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.

Radiation doses deriving from patients treated with 166Ho-ferric hydroxide

2003 ◽  
Vol 42 (06) ◽  
pp. 251-254
Author(s):  
C. Pirich ◽  
P. John ◽  
S. Ofluoglu ◽  
H. Sinzinger ◽  
E. Havlik ◽  
...  
Keyword(s):  
Radiation Exposure ◽  
Radiation Protection ◽  
Ferric Hydroxide ◽  
Medical Personnel ◽  
Whole Body ◽  
Radiation Doses ◽  
Annual Dose ◽  
Tracer Injection ◽  
Dose Rates ◽  
Protection Devices

Summary Aim: To estimate radiation doses deriving from patients treated with 166Ho ferric hydroxide. Methods: For radiation synoviorthesis about 900 ± 100 MBq 166Ho ferric hydroxide was injected into the knee joint of 16 patients. To estimate the radiation exposure of persons in the neighbourhood of the patients measurements of the dose rates were performed at 0.5 m, 1 m and 2 m distance of the treated joint 10 min after tracer injection. Measurements were carried out with and without radiation protection devices of the syringe. Results: The initial values of the dose rate were 11.9 μSv/h at 0.5 m, 3.5 μSv/h at 1 m and 1 μSv/h at 2 m distance, respectively. The whole body doses were 2.9 μSv for the physician and 4.6 μSv for the technologist. The finger doses for the technologist and the physician were ranging from 65 to 111 μSv. After discharge at home other persons might receive 118 μSv. Conclusion: Our results, under very strict assumptions, clearly demonstrate that the calculated radiation exposure to medical and non medical personnel is well below the maximum annual dose limit. The use of any additional radiation protection device as syringe shielding does not significantly lower radiation exposure.

RADIATION DOSES TO THE EYE LENS AND FOREHEAD OF INTERVENTIONAL RADIOLOGISTS: HOW HIGH AND ON WHAT GROUNDS?

2020 ◽  
Vol 190 (2) ◽  
pp. 150-157
Author(s):  
M Psarras ◽  
A Ploussi ◽  
E Carinou ◽  
E Brountzos ◽  
S C Spiliopoulos ◽  
...  
Keyword(s):  
Eye Lens ◽  
Radiation Doses ◽  
Dose Limit ◽  
Annual Dose ◽  
Occupational Dose ◽  
Primary Operator ◽  
Reliable Assessment ◽  
Left And Right ◽  
The Right ◽  
Percutaneous Transluminal

Abstract The aim of the study was to measure and evaluate the radiation dose to the eye lens and forehead of interventional radiologists (IRs). The study included 96 procedures (lower-limb percutaneous transluminal angioplasties, embolisations/chemoembolisations and vertebroplasties) performed by 6 IRs. A set of seven thermoluminescence dosemeters was allocated to each physician. The highest dose per procedure was found for the left eye lens of the primary operator in vertebroplasties (1576 μSv). Left and right eye doses were linearly correlated to left and right forehead doses, respectively. A workload-based estimation of the annual dose to participating IRs revealed that the occupational dose limit for the eye lens can be easily exceeded. The left eye dose of ΙRs must be routinely monitored on a personalised basis. Τhe left eye dose measurement provides a reliable assessment of the ipsilateral forehead dose, along with valid estimations for the right eye and right forehead doses.

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.

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 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)

Calculation of the radiation doses occurring in the human body for inadvertent ingestion of soil and other soil exposure pathways

2003 ◽  
Vol 81 (11) ◽  
pp. 1303-1307
Author(s):  
F Öner ◽  
N T Okumuşoğlu
Keyword(s):  
Human Body ◽  
Absorbed Dose ◽  
Whole Body ◽  
Radiation Doses ◽  
Dose Calculations ◽  
Bone Surface ◽  
Soil Ingestion ◽  
Red Marrow ◽  
Soil Exposure ◽  
Effective Doses

We estimate the radiation doses in the human body, in the Gudalore region in India, following the inadvertent ingestion of soil and exposure to other soil pathways by measuring 232Th, 238U, and 40K. We estimate the equivalent dose in eleven different organs and the absorbed dose calculations for the whole body. The annual effective doses are calculated, the lowest is in Kariyasolai at 7.8 × 10–3 mSv whereas the highest is in Ponnur at 8.9 × 10–2 mSv. In all regions, the lowest equivalent doses through inadvertent soil ingestion are calculated in the kidney and thyroid whereas the highest doses are in the red marrow and on the bone surface. PACS No.: 87.50.–a

scholarly journals Fifteen years of occupational exposure monitoring in the Federation of Bosnia and Herzegovina

2018 ◽  
Vol 33 (4) ◽  
pp. 395-405
Author(s):  
Begzada Basic ◽  
Adnan Beganovic ◽  
Maja Gazdic-Santic ◽  
Amra Skopljak-Beganovic ◽  
Davorin Samek
Keyword(s):  
Bosnia And Herzegovina ◽  
Dose Limit ◽  
Annual Dose ◽  
Exposure Monitoring ◽  
Positron Emission ◽  
Medical Institutions ◽  
Radiation Sources ◽  
Radiation Workers ◽  
Personal Dosimetry ◽  
To Come

