PUBLIC EXPOSURE TO EXTERNAL GAMMA RADIATION ON A MINE LANDFORM COVERED BY LOW URANIUM GRADE WASTE ROCK

2019 ◽  
Vol 188 (1) ◽  
pp. 123-128
Author(s):  
Che Doering
Keyword(s):  
Gamma Radiation ◽  
Dose Rate ◽  
Annual Effective Dose ◽  
Waste Rock ◽  
Uranium Mine ◽  
Mining Sites ◽  
The Public ◽  
Order Of Magnitude ◽  
Public Exposure ◽  
General Guidance

Abstract Public exposure to external gamma radiation on the waste-rock-covered-8.5-km2-planned final landform from rehabilitation of the Ranger uranium mine was assessed. The average above-background dose rate from external gamma radiation on the planned final landform was determined to be 6.0 × 10−3 mSv d−1. This dose rate was one order of magnitude higher than that for inhalation of radon progeny and two orders of magnitude higher than that for inhalation of radionuclides in dust on the final landform. The above-background annual effective dose to the public from external gamma radiation when the envisioned land use by Aboriginal traditional owners was averaged over the entire 79 km2 Ranger Project Area was about 4.1 × 10−2 mSv. The results of this study may provide general guidance to sites elsewhere on the relative importance of the external gamma pathway and assist in the development or assessment of rehabilitation plans for uranium mining sites.

scholarly journals Monitoring of220Rn Concentrations in Buildings of Kufa Technical Institute, Iraq

2015 ◽  
Vol 2015 ◽  
pp. 1-5 ◽  
Author(s):  
Ali Abid Abojassim Al-Hamidawi
Keyword(s):  
Dose Rate ◽  
Half Life ◽  
Annual Effective Dose ◽  
Measuring System ◽  
Technical Institute ◽  
The Public ◽  
Effective Doses ◽  
Public Exposure ◽  
Effective Dose Rate ◽  
Annual Effective Dose Rate

This paper presents the measurements of thoron and the progeny in fifteen buildings in Kufa Technical Institute, Iraq, from June 2015 to April 2015 using RAD-7 detectors. Also, annual effective dose rate was calculated in all buildings under study. The thoron concentration varies from05.35±0.58 Bq/m3to53.50±1.82 Bq/m3with an average18.39±4.18 Bq/m3. The concentration of thoron daughters was found to vary from 0.14 mWL to 1.44 mWL with an average0.53±0.11 mWL. The annual effective doses due to thoron mainly vary from 0.042 mSv/y to 0.81 mSv/y with an average0.20±0.06 mSv/y. The preliminary results in this study indicate that they may be suitable for evaluating the indoor220Rn and its progeny concentrations whenever the public exposure to220Rn and its progeny is taken into account. During this survey, the continuous difficulty in measuring thoron was also pointed out, due to its short half-life and faults in the measuring system.

scholarly journals Health Risk Implications of Terrestrial Gamma Radiation Dose Rate in Central Jakarta, Indonesia: Short Communications

2017 ◽  
Vol 9 (12) ◽  
pp. 19
Author(s):  
Nursama Heru Apriantoro ◽  
Muzilman Muslim ◽  
Dadong Iskandar ◽  
. Purwantiningsih ◽  
Witri Mulyani ◽  
...  
Keyword(s):  
Radiation Dose ◽  
Gamma Radiation ◽  
Dose Rate ◽  
Annual Effective Dose ◽  
Rate Measurement ◽  
Radiation Dose Rate ◽  
Average Value ◽  
Effective Dose Rate ◽  
Gamma Radiation Dose ◽  
Annual Effective Dose Rate

Terrestrial gamma radiation dose (TGRD) rate measurement has been conducted around downtown region of Central Jakarta Indonesia. The real time count data was taken 1 m above the ground in eight sub district locations by using a portable gamma Surveymeter of Exploranium GR-135 Plus Model. The reading position was detemined using  Garmin GPSMAP 62s. The average value of TGRD rate of  (47.76 ± 18.24) nSv h-1 ranged from 6.40 nSv h-1 to 120.90 nSv-1, it is higher than Indonesia. The annual effective dose rate of 0.058 mSv. Its  contributes to fatal cancer risk of about  3.22 x 10-5 per year for each individual in Central Jakarta. For the subdistrict TGRD rate value was variated, however all the result is not high enough to cause for alarm.

