Estimation of annual occupational effective doses from external ionising radiation at medical institutions in Kenya

2011 ◽  
Vol 15 (4) ◽  
pp. 116 ◽  
Author(s):  
Geoffrey K Korir ◽  
Jeska S Wambani ◽  
Ian K. Korir
Keyword(s):  
Effective Dose ◽  
Annual Effective Dose ◽  
Radiation Characteristic ◽  
Thermoluminescent Dosimeters ◽  
Medical Sector ◽  
Medical Institutions ◽  
Radiation Workers ◽  
One Year ◽  
Effects Of Radiation ◽  
Occupational Radiation

This study details the distribution and trends of doses from occupational radiation exposure among radiation workers from participating medical institutions in Kenya, where monthly dose measurements were collected for a period of one year (January to December 2007) using thermoluminescent dosimeters. A total of 367 medical radiation workers were monitored, comprising 27% radiologists, 2% oncologists, 4% dentists, 5% physicists, 45% technologists, 4% nurses, 3% film processor technicians, 4% auxiliary staff, and 5% radiology office staff. The average annual effective dose for all subjects ranged from 1.19 to 2.52 mSv. Among these workers, technologists received the largest annual effective dose. The study forms the initiation stage of wider, comprehensive and more frequent monitoring of occupational radiation exposures and long-term investigations into its accumulation patterns, which could form the basis of future records on the detrimental effects of radiation, characteristic of workers in the medical sector, and other co-factors in a developing country such as Kenya.

scholarly journals Risk Assessment of Occupational Exposure of Workers Engaged in Radiation Practice without Monitoring Devices

2019 ◽  
pp. 1-6
Author(s):  
Akinlade Bidemi I. ◽  
Akisanya Daniel F. ◽  
Badmus Biodun S.
Keyword(s):  
Effective Dose ◽  
Radiation Protection ◽  
Annual Effective Dose ◽  
Recommended Dose ◽  
Thermoluminescent Dosimeters ◽  
Ogun State ◽  
Occupational Dose ◽  
Radiation Workers ◽  
Risk Of Cancer ◽  
Monitoring Devices

Objective: This study was carried out to evaluate occupational dose of personnel, engaged in radiation work without wearing monitoring device, at five diagnostic centres in Abeokuta, Ogun State metropolis, namely, Rainbow, New image, Bethel, Akinolugbade and Abiolad.  Materials and Methods: Thermoluminescent dosimeters (TLDs) obtained from Radiation Protection Services, Lagos State University (LASU), Ojo were used for dose measurements. LASU is accredited by the Nigerian Nuclear Regulatory Authority (NNRA) to provide radiation monitoring services. The TLDs were distributed to each of the centre for personnel and area (control and supervised) monitoring. The period of exposure of the TLDs was three months. The exposed TLDs were returned to LASU for processing. The effective dose received by personnel per quarter was extrapolated to annual effective dose to make comparison with the International Commission on Radiation Protection (ICRP) recommended dose limit. The stochastic effect of the measured dose was also estimated.  Results: Annual effective dose received by all personnel ranged from 1.16 - 2.54 mSv. While the highest value was obtained by personnel at Bethel diagnostic centre, the lowest value was obtained at Akinolugbade. The risk of cancer associated with these values, estimated for a million population, was 112 and 61 at Bethel and Akinolugbade respectively. Conclusion: This study showed that the annual effective doses to personnel at these centres were below the ICRP recommended dose of 20 mSv per annum. However, the Managements of these diagnostic centres should provide monitoring devices for their radiation workers in line with NNRA authorization requirements.

