scholarly journals Committed Effective Doses Received by Occupational Workers Handling Radioisotopes (131I and 99mTc) at INMAS, as Assessed from Urine-Samples

2020 ◽  
Vol 68 (2) ◽  
pp. 161-165
Author(s):  
Yeasin Noor ◽  
Jannatul Ferdous ◽  
Naureen Ahsan ◽  
Abdus Sattar Mollah
Keyword(s):  
Nuclear Medicine ◽  
Urine Samples ◽  
Radiological Protection ◽  
Dose Limit ◽  
Annual Dose ◽  
Potential Health ◽  
Medical College ◽  
High Purity Germanium ◽  
Effective Doses

This study estimates the potential health risks attributed to the internal contamination of occupational workers at the Institute of Nuclear Medicine and Allied Sciences (INMAS) located at Dhaka Medical College and Hospital, Dhaka, during nuclear medicine practices involving the radionuclides 131I and 99mTc, using in vitro methods from urine samples. A total of 55 urine samples from 6 occupational workers are collected over a period of about 11 months. These samples are analyzed using a High Purity Germanium (HPGe) detector coupled with a multichannel analyzer (MCA). The radioactivity of the isotopes present in each urine sample is measured based on the detector efficiency, and the committed effective dose due to each intake is calculated from this activity. The average annual doses of individual workers found in this study range from 4.57 × 10-5 mSv to 9.72 × 10-3 mSv. Although these doses are considerably below the International Commission on Radiological Protection (ICRP) recommended annual dose limit of 20 mSv, efforts to abide by the ALARA principle should continue. Dhaka Univ. J. Sci. 68(2): 161-165, 2020 (July)

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

2021 ◽  
Vol 22 (2) ◽  
pp. 125-129
Author(s):  
Mahadee Hasan Shubho ◽  
Md Mahidul Haque Prodhan ◽  
Ferdoushi Begum ◽  
Md Hossain Sahadath ◽  
Md Zakir Hossain ◽  
...  
Keyword(s):  
Nuclear Medicine ◽  
Urine Samples ◽  
Internal Exposure ◽  
Nuclear Facilities ◽  
Internal Radiation ◽  
Annual Dose ◽  
Radiation Workers ◽  
Minimum Detection Level ◽  
Effective Doses

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

scholarly journals Effective dose in medicine

2020 ◽  
Vol 49 (1_suppl) ◽  
pp. 126-140
Author(s):  
C.J. Martin
Keyword(s):  
Nuclear Medicine ◽  
Effective Dose ◽  
Imaging Techniques ◽  
Radiological Protection ◽  
Medical Procedures ◽  
Patient Referral ◽  
Similar Dose ◽  
Effective Doses ◽  
Public Exposure ◽  
Made In

The International Commission on Radiological Protection (ICRP) developed effective dose as a quantity related to risk for occupational and public exposure. There was a need for a similar dose quantity linked to risk for making everyday decisions relating to medical procedures. Coefficients were developed to enable the calculation of doses to organs and tissues, and effective doses for procedures in nuclear medicine and radiology during the 1980s and 1990s. Effective dose has provided a valuable tool that is now used in the establishment of guidelines for patient referral and justification of procedures, choice of appropriate imaging techniques, and providing dose data on potential exposure of volunteers for research studies, all of which require the benefits from the procedure to be weighed against the risks. However, the approximations made in the derivation of effective dose are often forgotten, and the uncertainties in calculations of risks are discussed. An ICRP report on protection dose quantities has been prepared that provides more information on the application of effective dose, and concludes that effective dose can be used as an approximate measure of possible risk. A discussion of the way in which it should be used is given here, with applications for which it is considered suitable. Approaches to the evaluation of risk and methods for conveying information on risk are also discussed.

