scholarly journals Assessing the Radiological Risks Associated with High Natural Radioactivity of Microgranitic Rocks: A Case Study in a Northeastern Desert of Egypt

2022 ◽  
Vol 19 (1) ◽  
pp. 473
Author(s):  
Neveen S. Abed ◽  
Mohamed Abdel Monsif ◽  
Hesham M. H. Zakaly ◽  
Hamdy A. Awad ◽  
Mahmoud M. Hessien ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Fuel Cycle ◽  
Radiological Hazard ◽  
United Nations Scientific Committee ◽  
Southeastern Part ◽  
Gamma Ray Spectrometer ◽  
Activity Concentrations ◽  
Radiological Hazards ◽  
The Mean

This study aimed to evaluate the radiological hazards of uranium (238U), thorium (232Th), and potassium (40K) in microgranitic rocks from the southeastern part of Wadi Baroud, a northeastern desert of Egypt. The activity concentrations of the measured radionuclides were determined by using a gamma-ray spectrometer (NaI-Tl-activated detector). The mean (238U), (232Th), and (40K) concentrations in the studied rocks were found to be 3680.3, 3635.2, and 822.76 Bq/kg, respectively. The contents in these rocks were elevated, reaching up to 6.3 wt%. This indicated the alkaline nature of these rocks. The high ratios of Th/U in the mineralized rocks could be related to late magmatic mineralization, suggesting the ascent of late magmatic fluids through weak planes such as faults and the contact of these rocks with older granites. The present data were higher than those of the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) guideline limits. All the radiological hazard results indicated high human health risks. This confirmed that this area is not radiologically safe, and care must be taken when working in this area. This study showed that the area under investigation had high U content suitable for uranium extraction that could be used in the nuclear fuel cycle.

MODELLING OF 226Ra ACTIVITY CONCENTRATIONS ALONG OGUN RIVER, SOUTH WESTERN NIGERIA

2018 ◽  
Vol 14 (2) ◽  
pp. 1-14
Author(s):  
I C OKEYODE ◽  
N N JIBIRI ◽  
R BELLO
Keyword(s):  
Experimental Data ◽  
Gamma Ray ◽  
Statistical Tests ◽  
Least Square ◽  
Approximation Technique ◽  
Sediment Samples ◽  
Gamma Ray Spectrometer ◽  
Activity Concentrations ◽  
226Ra Activity ◽  
Ogun River

This work was aimed at generating a model using least square approximation technique to predict values of activity concentrations of 226Ra in any location along Ogun river in Nigeria using experimental data. Sediment samples were collected in thirty two locations along the river of about 400 km in length. NaI(Tl) gamma-ray spectrometer system was used to obtain activity concentrations of 226Ra.The aver-age value of activity concentration of 226Ra in the sediment samples from the upper region through the middle to the lower region of the river was found to be 12.65 ± 3.48 Bq/kg, having values ranging from 5.57 ± 2.36 Bq/kg (at Ekerin) to 20.40 ± 4.52 Bq/kg (at Sokori). From this work, it was observed that the generated model and experimental data could be used to predict values of activity concentrations of 226Ra in any location along the river once the latitude and longitude (position) are known. Statistical tests on the model also showed that there were no significant differences between the experimental and predicted data of 226Ra and that 98.70% of the experimental data were predicted by the model.

scholarly journals Low-background, digital gamma-ray spectrometer with BEGe detector and active shield: commissioning, optimisation and software development

2019 ◽  
Vol 322 (3) ◽  
pp. 1311-1321
Author(s):  
Krzysztof Gorzkiewicz ◽  
Jerzy Wojciech Mietelski ◽  
Renata Kierepko ◽  
Kamil Brudecki
Keyword(s):  
Gamma Ray ◽  
Germanium Detector ◽  
Low Background ◽  
Gamma Ray Spectrometer ◽  
Annihilation Peak ◽  
The Mean ◽  
Plastic Scintillators ◽  
Set Up ◽  
Active Shield ◽  
Broad Energy