Radiation Safety Standards and Basic Health Rules for Radiation Safety: Proposal on the Development of New Versions

2019 ◽  
Vol 64 (5) ◽  
pp. 15-19
Author(s):  
А. Симаков ◽  
A. Simakov ◽  
Ю. Абрамов ◽  
Yu. Abramov
Keyword(s):  
Effective Dose ◽  
Radiation Safety ◽  
Specific Activity ◽  
Annual Effective Dose ◽  
Uranium Isotopes ◽  
Time Interval ◽  
Solid Materials ◽  
Safety Standards ◽  
Basic Health ◽  
One Year

The objective of this work is to enhance national Radiation safety standards (NRB) and Basic Health Rules for Radiation Safety (OSPORB).  This article discusses proposals how to amend new versions of the fundamental regulatory documents – national NRB and OSPORB as regards the interpretation of the term “limit of the annual effective dose of manmade individual exposure” and the health physics limiting the content of artificial radionuclides in solid materials for their unrestricted use. In current Radiation Safety Standards, NRB-99/2009 (paragraph 3.1.5.), in contrast to the Federal Law of 09.01.1996 No 3-FZ “On the Public Radiation Protection” and provisions of draft International Basic Safety Standards, annual effective dose means gross effective dose of external and internal exposure, received for the calendar year. The article describes the situation where the doses of a conditional worker do not exceed the dose limits in a single calendar year, i.e. < 50 mSv, however, for any arbitrarily taken time interval equal to one year, the annual dose limit of 50 mSv is repeatedly exceeded. Therefore, the following amendment is proposed to be made in new version of the NRB: “Annual effective dose means the sum of the effective external dose received for any arbitrarily taken time interval equal to one year and the ambient effective internal dose due to the intake of radionuclides in the body over the same period”. In current Basic Health Rules for Radiation Safety, OSPORB 99/2010, Annex 3 “The Specific Activities of Artificial Radionuclides, at which Unrestricted Use of Materials is Permitted” does not include the uranium isotopes 234U, 235U and 238U; this contradicts paragraph 5.2.10 of OSPORB-99/2010, according to which these isotopes should be attributed to manmade radiation sources.  The article justifies the expediency of establishing the upper value of the specific activity of 1 Bq/g for the main uranium radionuclides in solid materials in case of their unlimited use. The supplement of Appendix 3 is proposed to the new version of the OSPORB with uranium isotopes 234U, 235U, 238U, setting the standard for their specific activity of 1 Bq/g in solid materials for unlimited use.

Occupational radiation doses among nurses working in several medical departments in Saudi Arabia: a five-year national study

2021 ◽  
Author(s):  
N. Shubayr ◽  
Y. Alashban
Keyword(s):  
Saudi Arabia ◽  
Effective Dose ◽  
National Study ◽  
Radiation Doses ◽  
Catheterization Laboratory ◽  
Thermoluminescent Dosimeters ◽  
Cardiac Catheterization Laboratory ◽  
Occupational Dose ◽  
Effective Doses ◽  
Occupational Radiation

There has been an increase in the numbers of diagnostic and therapeutic procedures, which, in turn, has increased the occupational radiation doses delivered to healthcare practitioners. The aim of this study is to estimate a baseline for the occupational effective doses for five consecutive years (2016–2020) among nurses working in several medical departments in Saudi Arabia. A total of 3249 nurses were monitored from 2016 to 2020. Occupational effective doses were estimated using thermoluminescent dosimeters (TLD-100 chip) made of lithium fluoride (Li natural) LiF:Mg.Ti materials. An analysis of the dosimetry data revealed that the overall mean annual effective dose (MAED), range of the effective doses and the mean collective effective dose for nurses in selected departments during the study period were 0.85 mSv, 0.06–13.07 mSv and 46.51 man-mSv, respectively. The MAEDs for nurses were obtained from various departments, including the operating room (OR; 0.81 mSv), general X-ray (0.90 mSv), cardiac catheterization laboratory (cath-lab; 0.97 mSv), endoscopy (0.79 mSv), computed tomography (CT; 0.77 mSv), fluoroscopy (0.81 mSv), dentistry (0.92 mSv), angiography (0.91 mSv), nuclear medicine (1.01 mSv), urology (0.68 mSv), radiotherapy (0.67 mSv) and mammography (0.77 mSv). The MAED for cath-lab nurses was significantly higher than that for OR, CT and endoscopy nurses. The occupational doses among nurses in Saudi Arabia were below the recommended dose limit of 20 mSv. However, to further reduce the occupational dose, we recommend training and continuing education in radiation protection for nurses involved in radiological procedures.

