scholarly journals GIS MAPPING OF BIR LEVELS AROUND FOSSIL FUEL AND GAS DISPENSING STATIONS AND ASSESSMENT OF THEIR RADIOLOGICAL RISK IMPLICATIONS

2020 ◽  
Vol 4 (2) ◽  
pp. 54-62
Author(s):  
Agbalagba E. O. ◽  
Nenuwe O.N ◽  
Egarievwe S.U

The assessment of terrestrial background ionizing radiation levels within fossil fuel and gas dispensing environments to evaluate the radiological risk around Warri metropolis has been conducted using a digilert 200 Nuclear Radiation monitor meter and a GPS. The GIS monitoring of the BIR levels was carried out between September and December 2018 by delineating the city into eight zones using GIS mapping. The measured average exposure rates ranged from 0.006mRh-1(0.50 𝑚𝑆𝑣𝑦-1) to 0.026mRh-1(2.19𝑚𝑆𝑣𝑦-1) with an overall mean value of 0.015±0.004mRh-1 (1.26±0.32 𝑚𝑆𝑣𝑦-1). The estimated mean outdoor absorbed dose rate for the regions ranged from 116.60±40.38nGyh-1 in Jeddo region to 148.9±49.63nGyh-1 in PTI region and a mean of 129.82±32.98𝜂Gyh-1.The AEDE evaluated is 0.16±0.04 𝑚𝑆𝑣𝑦-1 while the ELCR value is 0.56±0.014µ𝑆𝑣𝑦-1. The estimated dose to organs testes receiving the highest organ dose of 0.10 𝑚𝑆𝑣𝑦-1 while the liver receives the lowest dose to organ of 0.06 𝑚𝑆𝑣𝑦-1. The GIS mapping of the examined facilities revealed that radiation levels in 38 of the 61 sampling locations (62.3%) exceeded the global ambient permissible level of 13.0 𝜇Rh-1 (1.0 𝑚𝑆𝑣𝑦-1) reported by UNSCEAR, therefore the measured values are adjudged high and the environment radiologically impaired. But, these may not cause any short- team health risk to the fuel/gas attendants and attendees in these stations. The obtained estimated excess lifetime cancer risk indicates low chances of contracting cancer and the radiation doses to the adult organs investigated is insignificant.

2020 ◽  
Vol 35 (2) ◽  
pp. 154-164
Author(s):  
Sreten Ilic ◽  
Tatjana Golubovic ◽  
Natasa Pajic ◽  
Mirjana Djurasevic ◽  
Aleksandar Kandic

This paper presents the results of analyses of radionuclide content in the samples of the surrounding soil and clayey material of ?Zbegovi? open-pit mine in Donje Crniljevo, Serbia. Samples from 78 sites were collected and prepared. The activity concentrations were determined for radionuclides: 238U, 232Th, 40K, 226Ra, and 137Cs. The mean values obtained are as follows: 23 Bqkg?1, 89 Bqkg?1, 372 Bqkg?1, 56 Bqkg?1, and 11 Bqkg?1, respectively. Concentrations of 238U, 40K, and 226Ra in the studied area do not deviate from the values obtained for the soil in Serbia. The concentration of 232Th in the studied area is slightly higher relative to average values for soil, and slightly lower compared to similar deposits of clayey material in the world. Measurements performed showed that the open-pit mine of clayey material is completely uncontaminated surface as far as 137Cs is concerned, while there are sites where measured 137Cs concentrations are significantly higher, which is due to topographic differences and inhomogeneous surface contamination of land after the Chernobyl accident. To assess the radiological risks in the observed area, the following indices were determined: absorbed dose rate, annual outdoor effective dose, absorbed dose for biota, excess lifetime cancer risk outdoors as well as external radiation hazard index. The mean value of the estimated absorbed dose rate in the given area amounts to 80.1 nGyh?1, and the annual outdoor effective dose ranges from 46.9 to 134 Sv. Absorbed dose rate for biota in the studied area is 1.31 10?4 Gyd?1. The mean excess lifetime cancer risk outdoors for the population is 3.8 10?4, and t he mean value of the external radiation hazard index obtained in this study is 0.48, which is consistent with the world average. A low dose of radiation will not pose a risk to the population and biota in the studied area.