The personal dosimetry in Bosnia and Herzegovina started in 1960. After a brief interruption in 1990s, the dosimetry service resumed in 1999. Until 2013, the Radiation Protection Centre of the Institute of Public Health of Federation of Bosnia and Herzegovina has been the only institution in the country that could provide this service. In 2013, this Center covered more than 70 % (1,485) of all radiation workers in the country. They mostly worked in medical institutions (1,417 or 95.4 %), while others are exposed to radiation sources in industry and veterinary radiology. From 1999 to 2013, the majority of annual doses were less than 1 mSv (96.2 %). There are no registered cases of exceeding the annual dose limit (20 mSv). The results analysis shows the reduction of individual doses in last five years. Newly adopted practices in medicine, such as the positron emission tomography, could cause the increase of doses in the years to come.

scholarly journals Effective doses to staff and dose rates emitted from patients undergoing positron emission tomography utilizing 18F- Fluorodeoxglucose

2015 ◽  
Vol 2 (1) ◽  
pp. 1-14 ◽  
Author(s):  
Carl Petter Skaar Kulseng ◽  
Jon Christoffer Sandstrøm
Keyword(s):  
Effective Dose ◽  
Dose Rate ◽  
The Body ◽  
Whole Body ◽  
Average Dose ◽  
Body Parts ◽  
Dose Rates ◽  
Effective Doses ◽  
Occupational Radiation ◽  
Different Parts

IntroductionThe purpose of this two--folded quantitative study was to determine the radiation doses received by staff during 2014 at the PET--department at St. Olavs Hospital in Trondheim, Norway. Although studies show that the doses received by staff performing such examinations are far beneath the limits set by regulation, there was a need to determine how much radiation the staff at this clinic actually was exposed to. We investigated in detail both dose rates emitted by 18 F from different parts of the body to the surroundings along with effective doses to staff during 2014.MethodPart one - Dose rates from 20 patients undergoing FDG-PET/CT--scans were measured with dosimeter RadEye B20 (Thermo Scientific, USA) from five measuring points at three different stages of a standard whole body PET-scan utilizing 18 F-FDG.Part two - Effective doses to five radiographers and four bioengineers were registered daily during 2014. The effective dose measurements were done daily by the staff with personal dosimeter RadEye EPD MK2+ (Thermo Scientific, USA). The dosimeter was worn at chest level. The automatic injector Medrad Intego (Bayer, Germany) administrate the radioactive doses.ResultsPart one - Dose rates emitted from different parts of patients show significant differences. The highest dose rate was measured from the head and sternum of the patients. The knees emit the least dose rate of all body parts and was considerably lower from one meterdistance.Part two - The average effective doses were far below the recommended limits for occupational radiation. The total average effective dose per member of staff was 0.13 mSv in 2014 and the daily average dose was 4.91 μSv/day.ConclusionPart one - 18 F-FDG showed irregular distribution in the body, the lowest dose rates originated from the lower extremities and reflects the metabolism of glucose in the body at rest.Part two - We found significant differences between staff working with both CT and the radioisotope injection compared to the staff working solely with one of these tasks. Nevertheless, all effective- doses were safely within the guideline limits for occupational radiation.

scholarly journals Internal dose assessment of 148Gd using isotope ratios of gamma-emitting 146Gd or 153Gd in accidently released spallation target particles

2020 ◽  
Vol 10 (1) ◽  
Author(s):  
C. Rääf ◽  
V. Barkauskas ◽  
K. Eriksson Stenström ◽  
C. Bernhardsson ◽  
H. B. L. Pettersson
Keyword(s):  
Operation Time ◽  
Isotope Ratios ◽  
Dose Assessment ◽  
Sensitive Indicator ◽  
Whole Body ◽  
Internal Dose ◽  
Tungsten Target ◽  
Alpha Emitter ◽  
Spallation Source ◽  
Effective Doses

AbstractThe pure alpha emitter 148Gd may have a significant radiological impact in terms of internal dose to exposed humans in case of accidental releases from a spallation source using a tungsten target, such as the one to be used in the European Spallation Source (ESS). In this work we aim to present an approach to indirectly estimate the whole-body burden of 148Gd and the associated committed effective dose in exposed humans, by means of high-resolution gamma spectrometry of the gamma-emitting radiogadolinium isotopes 146Gd and 153Gd that are accompanied by 148Gd generated from the operation of the tungsten target. Theoretical minimum detectable whole-body activity (MDA) and associated internal doses from 148Gd are calculated using a combination of existing biokinetic models and recent computer simulation studies on the generated isotope ratios of 146Gd/148Gd and 153Gd/148Gd in the ESS target. Of the two gamma-emitting gadolinium isotopes, 146Gd is initially the most sensitive indicator of the presence of 148Gd if whole-body counting is performed within a month after the release, using the twin photo peaks of 146Gd centered at 115.4 keV (MDA < 1 Bq for ingested 148Gd, and < 25 Bq for inhaled 148Gd). The corresponding minimum detectable committed effective doses will be less than 1 µSv for ingested 148Gd, but substantially higher for inhaled 148Gd (up to 0.3 mSv), depending on operation time of the target prior to the release. However, a few months after an atmospheric release, 153Gd becomes a much more sensitive indicator of body burdens of 148Gd, with a minimum detectable committed effective doses ranging from 18 to 77 µSv for chronic ingestion and between 0.65 to 2.7 mSv for acute inhalation in connection to the release. The main issue with this indirect method for 148Gd internal dose estimation, is whether the primary photon peaks from 146 and 153Gd can be detected undisturbed. Preliminary simulations show that nuclides such as 182Ta may potentially create perturbations that could impair this evaluation method, and which impact needs to be further studied in future safety assessments of accidental target releases.

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