scholarly journals Estimation of indoor radiological hazard on worker and public health in atomic energy centre Dhaka campus, Bangladesh

2021 ◽  
Author(s):  
Md. Rafiqul Islam ◽  
Mohammad Sohelur Rahman ◽  
Khondokar Nazmus Sakib ◽  
Md. Mohiuddin Tasnim ◽  
Selina Yeasmin
Keyword(s):  
Public Health ◽  
Cancer Risk ◽  
Effective Dose ◽  
Annual Effective Dose ◽  
Life Time ◽  
Radiation Monitoring ◽  
Atomic Energy ◽  
Radiological Protection ◽  
Radiological Hazard ◽  
Thermoluminescent Dosimeters

Introduction: Radiation gives tremendous benefit to mankind but unnecessary radiation may pose harm to worker and public. The purpose of the study is to continuous indoor radiation monitoring of Atomic Energy Centre Dhaka (AECD) campus to minimize the radiological risk on worker and public health in and around the campus. Materials and methods: Continuous indoor radiation monitoring was conducted in the AECD campus from November 2018-April 2019 using the Thermoluminescent dosimeters. The excess life-time cancer risk on worker and public health were estimated based on the continuous indoor radiation monitoring data. Results: The annual effective doses to the worker and public from indoor radiation were ranged from 0.28±0.11 mSv to 0.67±0.25 mSv and the mean was found to be 0.43±0.10 mSv. The excess life-time cancer risk (ELCR) on the radiation worker & public health were estimated based on the annual effective dose and ranged from 1.13 Χ 10-3 to 2.65 Χ 10-3 with an average of 1.72 Χ 10-3.The average annual effective dose and ELCR on worker and public health were lower than those of the worldwide average values. Conclusion: The radiological hazard on worker and public health in and around the AECD campus is not significant because those values are lower than the recommended values of the international commission on radiological protection. Monitoring of these indoor places would help in keeping a record of safe working practices during the handling of the radioactive substances and radiation generating equipments in a radiological facility.

ASSESSMENT OF ANNUAL EFFECTIVE DOSE FROM EXPOSURE TO NATURAL RADIOACTIVITY SOURCES IN A CASE–CONTROL STUDY IN BIHOR COUNTY, ROMANIA

2018 ◽  
Vol 185 (1) ◽  
pp. 7-16 ◽  
Author(s):  
T Dicu ◽  
B D Burghele ◽  
A Cucoș ◽  
R Mishra ◽  
B K Sapra
Keyword(s):  
Effective Dose ◽  
Annual Effective Dose ◽  
Indoor Radon ◽  
Control Sample ◽  
Track Detector ◽  
Radon Activity ◽  
Thermoluminescent Dosimeters ◽  
Activity Concentrations ◽  
Two Samples ◽  
Significant Difference

Abstract The purpose of the article is to evaluate the annual effective dose for 80 women divided into two samples; one sample located in the former uranium Băiţa-Ştei area, hereinafter referred to as case sample, respectively for a control sample, located in the same county, but exposed in most cases to indoor radon activity concentrations <300 Bq m−3. In this regard, the homemade ‘RaThoGamma’ kit was used, which contained two thermoluminescent dosimeters, a CR-39 track detector (RSKS) for indoor radon activity concentration, two CR-39 track detectors (Radtrak2®/ Radtrak2T®) for radon and thoron activity concentrations as well as Direct Radon Progeny Sensors/Direct Thoron Progeny Sensors for measuring time-averaged radon and thoron progenies concentrations. In addition, a total of 80 water samples were collected in order to evaluate the ingestion dose due to radon and radium activity concentrations in drinking water. The maximum total annual effective dose in the control sample was 14.1 mSv, while in the case sample the maximum annual effective dose was 60.5 mSv. This difference is mainly due to radon progenies inhalation. Other pathways did not show a statistically significant difference between the two samples, showing a minor contribution to the annual effective dose.