Abstract This paper presents results of the development process of low-background, digital gamma-rays spectrometer equipped with Broad Energy Germanium detector (CANBERRA BE5030), multi-layer passive shield and cosmic veto system that consists of five plastic scintillators (SCIONIX EJ-200). Data acquisition is performed using digitizer CAEN DT5725 with CoMPASS software. Output data analysis is carried out with purposely written and developed code VETO. On the basis of conducted tests, acquisition parameters were set up and tuned as well as time delays between all detectors were established. As a result of the configuration process, the mean background counts reduction of 64% in the whole spectrum and 65% in annihilation peak were achieved. This procedure allowed diminishing detection limits of selected isotopes 37% on average.

scholarly journals Assessment of Natural Radioactivity Level and Annual Effective Dose of Amber Rice Samples Cultivated in the South of Iraq

2019 ◽  
Vol 122 ◽  
pp. 05004
Author(s):  
Abdulridha S. Younis ◽  
Nada F. Tawfiq
Keyword(s):  
Effective Dose ◽  
Gamma Ray ◽  
Annual Effective Dose ◽  
Radioactive Material ◽  
Radiological Protection ◽  
Gamma Ray Spectrometer ◽  
Activity Concentrations ◽  
Rice Consumption ◽  
Rice Samples ◽  
South Of Iraq

In this work, the activity concentrations of naturally occurring radioactive material including 238U, 232Th, and 40K were measured of some amber rice samples cultivated in southern Baghdad and Al Najaf governorate and used in Baghdad governorate, Iraq in 2018, using gamma-ray spectrometer with NaI (Tl) detector. The results show that the activity concentrations for 238U ranged from (2.68 to 10.81) Bq/kg with average 5.94 Bq/kg, 232Th ranged from (B.D.L to 3.37) Bq/kg with average 2.65 Bq/kg, and for 40K ranged from (4.48 to 35.7) Bq/kg with average 16.84 Bq/kg. The annual effective dose from rice consumption by adults for 238U, 232Th, and 40K ranged from (0.41 to 1.6) x10-5 Sv/y with average 0.9 x10-5 Sv/y, (B.D.L to 0.42) x10-5 Sv/y with average 0.2 x10-5 Sv/y, and (0.17 to 1.2) x10-5 Sv/y with average 0.45 x10-5 Sv/y respectively. All values of the average specific activities are less than the global average values of ICRP, and the annual effective dose from rice consumption by adults was lower than the permissible limit of (1 m Sv/y) recommended by the International Commission on Radiological Protection.

Comparing of the Natural Radioactivity in Soil Samples of University at Al-Husseineya and Al-Mothafeen Sites of Kerbala, Iraq

2021 ◽  
Vol 14 (2) ◽  
pp. 177-191
Keyword(s):  
Natural Radioactivity ◽  
Gamma Ray ◽  
Specific Activity ◽  
Soil Samples ◽  
Standard Errors ◽  
Radiological Hazard ◽  
Gis Technology ◽  
Mean Values ◽  
The Mean ◽  
Radiological Hazard Indices

Abstract: Radioactivity must be studied in soil to see the changes in the doses of human exposure. In this study, natural radioactivity and radiological hazard indices in soil samples of the Faculty of Agriculture (Al-Husseineya site) and the Faculty of Medicine (Al-Mothafeen site) in Kerbala Governorate were determined using gamma-ray spectroscopy. The results showed that the mean values of specific activity (in units of Bq/kg) and standard errors of: 238U, 232Th and 40K at Al-Husseineya site was 21.7±7.2, 9.43±3.2 and 335.8±82.2, respectively, while at Al-Mothafeen site, the mean values and standard errors were 22.4±8.8, 11.2±3.3 and 333.1±70.7, respectively. Radiation maps of natural radioactivity (238U, 232Th and 40K) at Al-Husseineya and Al-Mothafeen sites were mapped using geographic information system (GIS) technology. Moreover, most results in the present study fall within the acceptable levels, as defined by OCDE, UNSCEAR and ICRP. Therefore, there is no significant radiological hazard at the sites which were studied. Keywords: Radiological hazard, Natural radioactivity, Soil, NaI (Tl), Gamma-ray, Karbela University.

