Annual effective dose assessment for 226Ra and 228Ra due to consumption of foodstuffs by Tehran city residents

2006 ◽  
Vol 3 (2/3) ◽  
pp. 192
Author(s):  
Maryam Asefi ◽  
Ali Asghar Fathivand ◽  
Jamshid Amidi
Keyword(s):  
Effective Dose ◽  
Annual Effective Dose ◽  
Dose Assessment

scholarly journals Radon Activity Concentrations in Natural Hot Spring Water: Dose Assessment and Health Perspective

2021 ◽  
Vol 18 (3) ◽  
pp. 920
Author(s):  
Eka Djatnika Nugraha ◽  
Masahiro Hosoda ◽  
June Mellawati ◽  
Untara Untara ◽  
Ilsa Rosianna ◽  
...  
Keyword(s):  
Public Health ◽  
Effective Dose ◽  
Radiation Protection ◽  
Water Samples ◽  
Hot Springs ◽  
Hot Spring ◽  
Annual Effective Dose ◽  
Spring Water ◽  
Dose Assessment ◽  
West Java

The world community has long used natural hot springs for tourist and medicinal purposes. In Indonesia, the province of West Java, which is naturally surrounded by volcanoes, is the main destination for hot spring tourism. This paper is the first report on radon measurements in tourism natural hot spring water in Indonesia as part of radiation protection for public health. The purpose of this paper is to study the contribution of radon doses from natural hot spring water and thereby facilitate radiation protection for public health. A total of 18 water samples were measured with an electrostatic collection type radon monitor (RAD7, Durridge Co., USA). The concentration of radon in natural hot spring water samples in the West Java region, Indonesia ranges from 0.26 to 31 Bq L−1. An estimate of the annual effective dose in the natural hot spring water area ranges from 0.51 to 0.71 mSv with a mean of 0.60 mSv for workers. Meanwhile, the annual effective dose for the public ranges from 0.10 to 0.14 mSv with an average of 0.12 mSv. This value is within the range of the average committed effective dose from inhalation and terrestrial radiation for the general public, 1.7 mSv annually.

MEASUREMENT OF THE ACTIVITY CONCENTRATIONS OF GAMMA EMITTING RADIONUCLIDES IN TOOTHPASTE SAMPLES AND ASSESSMENT OF THE CORRESPONDING ANNUAL EFFECTIVE DOSES

2021 ◽  
Author(s):  
Anas M Ababneh ◽  
Qutad M Samarah
Keyword(s):  
Effective Dose ◽  
Oral Hygiene ◽  
Annual Effective Dose ◽  
Daily Basis ◽  
Dose Assessment ◽  
Accidental Ingestion ◽  
Activity Concentrations ◽  
Effective Doses

Abstract It is inevitable that we are exposed to radiation daily from various sources and products that we consume on daily basis. The use of toothpaste for oral hygiene is one of the most common daily practices by humans and yet very little data are available regarding its radiation content. In this work, we investigated the concentrations of gamma emitting radionuclides in toothpaste samples consumed in Jordan. 40K and 226Ra were detected in almost one-third of the samples, whereas 228Ra was detected in nearly half of them. The corresponding activity concentrations in the detected samples were in the ranges of 68.7–154.2, 4.6–14.1 and 1.3–10.0 Bq/kg, respectively. Dose assessment of accidental ingestion of toothpaste for children and adults was made, and its contribution to the annual effective dose was found to be very minimal with maximum doses of ~2.9 and 1.3 μSv for children and adults, respectively.

scholarly journals Natural Radioactivity and dose Assessment in Sand and Sediment Samples from Kuakata Beach, Bangladesh

2016 ◽  
Vol 40 (1) ◽  
pp. 45-55 ◽  
Author(s):  
Md Murad Ahmed ◽  
Suranjan Kumar Das ◽  
Sariful ◽  
Selina Yeasmin
Keyword(s):  
Effective Dose ◽  
Annual Effective Dose ◽  
Dose Assessment ◽  
Absorbed Dose Rate ◽  
Radium Equivalent Activity ◽  
Mean Values ◽  
Sediment Samples ◽  
World Average ◽  
Average Value ◽  
Activity Concentrations