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

A study of background ionizing radiation (BIR) levels to estimate organ dose rates and excess lifetime cancer risk in Unicem cement producing company, Calabar, Cross River state and Bua cement producing company, Okpella in Edo state have been carried out using Digilert 100 and Radalert-200 nuclear radiation monitor and a geographical positioning system (GPS) for GIS mapping of the area. The in-situ measurement of the exposure rate was between May, 2018 and June, 2019 at regular intervals. The average exposure rate of 0.023 mRh-1 was measured at Unicem, Calabar and 0.027 mRh-1 at Bua cement area, Okpella. The mean equivalent doses of 1.92 mSvy-1 and 2.29 mSvy-1 was recorded in Unicem and Bua Okpella respectively. The estimated mean outdoor absorbed dose rate value of 196.74 nGyh-1 in Unicem and its environment while in Bua cement industry, Okpella, the value of 234.9 nGyh-1 was obtained. The mean annual effective dose calculated was 0.24 and 0.29 mSvy-1 for Unicem and Bua Okpella respectively. The mean excess life time cancer risk recorded in the areas 0.72 x10-3 in Unicem area and 1.01 x10-3 in Bua cement environment. The calculated dose to organs showed that the testes have the highest organ dose of 0.74 mSvy-1 and 0.83 mSvy-1 for Unicem and Bua Okpella areas respectively while the liver has the lowest organ dose of 0.08 mSvy-1 and 0.11 mSvy-1 for Unicem and Bua Okpella respectively. This study revealed that the exposure rate and all the radiological risk parameters exceeded their recommended safe values. The area of study is radiologically polluted and may be detrimental to human health for long term exposure.


2019 ◽  
pp. 1-9
Author(s):  
M. Onwuka ◽  
C. P. Ononugbo

Radiometric survey of the granitic quarry site at Ishiagu and its environment was done using two radiation monitors and geographical positioning system (GPS) for GIS mapping. In-situ measurement of exposure rate was carried out following the international standard organizational standard between May 2018 and June 2019. The measured average exposure rates ranged from 0.010± 0.002 to 0.038 ± 0.003 mRh-1 with mean value of 0.026 ±0.005 mRh-1. The estimated outdoor absorbed dose rate ranged from 87.0 to 330.6 nGyh-1 with mean value of 228.38 nGyh-1. The equivalent dose rate ranges from 0.84 to 3.20 mSvy-1 with mean value of 2.21 mSvy-1. The mean annual effective dose equivalent (AEDE) calculated was 0.28 mSvy-1 while the mean excess lifetime cancer risk (ELCR) was 0.98 x 10-3. The estimated annual effective dose to different organs showed that the testes have the highest annual effective  dose of 0.191 mSvy-1 followed by ovaries and kidney of 0.135 and 0.139 mSvy-1 respectively while the liver has the lowest annual effective  dose of 0.103 mSvy-1. The radiation contour map of the area showed the distribution of radiation of high and low areas. The result showed that the radiation exposure rate and its associated radiological risk parameters exceeded the safe limits prescribed by ICRP and also the values reported in literatures. However, these values may not constitute acute health risk but long term exposure of residents and workers may be detrimental to their health. Therefore adequate monitoring of this quarry site is necessary to checkmate the exposure rate and provide some protective measures for quarry workers.