EVALUATION OF RADIATION DOSES AND HAZARD INDICES IN CRUSHED ROCKS FROM SOME QUARRIES IN IBADAN SOUTHWESTERN NIGERIA

2019 ◽  
Vol 187 (3) ◽  
pp. 383-389 ◽  
Author(s):  
S K Alausa ◽  
F O Eluyera ◽  
J O Coker
Keyword(s):  
Health Effect ◽  
Radiation Doses ◽  
Radiological Hazard ◽  
Hazard Indices ◽  
Southwestern Nigeria ◽  
Activity Concentrations ◽  
The Mean ◽  
Radiological Health ◽  
Radiological Hazard Indices ◽  
Radioactivity Levels

Abstract The radiological assessment of rock samples from four quarry sites in Ibadan have been carried out. The mean activity concentrations of 40K, 226Ra and 232Th were 377.0 ± 37.9, 17.7 ± 3.6 and 4.98 ± 2.1 Bq kg−1, respectively, for Ratcon Quarry (RQ); 408.0 ± 28.7, 16.6 ± 1.6 and 10.6 ± 2.3 Bq kg−1, respectively, for Dekit Quarry; 388.0 ± 26.6, 15.7 ± 1.9 and 9.85 ± 3.9 Bq kg−1, respectively, for Hajaig Quarry; and 388.084 ± 55.9, 16.2 ± 3.9 and 12.1 ± 3.8 Bq kg−1, respectively, for NSCE Quarry (NQ). The highest mean outdoor effective dose of 0.038 ± 0.005 mSv y−1 and the minimum of 0.033 ± 0.004 mSv y−1 were obtained at NQ and RQ, respectively. The radiological hazard indices recorded in each site were <1.0. The results show lower radioactivity levels than the world average values; therefore, no serious radiological health effect is expected when the crushed rocks from the quarries are used for buildings construction.

scholarly journals Radioactivity of some building and raw materials used in Croatia

2011 ◽  
Vol 13 (3) ◽  
pp. 23-27 ◽  
Author(s):  
Tahir Sofilić ◽  
Delko Barišić ◽  
Una Sofilić ◽  
Marija Đuroković
Keyword(s):  
Activity Concentration ◽  
Gamma Ray ◽  
Raw Materials ◽  
Coal Fly Ash ◽  
Radium Equivalent Activity ◽  
Gamma Ray Spectrometer ◽  
Activity Concentrations ◽  
Radium Equivalent ◽  
Average Activity ◽  
Materials Used

Radioactivity of some building and raw materials used in Croatia In the present study, the activity concentrations of 226Ra, 232Th, 40K in some building and raw materials used in Croatia were measured by using a gamma-ray spectrometer with the HPGe detector. The average activity concentrations of the studied different building and raw materials ranged from 11.6 ± 1.7 (concrete) to 251.2 ± 25.7 Bqkg-1 (GBFS), 14.0 ± 2.7 (concrete) to 54.4 ± 8.3 (coal fly ash) and 147.2 ± 19.0 (concrete) to 773.7 ± 82.0 Bqkg-1 (tuff) for 226Ra, 232Th and 40K, respectively. Radium equivalent activity, activity concentration index, absorbed gamma dose rate indoor due to the external exposure and corresponding annual effective dose were determined to estimate the exposure risk arising due to the use of these building and raw materials.

scholarly journals The presence of radioactive heavy minerals in prospecting trenches and concomitant occupational exposure