The activity concentrations of radionuclides and their respective annual effective dose rates produced by 226Ra, 232Th and 40K were measured by using high purity germanium (HPGe) detector of relative efficiency 20%. The activity concentrations of 226Ra, 232Th and 40K in the sand samples were found to vary from 22.83 ± 4.11 to 100.21 ± 2.39 BqKg-1, 68.76 ± 2.86 BqKg-1 to 297.37 ± 4.32 BqKg-1 and 75.87 ± 15.75 to 161.81 ± 19.90 BqKg-1 with mean values 48.76, 126.11 and 292.38 Bqkg-1, respectively. For sediment samples the corresponding radionuclides ranged between 12.11 ± 1.99 and 31.64 ± 1.64 BqKg-1, 18.94 ± 1.90 BqKg-1 and 71.11 ± 2.88 BqKg-1 and 182.73 ± 19.81 BqKg-1 and 345.77 ± 21.07 BqKg-1, with mean values 19.67, 32.13 and 243.38 Bqkg-1, respectively. The absorbed dose rate was estimated to the range from 30.50 to 242.93 nGyh-1 with an average value of 74.87 nGyh-1. The estimated outdoor annual effective dose varied between 0.22 and 1.79 mSv/year with a mean value of 0.55 mSv/year, which is higher than the world average for outdoor annual effective dose (0.07 mSv/year). The external hazard indices for the samples varied from 0.17 to 1.43 with the average value of 0.44, which is less than the unity. The average value of radium equivalent activity was estimated and found to be 161.40 BqKg-1 which is less than the acceptable limit of world average value of 370 BqKg-1.Journal of Bangladesh Academy of Sciences, Vol. 40, No. 1, 45-55, 2016

scholarly journals REVIEW OF METHODIC INSTRUCTIONS AND RECOMMENDATIONS FOR EVALUATION OF ANNUAL EFFECTIVE DOSE TO HUMAN BEING IN CASES OF LIVING AT RADIOACTIVE CONTAMINATED AREAS

2021 ◽  
pp. 57-69
Author(s):  
A. V. Toporova ◽  
Yu. V. Baklanova ◽  
Yu. G. Strilchuk ◽  
A. N. Shatrov
Keyword(s):  
Effective Dose ◽  
Annual Effective Dose ◽  
Dose Calculation ◽  
Test Site ◽  
Dose Assessment ◽  
Human Being ◽  
Calculation Methods ◽  
Artificial Radionuclides ◽  
Semipalatinsk Test Site ◽  
Basic Approaches

The proposed paper provides a review of recommendations, methodic instructions and software for evaluation of exposure doses to population domiciling radioactive contaminated territories. There is a review of dose calculation methods which are most common in neighbouring countries and beyond. The paper presents basic approaches, factors required for dose assessment with review of main pathways for artificial radionuclides intake. It addresses the need to develop methodic instructions and software for the cases of people living at Semipalatinsk test site area.

scholarly journals Age-dependent dose assessment of uranium intake from bottled water in Punjab state, India

2020 ◽  
Vol 20 (7) ◽  
pp. 2794-2803
Author(s):  
Vikas Duggal
Keyword(s):  
Effective Dose ◽  
Uranium Concentration ◽  
Annual Effective Dose ◽  
Age Groups ◽  
Dose Assessment ◽  
Radioactive Material ◽  
World Health ◽  
Human Consumption ◽  
Radiological Protection ◽  
Age Dependent

Abstract Uranium, both a radioactive material and a heavy metal, poses a health risk due to its radiological properties and chemical toxicity. In the present study, uranium concentration and relative age-dependent effective dose have been measured in 27 commercial brands of bottled waters collected randomly from different districts of Punjab, India. Uranium concentration varied from 0.19 to 9.29 μg l−1 with a mean value of 1.58 μg l−1, a standard deviation of 1.95 μg l−1 and a median of 0.82 μg l−1. Uranium concentrations in all the samples were found to be lower than the World Health Organization (WHO) and U.S. Environmental Protection Agency (USEPA) prescribed limit of 30 μg l−1 and AERB India proposed a radiological based limit of 60 μg l−1. Based on permissible limits, all the samples were suitable for human consumption. The annual effective dose was determined by taking the recommended water intake values of different age groups. The mean annual effective dose for all age groups was well within the International Commission on Radiological Protection (ICRP) recommended reference dose level of 1 mSv y−1. The highest dose was calculated for infants, which makes them the most crucial group of the population.

STUDY OF 222RN CONTINUOUS MONITORING TIME SERIES AND DOSE ASSESSMENT IN SIX EUROPEAN CAVES

2020 ◽  
Vol 191 (2) ◽  
pp. 233-237
Author(s):  
F Ambrosino ◽  
L Thinová ◽  
M Briestenský ◽  
C Sabbarese
Keyword(s):  
Effective Dose ◽  
Natural Ventilation ◽  
Annual Effective Dose ◽  
Working Hours ◽  
Health Impact ◽  
Dose Assessment ◽  
Radiological Protection ◽  
Radon Activity ◽  
Clastic Sediments ◽  
Effective Doses

Abstract The present work aims to assess the effective doses from long-term continual radon monitoring in six European caves (Slovenia, Slovakia and the Czech Republic), including influencing environmental factors. Caves are important radiation protection subjects because of elevated radon activity concentration (~kBq/m3), mostly due to the low natural ventilation. The sources of radon gas are most often underground rock layers and clastic sediments. The radon activity concentrations show seasonal variations, for which the outside temperature is the main driving force. The human health impact due to the radon inhalation in monitored caves was estimated through the annual effective dose, using the methodology provided by the International Commission on Radiological Protection (ICRP Publication 137). The annual effective dose could reach several tens of mSv, depending on the working hours spent in the underground.

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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