed to enter the room when the facility is in the ON mode. However, except one location, positions outside the facility have dose rates about 3 time higher than 0.5 μSv/hr, the dose limit for public at large. Therefore, this analysis shows that the existing shield design aspects of IFRB’s Co-60 gamma source room is safe for a 100 kCi source from the viewpoint of radiation safety to operating personnel but not for public at large within proximity of the facility. Bangladesh Journal of Medical Physics Vol.15 No.1 2022 P 1-7
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孟加拉国原子能委员会食品和辐射生物学研究所伽马源处半工业Co-60伽马辐照设施屏蔽设计方面的研究
这项工作的目的是调查一个半工业钴- 60 γ辐照设施现有的屏蔽设计方面,该设施设计用于辐照药品和日常食品以及孟加拉国原子能委员会食品和辐射生物学研究所的研究和开发目的。早些时候,该设施的初始活动为65 kCi,密度为2.60 g/cc的石基钢筋混凝土(SBRC)和特定厚度用于保护设施,以确保操作人员和外部公众的安全。由于对医药产品和日常食品的辐照有很大的需求,IFRB已决定将该设施的初始活度提高到100千摄氏度。因此,需要重新计算和检查该设施的屏蔽设计方面的安全性。考虑到国际放射防护委员会(ICRP-60) 1990年规定的辐射工作人员剂量限值为10 μSv/hr,分别采用点核屏蔽代码Micro-Shield 5.05和公共领域点核屏蔽代码QAD-CGGP2进行分析。相应的公众剂量限值为0.5 μSv/hr。除一个地区外,设施周围不同地点的计算剂量率均远低于10 μSv/hr。这个位置在源室里。设备处于开启状态时,任何人不得进入房间。然而,除了一个地点外,设施外的剂量率比公众的剂量限值0.5 μSv/hr高出约3倍。因此,该分析表明,从对操作人员的辐射安全角度来看,IFRB的Co-60 γ源室的现有屏蔽设计方面对于100 kCi的源是安全的,但对于设施附近的一般公众则不安全。孟加拉医学物理杂志Vol.15 No.1 2022 P . 1-7
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