scholarly journals Occupational Exposure to Ionizing Radiation in Interventional Cardiology Practices in Bangladesh during 2010-2014

2016 ◽  
Vol 3 (2) ◽  
pp. 63-68
Author(s):  
Mohammad Sohelur Rahman ◽  
Aleya Begum ◽  
Md. Rezaul Karim Khan ◽  
Md. Ashraful Hoque ◽  
M. M. Mahfuz Siraz
Keyword(s):  
Occupational Exposure ◽  
Ionizing Radiation ◽  
Effective Dose ◽  
Radiation Protection ◽  
Annual Effective Dose ◽  
Interventional Cardiology ◽  
Dhaka City ◽  
Thermoluminescent Dosimeters ◽  
Status And Trends ◽  
The Status

Objective: The objective of this study is to assess, analyze and discuss the occupational exposure to ionizing radiation in interventional cardiology practices in Bangladesh for the last 5-year periods. Method: Each year, about 100 workers working in interventional cardiology departments of big hospitals in Dhaka City were monitored using Harshaw Thermoluminescent Dosimeters (TLDs) for quarterly basis. The effective dose of the occupational workers were measured using Two Harshaw TLD Readers (one is manual TLD reader, model-4500, and another is automatic TLD reader, model 6600 plus). Finding: The average annual effective dose (about 80 % workers) in interventional cardiology practices were <2mSv in 2010-2014 and no monitored workers were found to have received an occupational exposure >50 mSv in a single year or >100 mSv in a 5 year period. The status and trends in occupational exposure demonstrate that radiation protection conditions at the majority of the workplace were adequate. Despite that, further optimization is necessary due to large variations observed in the maximum individual doses over the 5-year periods.  

EVALUATION OF OCCUPATIONAL RADIATION EXPOSURE IN A RADIO-DIAGNOSTIC FACILITY IN KATSINA- NIGERIA

2020 ◽  
Vol 4 (2) ◽  
pp. 722-729
Author(s):  
Usman Sani ◽  
Bashir Gide Muhammad ◽  
Dimas Skam Joseph ◽  
D. Z. Joseph
Keyword(s):  
Radiation Dose ◽  
Radiation Exposure ◽  
Short Exposure ◽  
Skin Dose ◽  
Continuous Training ◽  
Short Exposure Time ◽  
Occupational Dose ◽  
Dose Limits ◽  
Radiation Workers ◽  
Occupational Radiation

Poor implementation of quality assurance programs in the radiation industry has been a major setback in our locality. Several studies revealed that occupational workers are exposed to many potential hazards of ionizing radiation during radio-diagnostic procedures, yet radiation workers are often not monitored. This study aims to evaluate the occupational exposure of the radiation workers in Federal Medical Centre Katsina, and to compare the exposure with recommended occupational radiation dose limits. The quarterly readings of 20 thermo-luminescent dosimeters (TLDs') used by the radiation workers from January to December, 2019 were collected from the facility's radiation monitoring archive, and subsequently assessed and analyzed. The results indicate that the average annual equivalent dose per occupational worker range from 0.74 to 1.20 mSv and 1.28 to 2.21 mSv for skin surface and deep skin dose, measured at 10 mm and 0.07 mm tissue depth respectively. The occupational dose was within the recommended national and international limits of 5 mSv per annum or an average of 20 mSv in 5 years. Therefore, there was no significant radiation exposure to all the occupational workers in the study area. Though, the occupational radiation dose is within recommended limit, this does not eliminate stochastic effect of radiation. The study recommended that the occupational workers should adhere and strictly comply with the principles of radiation protection which includes distance, short exposure time, shielding and proper monitoring of dose limits. Furthermore, continuous training of the radiation workers is advised.

