scholarly journals Assessment of background ionizing radiation dose levels in quarry sites located in Ebonyi State, Nigeria

2020 ◽  
Vol 24 (10) ◽  
pp. 1821-1826
Author(s):  
E.O. Echeweozo ◽  
F.O. Ugbede

The study presents a radiometric survey of Background Ionizing Radiation (BIR) dose levels in ten quarry sites located in Ebonyi State, Nigeria. In-situ BIR dose rate measurements, by means of nuclear radiation survey meter, at 1 m above ground level were carried out at the excavation section (ES) and quarrying section (QS) of the investigated quarry sites. The obtained results indicated dose rates ranging from from 0.14 to 0.18 μSv/h with mean of 0.15±0.01 μSv/h at the ES and 0.16 to 0.19 μSv/h with mean value of 0.18±0.01 μSv/h at the QS. While the values obtained at the QS are respectively higher than those measured at the ES, they are all higher than the worldwide average value of 84 nSv/h signifying BIR elevated environments. The estimated mean annual effective dose (AED) and excess lifetime cancer risk (ELCR) are 0.27±0.03 mSv/y and 0.94×10–3 respectively at the ES and 0.31±0.02 mSv/y and 1.07×10–3 at the QS. The obtained AED values for all the sites are well above the outdoor worldwide average value of 0.07 mSv/y but lower than the International Commission on Radiological Protection recommended permissible limits of 1.0 mSv/y for the general public. Generally, the BIR levels of the quarry sites are within acceptable limits and no immediate radiological health threat may be derived from the current levels. However, long-term health effects due to continuous exposure to low-level radiation doses may manifested in future over a lifetime exposure of 70 years as indicated by the ELCR values. Keywords: Background ionizing radiation, Dose rate, Annual effective dose, Quarry site, Ebonyi State

2021 ◽  
Vol 19 (12) ◽  
pp. 06-10
Author(s):  
Hussam Najem Abood ◽  
Ahmed Abbas Mohamed

Indoor radon/thoron concentration has been determined in some dwellings of Suq Alshouk district in Thiqar Governorate southern of Iraq, using LR-115 type II and CR-39 (SSNTDs). In this work the indoor radon/thoron concentration varies from (8-73) Bq m-3 for radon with an average 35±2Bq m-3, and ranges (1- 47) Bq m-3 for thoron with an average16±2Bq m-3. The average annual effective dose due to radon and thoron varies from 0.43-3.38m Sv y-1 with average value 1.43±0.11 mSv y-1.


2020 ◽  
Vol 12 (1) ◽  
pp. 1-4
Author(s):  
Nuraddeen Nasiru Garba ◽  
Rabiu Nasiru ◽  
Muniba Sufiyan ◽  
Abdullahi Muhammad Vatsa

Measurement of background radiation is of great interest for it provides useful information in monitoring environmental radioactivity. The aim of the present study is to provide information and generate database on the natural background radiation dose levels of densely populated Queen Amina Hall, Ahmadu Bello University, Zaria. The radiation dose (outdoor and indoor dose rate) were measured at 29 rooms (Block 1- 4) and their compounds using RADOS survey meter held at 1m above the ground. The measured radiation dose ranged 0.13 nGyh-1 to 0.43 nGyh-1 and 0.54 nGyh-1 to 1.72 nGyh1 for indoor and outdoor respectively. Some of the high values recorded could be attributed due to the contribution of cosmic radiation emanating from the atmosphere as well as the geological settings of the location as there is no any artificial contributing factor within the area. The annual effective doses within the study area was found to be 0.01 mSvy-1 throughout which is quit below the world average value of 0.87 mSvy-1 for natural sources. Keywords: Radiation dose, Annual effective dose, RADOS meter, Queen Amina


2020 ◽  
Vol 12 (1) ◽  
pp. 80-84
Author(s):  
S. Abdullahi ◽  
A.S. Ahmad ◽  
B. Abdulkadir ◽  
Y. Kabir ◽  
S. Mustapha ◽  
...  