scholarly journals Real-Time Environmental Gamma Radiation Dose Rate Measurement around Major Nuclear and Radiological Facilities in Bangladesh

2018 ◽  
Vol 6 (03) ◽  
Author(s):  
Sidratul Moontaha ◽  
Dr. Mohammad Sohelur Rahman ◽  
Dr. Md. Shafiqul Islam ◽  
Selina Yeasmin
Keyword(s):  
Radiation Dose ◽  
Gamma Radiation ◽  
Effective Dose ◽  
Dose Rate ◽  
Real Time ◽  
Annual Effective Dose ◽  
Radiation Monitoring ◽  
Monitoring Device ◽  
Dose Rates ◽  
Gamma Radiation Dose

Background: In this study, outdoor environmental gamma radiation dose rates were measured at area of Shahbag Thana under Dhaka city and Atomic Energy Research Establishment (AERE) Campus at Savar. Aim of the study: This kind of study is required to detect the presence of natural and artificial radionuclides (if any) releasing from nuclear and radiological facilities in the country or from neighbouring countries. Materials and Methods: The measurement was performed using a real-time portable radiation monitoring device from August-November 2017. The real-time portable radiation monitoring device was placed on tripod at 1 meter above the ground and data acquisition time for each monitoring point (MP) was 1 hour. Total 34 MP were selected around major nuclear and radiological facilities in Bangladesh for collection of dose rate due to gamma-ray. The MPs were marked-out using Global Positioning System (GPS) navigation. The GPS reading of the sampling locations were varied from E90º23'40.08" to E90º24'32.82" and from N23º44'58.62" to N23º43'26.58" for Shahbag Thana and from E90º16'26.58" to E90º16'50.52" and from N23º57'12.96" to N23º57'6.12" for AERE Campus, Savar. Results: The measured dose rates due to natural radionuclides were ranged from 0.105 ± 0.036056 μSv.h-1 to 0.208065 ± 0.106377μSv.h-1 with an average of 0.141568 ± 0.046995 μSv.h-1. The annual effective dose to the population from outdoor environmental gamma radiation was varied from 0.128772 ± 0.044218 mSv to 0.25517 ± 0.130461 mSv and the mean was found to be 0.17362± 0.057635 mSv. This value is lower than some countries like India, China, Sweden, Italy and Czech Republic; and higher than Canada, Mexico, Indonesia, Korea, Turkey, Finland, Spain and some other countries. Conclusion: From this study, it was observed that there is no burden of population exposure due to man-made sources. Therefore, it can be concluded that adequate safety and radiation protection of nuclear & radiological facilities had been ensured which is required for minimizing of unnecessary exposure to populations from man-made sources. The estimated mean annual effective dose found in this study is not expected to contribute significant additional hazard from the radiological health point of view.

ASSESSMENT OF INDOOR GAMMA RADIATION AND DETERMINATION OF EXCESS LIFETIME CANCER RISK IN TEHRAN IN WINTER AND SPRING 2017

2018 ◽  
Vol 184 (2) ◽  
pp. 148-154 ◽  
Author(s):  
Marjan Hashemi ◽  
Leila Akhoondi ◽  
Mohammad Hossien Saghi ◽  
Akbar Eslami
Keyword(s):  
Cancer Risk ◽  
Gamma Radiation ◽  
Dose Rate ◽  
Annual Effective Dose ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Lifetime Cancer Risk ◽  
Average Value ◽  
Excess Lifetime Cancer Risk

Abstract Natural radiation is a feature of the environment in which we live. One of the contributions of human exposure to ionizing radiation due to natural sources arises from gamma radiation. Therefore, present study was aimed to evaluate and map indoor gamma dose rate in Tehran. The corresponding annual effective dose (AED) and excess lifetime cancer risk (ELCR) were also calculated. All measurements were performed by a Geiger Muller detector in 43 dwellings in Tehran. The average indoor gamma dose rate in Tehran was appointed as 343.2 nGy/h. AED and ELCR were calculated as 2.4 mSv and 10.3 × 10−3, respectively. The evaluated indoor gamma dose rate and calculated AEDs and lifetime cancer risk were found higher than the world average value.