2020 ◽  
Vol 65 (1) ◽  
pp. 1-18
Author(s):  
Branislava Mitrovic ◽  
Dragana Todorovic ◽  
Jelena Ajtic ◽  
Borjana Vranjes

This review paper discusses the content of natural (40K, 238U, 226Ra, and 232Th) and artificial (137Cs) radionuclides in the soil of the mountains of Maljen, Tara and Kopaonik in the Republic of Serbia over 2002-2015. In addition, the paper gives radiation hazard parameters, i.e., radium equivalent activity, absorbed dose rate, annual effective dose equivalent, external hazard index, annual gonadal dose equivalent, and excess lifetime cancer risk outdoors that we calculated from the obtained content of the natural radionuclides in the soil samples. We compared the parameters to previously published results for different parts of the country and looked into the radioecological status of the investigated areas.


2020 ◽  
Vol 24 (3) ◽  
pp. 435-442 ◽  
Author(s):  
M. Atipo ◽  
O. Olarinoye ◽  
B. Awojoyogbe ◽  
M. Kolo

Mineral mining and milling can be a source of national economic and technological development. However, mining of minerals has been confirmed to disturb the natural distribution of radioisotopes in the soil, air and water bodies in the biota. In an attempt to evaluate the radiological burden resulting from tin mining activities at Rayfield-Du area of Jos, the background gamma-radiation level in the mine was measured via a well calibratedhand-held dosimeter placed at 1 m above ground level. The mean absorbed dose rate, annual effective dose rate and excess lifetime cancer risk for the mine was 0.83 μSvh-1; 1.44 mSv-1 and 0.005 respectively. Generally, dose rates were higher in the mine pits and processing areas as compared to administrative areas of the mine. The mean measured dose rate and calculated dose parameters for the mine were all high when compared to the regulatory limit for public exposure. The potential of developing radiation-induced health defects as a result of high radiation absorbed dose rate by the miners and dwellers around the mine is highly probable.  Keywords: Gamma-radiation; mine; absorbed dose rate; radiation exposure.


2020 ◽  
Vol 4 (2) ◽  
pp. 47-53
Author(s):  
Mohammed S. Chaanda ◽  
Agbalagba Ezekiel ◽  
Felix Igede

The study was carried out in-situ using a Radalert 100 nuclear radiation monitor and a geographical positioning system (GPS). Five facilities were investigated at the rig site which included the rig site host community as well as the camp site for the oil workers at Ekapkamreh town. Ten 10 sampling locations were evaluated at a total of 60 study points. The values obtained range between 0.115±0.018 (µSv/hr) and 0.299±0.040 (µSv/hr) for the rig site environment, 0.111±0.006 (µSv/hr) and 0.337±0.031 (µSv/hr) for field logistic base (offices and workshops), 0.114±0.011 (µSv/hr) and 0.312±0.021 (µSv/hr) for components of the mud circulation section. Also, the radiological concentration of the Chemical Store ranged between 0.126±0.019 (µSv/hr) and 1.181±0.104 (µSv/hr), while the radiological values obtained from other facilities within the rig site ranged from 0.155±0.026 (µSv/hr) and 0.249±0.026 (µSv/hr). Radiation readings obtained for soil ranged from 0.149±0.05 (µSv/hr) to 0.219±0.025 (µSv/hr) and 0.114±0.039 (µSv/hr) to 0.219±0.051 (µSv/hr) respectively at the host community and camp site. Most of the results obtained showed that the general environment of the rig site is slightly above the permissible absorbed dose rate threshold of 0.15(µSv/hr) recommended by the United Nation Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) in 2009. However, the exposure rates exceed the standard background level of 13µR/hr (coequal to 0.13µSv/hr). There is high tendency for the industry workers to be exposed to radiation with time.


