Assessment of Activity Concentration and Effective Doses from Bioassay Sample of Occupational Workers in NINMAS, Bangladesh

Ferdous, Jannatul; Hossain, Shahzad; Begum, Fatima; Hoque, Ashraful

doi:10.15406/ijrrt.2016.01.00008

Cited by 5 publications

(2 citation statements)

References 3 publications

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“…For thyroid diseases, 131 I is used for diagnostic and therapeutic purpose (3)(4)(5). When occupational workers process and labels the unsealed liquid sources with labeling compounds, the sources may enter their systems through inhalation and ingestion.…”

Section: Introductionmentioning

confidence: 99%

Individual Monitoring of Internal Exposure for Nuclear Medicine Workers in NINMAS through In-Vitro Bioassay Techniques

Shubho

Prodhan

Begum

et al. 2021

Bangladesh J. Nuclear Med.

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Internal radiation monitoring of occupational radiation workers is essential for protecting them against the risks of incorporated radionuclides. More than 400 workers in Bangladesh are working with unsealed radioactive sources and most of them are employed at different nuclear facilities. Among the 18 Nuclear Medicine Centers in the country, the National Institute of Nuclear Medicine and Allied Science (NINMAS), Dhaka was selected for this study where workers get internal radiation exposure while processing and labeling of the liquid sources. The aim of this study was to estimate the activity concentration and committed effective doses from bioassay sample, namely urine samples of Nuclear Medicine (NM) workers due to handling of radioactive Iodine (131I), Technetium (99mTc) and Fluorine (F-18). Total 86 urine samples were collected from 17 occupational workers of NINMAS during the year 2017 and analyzed using High Purity Germanium (HPGe) detector. The radioactivity of 131I and (99mTc) was found 2.21±0.44 BqL-1 to 444 ± 39.91 BqL-1 and 5.53±1.12 BqL-1 to 603 ± 72.36 BqL-1 respectively. Due to low activity of the unsealed F-18 sources and for appropriate shielding, radioactivity of F-18 was found below the minimum detection level in the urine samples of the workers who handled it. The effective doses of occupational workers have also been calculated using the radioactivity concentration and the dose coefficients given in ICRP publication 78. The highest and lowest effective doses due to handling of the unsealed source of (99mTc) were 28.2 and 0.0258μSv for working with 780 and 36mCi of radionuclide respectively. On the other hand, the highest and lowest effective doses due to handling of 131I were 8.73and 0.045μSv, for working with 1425 and 55 mCi respectively. Both the doses are found to comply with ICRP annual dose limit of 20 mSv. Bangladesh J. Nuclear Med. 22(2): 125-129, Jul 2019

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Section: Introductionmentioning

confidence: 99%

Individual Monitoring of Internal Exposure for Nuclear Medicine Workers in NINMAS through In-Vitro Bioassay Techniques

Shubho

Prodhan

Begum

et al. 2021

Bangladesh J. Nuclear Med.

Self Cite

View full text Add to dashboard Cite

show abstract

“…There are 18 Nuclear Medicine Centers in Bangladesh, from these Centers only one is selected for this study: National Institute of Nuclear Medicine and Allied Science (NINMAS) Dhaka. While processing and labeling of the liquid sources with labeling compounds, the sources may enter the bodies of the occupational worker through inhalation and ingestion [5]. The purpose of the present study has been to assess the activity of natural and artificial radionuclides in the air from the hot lab of the Institute of Nuclear Medicine (INM) concerning the human health and environment hazard due to airborne radioisotopes.…”

Section: Introductionmentioning

confidence: 99%

Airborne Radioactivity in Hot Lab of Nuclear Medicine

2017

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In this study, identification and measurement of gamma emitting radionuclides contaminant in air inside the hot lab at the Institute of Nuclear Medicine have been carried out. Air particulate collection has been performed by suction of indoor air through filter paper using Staplex air sampler. The radioactivities of Pb-212, Pb-214, Ac-228, Bi-214, K-40, I-131 and Tc-99m captured by the filter paper were assessed using gamma-ray spectrometry.

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Nuclear medicine: workplace monitoring and internal occupational exposure during a ventilation/perfusion single-photon emission tomography

Martínez

Baciu

Artigues

et al. 2019

Radiat Environ Biophys

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Assessment of Activity Concentration and Effective Doses from Bioassay Sample of Occupational Workers in NINMAS, Bangladesh

Cited by 5 publications

References 3 publications

Individual Monitoring of Internal Exposure for Nuclear Medicine Workers in NINMAS through In-Vitro Bioassay Techniques

Individual Monitoring of Internal Exposure for Nuclear Medicine Workers in NINMAS through In-Vitro Bioassay Techniques

Airborne Radioactivity in Hot Lab of Nuclear Medicine

Nuclear medicine: workplace monitoring and internal occupational exposure during a ventilation/perfusion single-photon emission tomography

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