Measurement of background radiation is of great interest for it provides useful information in monitoring environmental radioactivity. The aim of the present study is to provide information and generate database on the natural background radiation dose levels of densely populated Queen Amina Hall, Ahmadu Bello University, Zaria. The radiation dose (outdoor and indoor dose rate) were measured at 29 rooms (Block 1- 4) and their compounds using RADOS survey meter held at 1m above the ground. The measured radiation dose ranged 0.13 nGyh-1 to 0.43 nGyh-1 and 0.54 nGyh-1 to 1.72 nGyh-1 1 for indoor and outdoor respectively. Some of the high values recorded could be attributed due to the contribution of cosmic radiation emanating from the atmosphere as well as the geological settings of the location as there is no any artificial contributing factor within the area. The annual effective doses within the study area was found to be 0.01 mSvy-1 throughout which is quit below the world average value of 0.87 mSvy-1 for natural sources. Keywords: Radiation dose, Annual effective dose, RADOS meter, Queen Amina


Author(s):  
M. U. Audu ◽  
G. O. Avwiri ◽  
C. P. Ononugbo

Study of the terrestrial Background Ionizing Radiation levels of selected Oil Spill Communities of Delta State, Nigeria have been carried out using Digilert 200 and Radalert 100 nuclear radiation monitor and a geographical positioning system (Garmin GPSMAP 76S). The exposure rates of the five communities ranges from 0.016 to 0.030  at Jones Creek, 0.014 to 0.034  at Opuwade Community, 0.015 to 0.037   at Okpare community, 0.007 to 0.029  at OtuJeremi community and 0.011to 0.040  at Otor-Edo community. The obtained mean exposures rates were higher than ICRP standard limit of 0.013. The absorbed dose rates calculated ranged from 139.2 to 261 (Jones Creek), 121.8 to 259.8 nGyh-1 (Opuwade Community), 130.5 to 321.9 nGyh-1 (Okpare community), 60.9 to 252.3 nGyh-1 (OtuJeremi community) and 95.9 to 348 nGyh-1 (Otor-Edo community). The estimated annual effective dose equivalent varies from  0.21 to 0.40 , 0.19 to  0.45 , 0.20 to  0.49 , 0.09 to 0.39  and  0.15 to 0.53  for Jones Creek, Opuwade Community, Okpare community, Otu Jeremi community and Otor-Edo community respectively while the excess lifetime cancer risk calculated for Jones Creek varies from (0.75  to 1.40)  x 10-3, Opuwade community (0.65 to 1.59 )×, Okpare community (0.70 to 1.73 ) x , OtuJeremi community (0.33 to 1.35)× and Otor-Edo community (0.51 to 1.87)×. All the mean values of absorbed dose, annual effective dose and excess lifetime cancer risk exceeded their recommended safe values. The results obtained in this work may not constitute any immediate health risk to the residents of the selected oil spill communities but long term exposure in the area may lead to detrimental health risks.


2021 ◽  
Vol 8 (S1-Feb) ◽  
pp. 97-103
Author(s):  
Niranjan R S ◽  
Ningappa C ◽  
Nandakumar V ◽  
Harshavardhana C N

All individual living beings on the earth are exposed continuously to the radiations coming from terrestrial and extraterrestrial sources and also from their own bodies. The indoor and outdoor ambient gamma radiations are measured in and around Nuggihalli- Holenarasipura schist belts of Hassan district in Karnataka state. The measurements are carried out using the environment radiation dosimeter UR 705 which is a portable detector. Absorbed dose rate and annual effective dose rate are estimated by measuring the exposure rate. The total annual effective dose calculated from both indoor and outdoor varies from 0.68 to1.62 mSv.y-1 with an average value of 1.16 mSv.y-1. The calculated indoor and outdoor annual effective doses are found to be higher than the world average.


2017 ◽  
Vol 9 (12) ◽  
pp. 19
Author(s):  
Nursama Heru Apriantoro ◽  
Muzilman Muslim ◽  
Dadong Iskandar ◽  
. Purwantiningsih ◽  
Witri Mulyani ◽  
...  

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.


Author(s):  
Sidratul Moontaha ◽  
Dr. Mohammad Sohelur Rahman ◽  
Dr. Md. Shafiqul Islam ◽  
Selina Yeasmin

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.


Author(s):  
Bouchra Amaoui ◽  
Abdennasser El Kharras ◽  
Mohammed Aabid ◽  
Oum Keltoum Hakam ◽  
Abdelmajid Choukri ◽  
...  