PLoS ONE ◽  
2021 ◽  
Vol 16 (3) ◽  
pp. e0249329
Author(s):  
Mohamed Youssef Mohamed Hanfi ◽  
Masoud Salah Masoud ◽  
M. I. Sayyed ◽  
Mayeen Uddin Khandaker ◽  
Mohammed Rashed Iqbal Faruque ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Fuel Cycle ◽  
Eastern Desert ◽  
Uranium Content ◽  
Nuclear Industry ◽  
Heavy Minerals ◽  
Radiological Protection ◽  
Physical Situation ◽  
Gamma Ray Spectrometer ◽  
Hazard Parameters

Uranium, perhaps the most strategically important component of heavy minerals, finds particular significance in the nuclear industry. In prospecting trenches, the radioactivity of 238U and 232Th provides a good signature of the presence of heavy minerals. In the work herein, the activity concentrations of several key primordial radionuclides (238U, 232Th, and 40K) were measured in prospecting trenches (each of the latter being of approximately the same geometry and physical situation). All of these are located in the Seila area of the South Eastern desert of Egypt. A recently introduced industry standard, the portable hand-held RS-230 BGO gamma-ray spectrometer (1024 channels) was employed in the study. Based on the measured data, the trenches were classified as either non-regulated (U activity less than 1000 Bq kg-1) or regulated (with 238U activity more than 1000 Bq kg-1). Several radiological hazard parameters were calculated, statistical analysis also being performed to examine correlations between the origins of the radionuclides and their influence on the calculated values. While the radioactivity and hazard parameters exceed United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) guided limits, the mean annual effective doses of 0.49 and 1.4 mSv y-1 in non-regulated and regulated trenches respectively remain well below the International Commission on Radiological Protection (ICRP) recommended 20 mSv/y maximum occupational limit. This investigation reveals that the studied area contains high uranium content, suitable for extraction of U-minerals for use in the nuclear fuel cycle.

scholarly journals Determination of natural radioactivity in soil samples around gold mining area in Khamkeut district, Bolikhamxay Province, Laos using gamma ray spectrometer with NaI(Tl) detector

2018 ◽  
Vol 34 (3) ◽  
Author(s):  
Somsavath LEUANGTAKOUN
Keyword(s):  
Gamma Ray ◽  
Natural Radionuclides ◽  
Mining Area ◽  
Soil Samples ◽  
Gold Mines ◽  
Gamma Ray Spectrometer ◽  
Activity Concentrations ◽  
Radium Equivalent ◽  
Average Activity

This paper presented the method of determining the radioactivity of 40K, 226Ra and 232Th in soil samples by gamma-ray spectrometer using NaI (Tl) scintillation detector. The radioactivity of each isotope is calculated based on the net count rate in the energy window characteristic for the 40K, 226Ra and 232Th radioisotopes respectively. We have determined  activity concentrations of the natural radionuclides 226Ra,232Th and 40K in 15 soil samples collected around gold mines of Khamkeut district, Bolikhamxay Province, Laos. The average activity concentrations of the natural radionuclides 226Ra, 232Th and 40K are 46.58  ±  7.36 , 71.19  ±  5.42 and 574.62  ±  25.02 Bq.kg-1, respectively. The average activity concentrations of 226Ra and 232Th in this work are higher than those of Bolikhamxay Province, Laos and the world average values. The estimated average outdoor annual effective dose (E) and radium equivalent actitvity (Raeq) are 0.10  ±  0.004 mSv.yr-1 and 192.64  ±  16.12 Bq.kg-1, respectively.

scholarly journals Radioactivity Concentrations in Soil Samples from Kandam, Gyalgyal, Burmawan masaka, Dinbisu and Giyawa Mines in Wurno LGA, Sokoto State, Nigeria

2018 ◽  
pp. 1-9
Author(s):  
Y. M. Ahijjo ◽  
A. N. Baba-Kutigi ◽  
M. Momoh ◽  
A. M. Bayawa ◽  
M. Hussain
Keyword(s):  
Hpge Detector ◽  
Gamma Ray ◽  
Soil Samples ◽  
Gamma Ray Spectrometry ◽  
Sample Population ◽  
Radiological Parameters ◽  
Activity Concentrations ◽  
The Mean ◽  
Channel Analyzer ◽  
Elevated Exposure