scholarly journals Real-Time Environmental Gamma Dose Rates Measurement and Evaluation of Annual Effective Dose to population of Shahbag Thana, Dhaka, Bangladesh

2018 ◽  
Vol 6 (04) ◽  
Author(s):  
Shamsad Tazmin ◽  
Dr. Mohammad Sohelur Rahman ◽  
Selina Yeasmin ◽  
Dr. M. Habibul Ahsan ◽  
Md. Mahfuzzaman
Keyword(s):  
Gamma Radiation ◽  
Effective Dose ◽  
Dose Rate ◽  
Annual Effective Dose ◽  
Natural Radionuclides ◽  
Outdoor Environment ◽  
Acquisition Time ◽  
Population Exposure ◽  
Monitoring Point ◽  
Dose Rates

Background: In this study, environmental gamma radiation dose rates were measured in the area of Shahbag Thana under Dhaka city, Bangladesh. Aim of the study: This kind of study is required to detect the presence of natural and artificial radionuclides (if any) releasing from nuclear facilities in the country or from neighbouring countries. Materials and Method: The measurement was performed using a digital portable Gamma-Scout detector. The digital portable Gamma-Scout detector was placed at 1 meter above the ground on tripod and data acquisition time for each monitoring point (MP) was 1 hour. Total 27 MPs were selected for collection of gamma-ray dose rate in the outdoor environment of Shahbag Thana. The measurements were performed during light day from January to September 2017. The MPs were marked-out using Global Positioning System (GPS) navigation. The GP Sreading of the sampling locations were varied from E: 90˚23'32.94" to E: 90˚24'31.32" and from N:23˚44'19.38" to N: 23˚43'24.3". Results: The measured dose rates due to natural radionuclides were ranged from 0.085 ± 0.0245µSv.h-1 to 0.190526 ± 0.081886 µSv.h-1 with an average of 0.145265 ± 0.025192 µSv.h-1.The annual effective dose to the population from outdoor environmental gamma radiation was varied from0.104244 ± 0.030041 mSv  to 0.233661085 ± 0.100425 mSv. The range of dose rate and annual effective dosedue to outdoor environmental gamma radiation is lower than some countries like India, Sweden, China, CzechRepublic, Italy and higher than Canada, Turkey, Indonesia, Belgium, Albania, New Zealand and some other counties. Conclusion: From this study, it was observed that there is no burden of population exposure due to man-made sources. Therefore, it can be concluded that adequate safety and radiation protection of radiological facilities had been ensured which is required for minimizing of unnecessary exposure to populations from man-made sources. The estimated mean annual effective dose found in this study is not expected to contribute significant additional hazard from the radiological health point of view.

Radiation exposure in the environment of patients after application of radiopharmaceuticals

2008 ◽  
Vol 47 (06) ◽  
pp. 267-274 ◽  
Author(s):  
F. Boldt ◽  
C. Kobe ◽  
W. Eschner ◽  
H. Schicha ◽  
F. Sudbrock
Keyword(s):  
Nuclear Medicine ◽  
Radiation Exposure ◽  
Radioactive Source ◽  
Time Intervals ◽  
The Public ◽  
Dose Rates ◽  
Diagnostic Nuclear Medicine ◽  
Photon Dose ◽  
Order Of Magnitude ◽  
Study Dose

Summary Aim: After application of radiopharmaceuticals the patient becomes a radioactive source which leads to radiation exposure in the proximity. The photon dose rates after administration of different radiopharmaceuticals used in diagnostic nuclear medicine were measured at several distances and different time intervals. These data are of importance for estimating the exposure of technologists and members of the public. Patients, method: In this study dose rates were measured for 67 patients after application of the following radiopharmaceuticals: 99mTc-HDP as well as 99mTcpertechnetate, 18F-fluorodeoxyglucose, 111In-Octreotid and Zevalin® and 123I-mIBG in addition to 123I-NaI. The dose rates were measured immediately following application at six different distances to the patient. After two hours the measurements were repeated and – whenever possible – after 24 hours and seven days. Results: Immediately following application the highest dose rates were below 1 mSv / h: with a maximum at 780 μSv/h for 18F (370 MBq), 250 μSv/h for 99mTc (700 MBq), 150 μSv/h for 111In (185 MBq) and 132 μSv/ h for 123I (370 MBq). At a distance of 0.5 m the values decrease significantly by an order of magnitude. Two hours after application the values are diminished to 1/3 (99mTc, 18F), to nearly ½ (123I) but remain in the same order of magnitude for the longer-lived 111In radiopharmaceuticals. Conclusion: For greater distances the doses remain below the limits outlined in the national legislation.