ASSESSMENT OF NATURAL RADIONUCLIDES LEVELS IN DRINKING WATER FROM OGUN STATE, NIGERIA

2016 ◽  
Vol 78 (6-7) ◽  
Author(s):  
Usikalu M. R. ◽  
Olawole C. O. ◽  
Joel E. S.
Keyword(s):  
Water Samples ◽  
Background Radiation ◽  
Natural Radionuclides ◽  
Age Groups ◽  
Radiological Protection ◽  
Ogun State ◽  
Naturally Occurring ◽  
High Purity Germanium ◽  
Naturally Occurring Radionuclides ◽  
Effective Doses

Naturally occurring radionuclides levels of 238U, 232Th and 40K were investigated in the water samples collected at different boreholes in all the local government of Ogun State using high-purity germanium (HPGe) detector (Canberra Industries Inc.). The activity concentrations measured from the water samples ranged from 0.06 to 1.37 Bq l-1 for 238U, 0.15 to 0.52 Bq l-1 for 232Th and 1.35 to 12.74 Bq l-1 for 40K. The measured activities concentrations for 238U, 232Th and 40K along with their ingested dose conversion factors were used to estimate the annual effective doses in accordance with International Commission on Radiological Protection (ICRP) based on age groups 0 -1y, 1 – 2y, 2 – 7y, 7 – 12y, 12 – 17y and >17y for water consumption. The total annual effective doses calculated varied from 0.004 to 0.517, 0.002 to 0.092, 0.001 to 0.078, 0.001 to 0.076, 0.024 to 0.110 and 0.002 to 0.117 for the age groups accordingly. The physiochemical results showed that 85% of the water was acidic as they have pH less than 6.5 and 65 % of them exceeded the copper concentration recommended limit. It revealed that consumption of the water is safe from natural background radiation for all groups except 0-1 y as the annual effective dose obtained for this group exceeded the average world limit (0.12). The study therefore, suggests that Ogun State populace should use less of these water samples for babies between the age 0-1 year.

scholarly journals Internal Radiation Monitoring of Occupational Staff in Nuclear Medicine Facility

2013 ◽  
Vol 5 (1) ◽  
pp. 63-70 ◽  
Author(s):  
MJ Ferdous ◽  
Z Alam ◽  
RK Khan ◽  
SM Iqubal ◽  
A Islam ◽  
...  
Keyword(s):  
Nuclear Medicine ◽  
Medical Physics ◽  
Ventilation System ◽  
Working Environment ◽  
Urine Samples ◽  
Internal Exposure ◽  
Fume Hood ◽  
Effective Doses ◽  
Potential Risks ◽  
Dose Coefficients

Unsealed radioactive sources used in Nuclear Medicine Centers, to diagnose and treat patients, pose significant risks of internal exposure to the occupational staff. This work intends to evaluate the potential risks of internal contamination of occupational staff in Nuclear Medicine facilities. 49 urine samples of 19 occupational staff working in the two busiest nuclear medicine centres, namely Institute of Nuclear Medicine and Ultrasound (INMU) and Centre of Nuclear Medicine and Ultrasound (CNMU) Dhaka, were collected to perform this study. The concentrations of 99mTc and 131I in urine samples were measured using a High Purity Germanium (HPGe) detector. The radioactivity of 99mTc and 131I were found to be 8.58±0.03 Bql-1 to 314±1.92 Bql-1 and from 6.47±0.03 Bql-1 to 283±0.27 Bql-1 respectively. The effective doses of occupational staff have also been calculated using the radioactivity concentration and the dose coefficients. Due to the highest (314 Bql-1) and the lowest (8.58Bql-1) concentration of 99mTc, the effective doses were 14.7 ?Sv and 0.402?Sv, on the other hand for the highest (283 Bql-1) and the lowest (6.47 Bql-1) concentration of 131I, the effective doses were 5.58 ?Sv and 0.12 ?Sv. These values are within limits, however to avoid inhalation and contamination of 131I and 99mTc proper working environment should be established with suitable ventilation system, fume hood, mask, etc. DOI: http://dx.doi.org/10.3329/bjmp.v5i1.14670 Bangladesh Journal of Medical Physics Vol.5 No.1 2012 63-70

scholarly journals GAMOS DICOM Simulation on Occupational EL Dose due to 99mTc and 131I Exposures in Nuclear Medicine Departments

2019 ◽  
Vol 30 (1) ◽  
pp. 65-78
Author(s):  
Abdulmalek Rajkhan Abdulmalek Rajkhan
Keyword(s):  
Nuclear Medicine ◽  
Radiation Dose ◽  
Atomic Bomb ◽  
Epidemiological Studies ◽  
Radioactive Material ◽  
Radiation Hazard ◽  
Dose Limit ◽  
Dicom Image ◽  
Annual Dose ◽  
Atomic Bomb Survivors