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 4 (4) ◽  
pp. 19-25
Author(s):  
Abiodun Olanrewaju ◽  
Nurudeen Mohammed AbdulKareem ◽  
Isiaka O. Raheem

Measurement of terrestrial background ionizing radiation of blacksmith workshops of Gombe State, Nigeria was carried out using well-calibrated Geiger-Muller counter meters and a meter tape. The measured average exposure rate of two line-sections are 0.018±0.002 and 0.017±0.002 mRh-1. Estimated equivalent dose rates for the two line-sections are 1.50 and 1.45 mSvy-1. The average absorbed dose rates estimated in line-section one and line-section two are 154.94 and 149.97 nGyh-1 respectively. Annual effective dose equivalent (AEDE) of 0.48 mSvy-1 was obtained for outdoor exposure in line-section one while in line-section two, AEDE was 0.23 mSvy-1. The calculated mean excess lifetime cancer risk values for the blacksmith workshop sections are 0.83x 10-3 and 0.80 x 10-3. The obtained values for background ionizing radiation in the line-sections of blacksmith workshop were above the recommended standard limit by ICRP while the absorbed doses (D) were above the recommended value and AEDE calculated in two line-sections of blacksmithing workshops were within the safe values this implies that blacksmithing activities in these areas may not influence the doses received by public. The excess lifetime cancer risk (ELCR) estimated were higher than their world permissible values of 0.29 x 10-3 respectively. The calculated dose to organs showed that the testes have the highest organ dose of 0.153 mSvy-1while liver has the lowest organ dose of 0.086 mSvy-1. This result shows that exposure to 


2021 ◽  
Author(s):  
Hemn Salh ◽  
Fatih Külahcı ◽  
Serpil Aközcan

Abstract A spatial simulation method in .mp4 format was proposed to determine Fukushima radioactive fallout transport and the Absorbed Dose Rate, Annual Effective Dose Equivalent, and Excess Lifetime Cancer Risk were determined for 10 months after the accident (March 11 2011). The findings of this study demonstrate that an appropriate ARIMA model can be applied for radiation dose time-series in the case of nuclear reactor accidents like Chernobyl and Fukushima to predict the future air dose rates, which can provide valuable information in determining the evacuation zones, decontamination processes, and radiation protection progresses. The model forecasted results and the actual observation data in the same period shows a gradual decrease in the air dose rates during the prediction period. Moreover, there is a good agreement between them as the prediction and observation scatter plot follows each other with small variations. These results provide important insights into the predictability of ARIMA models; thus, the models were utilized to forecast the air dose rates for the period (January 2020 - October 2020).


Author(s):  
A. Nwii Abayiga ◽  
G. O. Avwiri ◽  
C. P. Ononugbo

Human are exposed to Background Ionizing radiation (BIR) due to the consumption of crops from fertilized farms within the study area.an in-situ measurement of BIR exposure rate in six fertilized farms and the unfertilized farm aws carried out using a well calibrated portable nuclear radiation detector (Digilert 200). and Geographical positioning system (GPS) for measuring the geographical location. The BIR of the selected local government area varies from 0.012 mR/hr to 0.022 mR / hr and the higher BIR value recorded in Khana, Obio / Akpor, Ahuoda east and Emuoha Local Government area (0.015 mR/hr, 0.015 mR / hr , 0.014 mR/hr , 0.014 mR / hr . While the mean value of Eleme and Gokana were within the permissible limit of 0.013 mR/hr and the BIR of the unfertilized farm was lower than the standard value of 0.013 mR/hr.the mean of absorbed dose varies from 1131 nGy / hr to 122.1nGy/hr which was higher than the recommended safe limit of 84.0 nGy / hr UNSCEAR 2008.The mean of ELCR varies from 0.63 to 0.72x10-3 which is higher than the world average value. The AEDE varies from 0.14 to 0.33 mSv / yr which are below the recommended permissible limit of 1.0 mSv / yr for general public. The effective dose to different body organs are below the recommended limit of 1.0 mSv / yr. The study shows that fertilized farms are contaminated due consistence application of fertilizers during cultivation, but the contamination does not have any direction health effect on individual who consumed crops from fertilized farms but there is the potential for long term health hazards in future such as Cancer due to consistence consumption of crops from fertilized farms.


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