Objective: This study aims to estimate the annual doses for personnel categories following their exposure to ionizing radiation during their occupation in the external radiotherapy department of the Center of Oncology and Hematology (COH) at Mohammed VI Hospital in Marrakech. Materials and Methods: Operational dosimeters PACK MGP DMC 3000 were used to measure the dose rates around the machines operating with ionizing radiation. In order to assess the reliability of the measurements made by these dosimeters, they were checked against measurements made at the same position by the Inspector detector. The annual effective dose was calculated by multiplying the average dose rate measured during a procedure by the overall treatment time throughout a year. Results: Regarding the reliability check of the measuring instrument, the recorded error is between 2 and 10% with an average of 7%. For personnel category A, the measured dose rate ranges from 0.066 to 0.083 µSv/h, with an average value of 0.075 µSv/h. For category B, it varies between 0.066 and 0.083 µSv, with an average value of 0.092 µSv/h. It is 0.074 µSv/h for category C. The annual dose for category A ranges from 0.089 to 0.113 mSv/year, with an average value of 0.101 mSv/year. For category B, it varies between 0.089 and 0.113 mSv/year, with an average value of 0.100 mSv/year. It is 0.100mSv/year for category C. Conclusion: The annual effective doses to personnel categories, assessed by this study, are very low compared to the regulatory standards set by the International Commission on Radiological Protection (ICRP). As a result, workers benefit from good radiation protection conditions within the Center of Oncology and Hematology at Mohammed VI Hospital in Marrakech.


Author(s):  
S. P. Gautam ◽  
A. Silwal ◽  
S. Acharya ◽  
B. Aryal

Measurement of outdoor natural background radiation doses at different locations of Pokhara city, Nepal was carried out using GCA-07W, Nuclear Regulatory Commission (NRC) certified Geiger Muller (GM) detector. From the measurements, the least value of background radiation dose rate was found to be 0.26 ± 0.08 μSv/hr for Mahendra Cave area, and the highest value of dose rate was found to be 0.65 ± 0.12 μSv/hr for Prithvi Narayan Campus. The average annual effective dose rate of Pokhara city was found to be 0.56 ± 0.12 mSv/yr ranging from 0.31 ± 0.09 mSv/yr to 0.80 ± 0.14 mSv/yr. The radiation levels in Pokhara, the most populated city of the western development region of Nepal, were found to be within the secure limit for areas of the normal background recommended by the International Commission on Radiological Protection (ICRP) (1 mSv/yr). Further, the current result was compared with the previous study of annual effective dose rate measured in Kathmandu city. Comparable value of the average annual effective dose rate in Pokhara and Kathmandu was obtained.


Author(s):  
D. O. Samson ◽  
A. F. Anazia

Measurement of radioactive contamination in some commonly consumed foodstuffs within the six area councils of Abuja, Nigeria was conducted in this study by means of a very sensitive and portable 3M/3-X Geiger Müller counter-based environmental radiation dosimeter. Eight different food samples were randomly selected in each of the sample locations making a total of 48 foodstuffs samples surveyed across the six area councils. The results obtained show that, the range of radiation dose levels in the analyzed samples varied from 0.01590.0001 to 0.34070.0002 μSvy-1 at Bwari; 0.14900.0001 to 0.39020.0002 μSvy-1 at AMAC; 0.00950.0001 to 0.02090.0001 μSvy-1 at Gwagwalada; 0.00570.0001 to 0.01330.0002  μSvy-1 at Kuje; 0.02740.0001 to 0.22710.0002 μSvy-1 at Abaji; Kwali was between 0.01820.0001 and 0.35030.0002 μSvy-1, and their corresponding arithmetic mean are 0.16900.0001 μSvy-1, 0.22560.0001 μSvy-1, 0.01330.0001 μSvy-1, 0.00880.0001 μSvy-1, 0.13600.0001 μSvy-1 and 0.12370.0001 μSvy-1, which gives estimated annual effective dose rates of 0.18850.0003 mSvy-1, 0.25760.0001 mSvy-1, 0.11700.0001 mSvy-1, 0.07710.0001 mSvy-1, 0.15530.0002 mSvy-1, and 0.14120.0001 mSvy-1 for Bwari, AMAC, Gwagwalada, Kuje, Abaji and Kwali area councils respectively. This finding reveals that the obtained values were sufficiently less than the maximum recommended global average exposure dose limit for environmental background (2.4 mSvy-1) and general public dose limit (1.0 mSvy-1). The radiation dose levels and dose rates associated with the intake of foodstuffs across the area councils are, therefore, relatively low and may not pose any immediate radiological health hazard to the populace, as deterministic radiation effects occur only in extreme cases.  


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