Radiation induced cataracts is a disease that is common amongst radiation exposed staff. About 30 percent of retired occupational radiation workers developed eye lens (EL) cataracts. Epidemiological studies on radiation therapy patients, occupational workers, and atomic bomb survivors show that 0.5 Gy of acute or fractioned radiation dose to EL causes one or both lens to cloud. The annual EL dose limit drawn by the International Commission for Radiation Protection (ICRP) was 150 mSv and was changed in 2012 to 20 mSv averaged over 5 years, with no single year exceeding 50 mSv. The limited number of researche done in Nuclear Medicine (NM) clinics with the Hp(3) dosimeters suggest that the annual EL dose from three procedures is measured to be between 4.5 and 9 mSv (i.e. dispensing, preparing and administering). These procedures are performed when the radioactive materials are in closed shielded containers or behind a barrier. Common radioactive material handled by occupational workers in NM clinics are 99mTc and 131I. They pose less radiation hazard to workers EL in the three procedures when they are behind shielded containers. Moreover, once the radioactive material is administered into patients, they become open sources and pose more radiation hazard to workers. The Hp(3) dosimeter is a new uncommon dosimeter. Many radiation facilities use the Hp(0.07) and Hp(10) dosimeters coupled with many conditions and conversion factors to find approximate results. Therefore, simulations are performed to find the EL dose. However, some simulations are performed with little flexibility in simulation geometry, others utilize low-quality phantoms or present the simulation results in terms of fluxes or energy ranges. In the present study, the NM worker EL dose is simulated by utilizing a high-resolution Digital Imagning Communication in Medicine (DICOM) image in GEANT4 Archeticture for Medical Oriented Simulation (GAMOS). A water cylinder homogenously filled by radioactive material, representing the administered patient, was created in the simulation. The worker exposure scenario was simulated by placing the cylinder in three different directions and five different distances with respect to the DICOM image. The results of the simulation reveal that the highest occupational EL radiation dose is received from the anterior-posterior direction, followed by the lateral, and the posterior-anterior directions. The results of the conservative simulated scenario reveal that the worker EL dose is exposed to three tenths of the annual dose limit after 110 131I patients, or 300 99mTc patients.

scholarly journals Hand monitoring in nuclear medicine departments in Croatia - first results

2020 ◽  
Vol 35 (1) ◽  
pp. 82-86
Author(s):  
Marija Suric-Mihic ◽  
Robert Bernat ◽  
Jerko Sisko ◽  
Maja Vojnic-Kortmis ◽  
Luka Pavelic ◽  
...  
Keyword(s):  
Nuclear Medicine ◽  
Radiation Protection ◽  
Medical Staff ◽  
Monitoring Programme ◽  
Dose Limit ◽  
Annual Dose ◽  
First Results ◽  
Personal Dosimetry ◽  
Radioactive Sources ◽  
One Year

Individual hand monitoring for workers who manipulate unsealed radioactive sources in nuclear medicine is a necessity and the results can serve as the base for optimization processes. We performed an analysis of individual hand doses for medical staff preparing and applying radiopharmaceuticals (99mTc, 123I, 201Tl, 131I, or 125I) in three Croatian clinical hospitals, for a period of one year since extremity monitoring became legally mandatory in Croatia. The majority of annual hand doses for workers were below or slightly above 150 mSv per year with only a few workers exceeding the annual dose limit of 500 mSv. The analysis confirmed that the radiation protection expert's role in an individual monitoring programme and personal dosimetry is crucial in order to achieve the optimal radiation protection of workers.

scholarly journals Internal exposure in nuclear medicine: application of IAEA criteria to determine the need for internal monitoring

2008 ◽  
Vol 51 (spe) ◽  
pp. 103-107 ◽  
Author(s):  
Bernardo Maranhão Dantas ◽  
Eder Augusto de Lucena ◽  
Ana Letícia Almeida Dantas
Keyword(s):  
Nuclear Medicine ◽  
International Atomic Energy Agency ◽  
Monitoring Program ◽  
Atomic Energy ◽  
Internal Exposure ◽  
Radiological Protection ◽  
Energy Agency ◽  
Radiological Safety ◽  
Effective Doses ◽  
Medicine Application