Aims: This study was conducted in a bid to ascertain the concentration of NORMS in the soil samples dugout of some mining sites in Kandam, Gyalggal, Burmawan masaka, Dinbisu and Giyawa town in Wurno LGA, Sokoto State Nigeria. The concerns about NORMS radioactivity in the environment are frequently linked to natural radioactivity which is more of primordial radionuclides. Study Design: A total number of nine soil samples were randomly collected for this study. The randomness was in order to represent over 90% of the sample population of different mines in Wurno LGA, Sokoto state for the analysis of gamma-ray spectrometry of High Purity Germanium (HPGe) detector coupled to a Multi-Channel Analyzer (MCA). Place and Duration of Study: Department of Physics, Usmanu Danfodiyo University, Sokoto, Nigeria, between August 2015 and June 2016. Methodology: The concentrations of the radionuclides (226Ra, 232Th and 40K) were ascertained through a high-resolution gamma-ray spectrometry of HPGe detector coupled with a Multi-Channel Analyzer, Centre for Advanced Studies in Physics (CASP), Government College University (GCU), Lahore, Pakistan. The activity concentrations of 226Ra, 232Th and 40K in the soil samples were obtained and used to calculate the radiological parameters ( Raeq, Hex, Hin, DAbs and Deff ) in order to assess the radiological impacts on the inhabitants. Results: The mean activity concentrations for 226Ra, 232Th and 40K in the soil samples were found to be 58.34, 53.76 and 679.70 Bqkg-1 while the radiological hazards parameters revealed mean values of 187.55 Bqkg-1, 0.51, 0.66, 87.77 nGy.h-1 and 107.64 μScyr -1 for Raeq, Hex, Hin, DAbs  and Deff respectively. These were compared with the results of similar studies conducted elsewhere and around the world. It was noticed that 40K contributes the highest level of radioactivity in this study which could enhance the amount of background radiation received by the population in the study area. The activity concentration unveiled from the soil samples were considerably lower for 226Ra and 232Th when compared to the activity of 40K. The mean value of the doseused to calculate the radiological parameters calculations shows that an elevated exposure to radioactivity by the inhabitants around this mine is eminent.  Conclusion: Cancer and various forms of ailment due to radioactivity exposure are further anticipated for the workers in the pits and the dwelling communities.

Heat flow and surface radioactivity in the Quirke Lake Syncline near Elliot Lake, Ontario, Canada

1968 ◽  
Vol 5 (6) ◽  
pp. 1417-1428 ◽  
Author(s):  
J. H. Sass ◽  
P. G. Killeen ◽  
E. D. Mustonen
Keyword(s):  
Heat Flow ◽  
Heat Production ◽  
Gamma Ray ◽  
Average Rate ◽  
Structural Effects ◽  
Gamma Ray Spectrometer ◽  
A Value ◽  
The Mean ◽  
Data Yield ◽  
Ore Zones

Heat flow was measured in seven diamond-drilled holes, ranging in depth from 300 to 900 m, in the Quirke Lake Syncline (82° 30′ W, 46° 30′ N, mean elevation 370 m), Values for individual holes vary from 1.20 to 1.40 with a mean of 1.32 ± 0.02 μcal/cm2s, and no systematic variation was detected within the 50 km2 area studied. Radiometric measurements with a portable, three-channel, gamma-ray spectrometer show a downward concentration (stratigraphically) of Th, U, and K within the lower part of the syncline, with mean concentrations of 12.7 ppm, 3.3 ppm, and 1.9%, respectively. These data yield an average rate of heat production of 4.5 heat generation units (1 hgu = 10−13 cal/cm3s). Taking account of the ore zones, the mean heat production from the syncline is about 6 hgu. Corrections for structural effects and heat production from the ore result in a value of 1.2 for the regional heat flow. This is within the range of other shield values, although somewhat higher than the average for the Canadian Shield. The high value is readily explained if the observed mean surface radioactivity persists to a depth of 7 to 10 km.

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