The Measurements of Natural Radioactivity, (Radon and Gamma concentrations), around the old fertilizer factory in Basrah/Iraq

2015 ◽  
Vol 7 (1) ◽  
pp. 1324-1335
Author(s):  
Jabbar H. Jebur
Keyword(s):  
Effective Dose ◽  
Radon Concentration ◽  
Gamma Ray ◽  
Annual Effective Dose ◽  
Track Detector ◽  
Exhalation Rate ◽  
Hazard Indices ◽  
Radium Equivalent ◽  
Passive Technique ◽  
Radium Activity

Radon concentration, exhalation rate, annual effective dose, radium activity, thorium, uranium potassium and radium equivalent have been measured in the present investigation for soil in the area around the old fertilizer factory in southern of Basrah Governorate. The measurements based on CR39 track detector for passive method, RAD7 for active method and NaI(Tl) for gamma concentration measurements. Average values for radon concentration in soil were 112.04±10.76 Bq/m3 using passive technique and 104.56±6.05 Bq/m3 using RAD7. From the result of the passive technique, area and mass exhalation rates and the annual effective dose were calculated. Gamma ray spectroscopy for the soil samples were performed and found that the average concentrations of 226Ra, 232Th and 40K were 50.89 Bq/kg, 21.74 Bq/kg and 640.4 Bq/kg respectively. Gamma ray hazard indices were calculated and found they are within the world average.

Radiation exposure of the staff at the therapeutic and diagnostic nuclear medicine department

2008 ◽  
Vol 47 (04) ◽  
pp. 175-177 ◽  
Author(s):  
J. Dolezal
Keyword(s):  
Nuclear Medicine ◽  
Radiation Exposure ◽  
Effective Dose ◽  
Radiation Protection ◽  
Annual Effective Dose ◽  
Protection Measures ◽  
Professional Groups ◽  
Personal Dosimetry ◽  
The Mean ◽  
Administered Activity

SummaryAim: To assess a radiation exposure and the quality of radiation protection concerning a nuclear medicine staff at our department as a six-year retrospective study. Therapeutic radionuclides such as 131I, 153Sm, 186Re, 32P, 90Y and diagnostic ones as a 99mTc, 201Tl, 67Ga, 111In were used. Material, method: The effective dose was evaluated in the period of 2001–2006 for nuclear medicine physicians (n = 5), technologists (n = 9) and radiopharmacists (n = 2). A personnel film dosimeter and thermoluminescent ring dosimeter for measuring (1-month periods) the personal dose equivalent Hp(10) and Hp(0,07) were used by nuclear medicine workers. The wearing of dosimeters was obligatory within the framework of a nationwide service for personal dosimetry. The total administered activity of all radionuclides during these six years at our department was 17,779 GBq (99mTc 14 708 GBq, 131I 2490 GBq, others 581 GBq). The administered activity of 99mTc was similar, but the administered activity of 131I in 2006 increased by 200%, as compared with the year 2001. Results: The mean and one standard deviation (SD) of the personal annual effective dose (mSv) for nuclear medicine physicians was 1.9 ± 0.6, 1.8 ± 0.8, 1.2 ± 0.8, 1.4 ± 0.8, 1.3 ± 0.6, 0.8 ± 0.4 and for nuclear medicine technologists was 1.9 ± 0.8, 1.7 ± 1.4, 1.0 ± 1.0, 1.1 ± 1.2, 0.9 ± 0.4 and 0.7 ± 0.2 in 2001, 2002, 2003, 2004, 2005 and 2006, respectively. The mean (n = 2, estimate of SD makes little sense) of the personal annual effective dose (mSv) for radiopharmacists was 3.2, 1.8, 0.6, 1.3, 0.6 and 0.3. Although the administered activity of 131I increased, the mean personal effective dose per year decreased during the six years. Conclusion: In all three professional groups of nuclear medicine workers a decreasing radiation exposure was found, although the administered activity of 131I increased during this six-year period. Our observations suggest successful radiation protection measures at our department.

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