The manipulation of unsealed sources in nuclear medicine poses significant risks of internal exposure to the staff. According to the International Atomic Energy Agency, the radiological protection program should include an evaluation of such risks and an individual monitoring plan, assuring acceptable radiological safety conditions in the workplace. The IAEA Safety Guide RS-G-1.2 recommends that occupational monitoring should be implemented whenever it is likely that committed effective doses from annual intakes of radionuclides would exceed 1 mSv. It also suggests a mathematical criterion to determine the need to implement internal monitoring. This paper presents a simulation of the IAEA criteria applied to commonly used radionuclides in nuclear medicine, taking into consideration usual manipulated activities and handling conditions. It is concluded that the manipulation of 131I for therapy presents the higher risk of internal exposure to the workers, requiring the implementation of an internal monitoring program by the Nuclear Medicine Centers.

scholarly journals Occupational radiation exposures for medical workers in Pakistan – An overview

2020 ◽  
Vol 26 (1) ◽  
pp. 45-53
Author(s):  
Misbah Ahmad ◽  
Iftkhar Ahmad ◽  
Aakif Ullah Khan ◽  
Amin Ali Khan ◽  
Kamran Ali Shah ◽  
...  
Keyword(s):  
Occupational Exposure ◽  
Whole Body ◽  
Radiation Doses ◽  
Dose Limit ◽  
Annual Dose ◽  
Occupationally Exposed ◽  
Effective Doses ◽  
Personal Dosimetry ◽  
Occupational Radiation ◽  
Dosimetry Data

AbstractThe imperative use of ionizing radiation in medicine causes the inevitable occupational exposure of the medical workers during the course of routine duties. The magnitude of health risk due to such radiation exposures has been described in terms of occupational radiation doses. In this context, it is obligatory to monitor, measure and document the radiation dose of occupationally exposed medical workers. This study aims to review the whole-body occupational radiation exposures of medical workers in Pakistan. Specifically, online literature published during 2000-2018 was reviewed for the occupational radiation exposures of Pakistani medical workers. Analysis of the extracted personal dosimetry data revealed that the total number of monitored medical occupational workers was 26046. The range of total cumulative and annual average effective doses was 94-15785 Person-mSv and 0.66-7.37 mSv, respectively. A significant number of the workers (25477; ~98%) received an annual dose below 5 mSv, while only 18 workers received an occupational exposure exceeding the annual dose limit of 20 mSv. It is expected that this study will provide a useful reference for evaluating and improving radiation protection and safety policies in the country.

Establishment and application of diagnostic reference levels for nuclear medicine procedures in Germany

2004 ◽  
Vol 43 (03) ◽  
pp. 79-84 ◽  
Author(s):  
V. Minkov ◽  
G. Brix ◽  
D. Noßke
Keyword(s):  
Nuclear Medicine ◽  
The Body ◽  
Radiological Protection ◽  
Diagnostic Reference Levels ◽  
Reference Levels ◽  
Current Standard ◽  
Standard Equipment ◽  
Effective Doses ◽  
Clinical Conditions ◽  
The Eu

SummaryDiagnostic reference levels (DRL) were introduced in Germany by a publication in the Bundesanzeiger Nr. 143 from August 5, 2003. Thereby a recommendation of the International Commission on Radiological Protection (ICRP) from 1996 and a demand by the EU Guideline 97/43/EURATOM from 1997 is converted into national law. Aim of this paper is to acquaint with and to justify the determined DRL as well as to provide information on the practical use of the concept of the DRL. Material and method: DRL were established by experts on the basis of a national survey conducted in hospitals and private practices as well as of national and international recommendations and published by the Federal Office for Radiation Protection. Besides the data basis the dosimetric principles are described for the estimation of the effective doses of the various examinations. Results: DRL were established for 10 frequent and dose-relevant examinations constituting more than 80% of all nuclear medicine examinations currently performed in Germany. For some examinations two different DRL were given to take into account clinical conditions. For paediatric examinations fractions of the activities to be administered to adults are given dependent on the body weight. Discussion: The published DRL are in agreement with the majority of national and international recommendations and with the present practice of nuclear medicine examinations in Germany. They are related to average activities for groups of patients with standard sizes and, moreover, to typical examinations with current standard equipment. It is planned to check and to reconsider the DRL about every 2-3 years.

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