scholarly journals The OpenRadiation project: monitoring radioactivity in the environment by and for the citizens

2019 ◽  
Vol 54 (4) ◽  
pp. 241-246 ◽  
Author(s):  
J.F. Bottollier-Depois ◽  
E. Allain ◽  
G. Baumont ◽  
N. Berthelot ◽  
G. Darley ◽  
...  
Keyword(s):  
Emergency Management ◽  
Dose Rate ◽  
Scientific Community ◽  
Emergency Situation ◽  
Collaborative Approach ◽  
Fukushima Accident ◽  
The Public ◽  
Collaborative Tools ◽  
Share Data ◽  
Project Monitoring

After the Fukushima accident, initiatives emerged offering the public the possibility to realise measurements of the radioactivity in the environment with various devices and to share data and experiences through collaborative tools. The objective of the OpenRadiation project is to offer the public the opportunity to perform measurements of the radioactivity using connected dosimeters on smartphones. The challenge is to operate such a system on a sustainable basis in normal situations and in order to be useful in an emergency situation. In normal situations, this project is based on a collaborative approach including pedagogical activities. In case of emergency situation, data from the field will be available in “real time” providing an opportunity for the emergency management and the communication with the public. The practical objectives are to develop i) a website centralising measurements using various dosimeters, providing dose rate maps with raw and filtered data and offering dedicated areas for specific projects and exchanges about data and ii) a dosimetric app using a connected dosimeter. This project is conducted within a partnership between organisms’ representative of the scientific community and associations to create links with the public.

MEASUREMENT OF RADON CONCENTRATION IN SOIL SAMPLES OF MAZAT AND KAFI-HABU MINING SITES, PLATEAU, NIGERIA

2021 ◽  
Vol 4 (4) ◽  
pp. 295-301
Author(s):  
Abubakar Sadiq Aliyu ◽  
Aminu Ismaila ◽  
A. M. Na'Inna ◽  
Ahmed Mohammed
Keyword(s):  
Dose Rate ◽  
Radon Concentration ◽  
Background Radiation ◽  
Average Concentration ◽  
Soil Samples ◽  
Radiological Protection ◽  
Sampling Point ◽  
Monitoring And Control ◽  
Tailing Dump ◽  
Mining Sites

Radon and its short-lived progenies contributed significantly to natural background radiation. Long-term exposure to such radiation increases the probability of lung cancer to persons. To assess the radiological hazards associated with the inhalation of radon gas from ore dust in Mazat and Kafi-Habu mining sites of Plateau, Nigeria, 12 soil samples from an abandoned tailing dump ground were collected and analysed for radon using RAD-7 electronic detector. The dose rate of each sampling point was directly measured using RADOS RDS -120 portable survey meter. The results gave a mean radon concentration ranging from 771.51 ± 21.9 Bq/m3 to 5666.13 ± 28.8 Bq/m3 with 3451.13 ± 42.9 Bq/m3as the average value for all measurements. The average concentration of measurements from Mazat and Kafi-Habu is 3671.6 ± 41.2 Bq/m3 and 3010.16 ± 46.5 Bq/m3 respectively. The average values obtained from the analysis are significantly higher than the upper limit of 300 Bq/m3 set by the International Commission on Radiological Protection (ICRP) suggesting quick remediation on the host communities. The geometrical mean value of Dose Rate (DR) and Annual Effective Dose Equivalent (AEDE) were 870 nGy/hr and 1.04 mSv/yr respectively. Again, these values are above the global average limits of 59 nGy/hr and 1 mSv/yr. The result indicates that miners working in those sites and dwellers of the study areas are at higher risk of getting exposed to radon and need to employ protective measures. This work is useful in monitoring and control of radon level for the on-site workers and the 

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