Radiometric analysis of micas used in many industries and evaluation of radiological hazards

2021 ◽  
Vol 0 (0) ◽  
Author(s):  
Ferhat Gezer ◽  
Şeref Turhan ◽  
Yüksel Ufuktepe

Abstract Mica group minerals have been utilized in various industries such as paint, cement, rubber, plastic, paper, automotive, cosmetics, textile, etc. due to their unique electrical, thermal, and mechanical properties. In this study, the radiometric properties of 58 mica samples collected from three quarries operated commercially in Turkey were investigated using gamma-ray spectroscopy with an HPGe detector. The average activity concentrations of 226Ra, 232Th, and 40K analyzed in mica samples were found as 12, 44, and 2763 Bq kg−1, respectively. The radon emanation coefficient and radon mass exhalation rate of mica samples varied from 4 to 22% with an average of 10% and 0.4–5.9 µBq kg−1 s−1 with an average of 2.6 µBq kg−1 s−1, respectively. The radiological hazard caused by the utilization of mica samples as raw materials in the cement and concrete industry was evaluated for adults by calculating the gamma index and annual effective dose due to external exposure indoor. The study results revealed that there are no significant radiological hazards associated with the utilization of mica samples as building raw materials.

2011 ◽  
Vol 13 (3) ◽  
pp. 23-27 ◽  
Author(s):  
Tahir Sofilić ◽  
Delko Barišić ◽  
Una Sofilić ◽  
Marija Đuroković

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.


2021 ◽  
Vol 24 (3) ◽  
pp. 43-49
Author(s):  
Yassamin S.Khalf ◽  
◽  
Kareem K. Mohammad ◽  

The Gamma-ray spectrometry (spectra line Gp) and a high-purity germanium (HPGe) detector were used to determine the activity concentrations of 226Ra, 232Th, and 40K in fertilizer samples. 226Ra, 232Th, and 40K activity concentrations in fertilizers and phosphate raw. In this study the gamma index(I), Radium equivalent dose(Raeq),dose rate(DR),external hazard index(Hex) internal hazard index(Hin), annual effective dose outdoor(AEDout) and annual effective dose indoor(AEDin)were found. This study could serve as a starting point for figuring out how fertilizer radiation affects human health.


2019 ◽  
Vol 122 ◽  
pp. 05004
Author(s):  
Abdulridha S. Younis ◽  
Nada F. Tawfiq

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.


Author(s):  
Neveen S. Abed ◽  
Mohamed Abdel Monsif ◽  
Hesham M. H. Zakaly ◽  
Hamdy A. Awad ◽  
Mahmoud M. Hessien ◽  
...  

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.


2016 ◽  
Vol 31 (2) ◽  
pp. 165-172 ◽  
Author(s):  
Shaaban Harb ◽  
Noor Ahmed ◽  
Wael Badawy ◽  
Nagwa Saad

The activity concentrations of natural radionuclides (226Ra, 232Th, and 40K) for a set of 31 agricultural soil samples from the Nile River banks in the area of El-Sebaiya city, Aswan Governorate, Egypt were measured by gamma-spectrometry. The study revealed that the average activity concentrations of natural radionuclides 226Ra, 232Th, and 40K were 23.2 ? 2.8Bq/kg, 21.1 ? 2.8 Bq/kg, and 218.6 ? 3.7 Bq/kg, respectively. The obtained results of the activity concentrations are within the range of values reported for neighbouring areas in Egypt. The values obtained for the hazard indices and the representative level index in all sampling sites were lower than unity, showing that there is no significant risk arising from the exposure to the soil in the studied area. The absorbed dose rate and annual effective dose in air outdoors and indoors were calculated from 226Ra, 232Th, and 40K in soil, the average values being 32.64 nGy/h, 40.06 ?Sv, and 160.25 ?Sv, respectively. The absorbed dose rate at the eastof El-Sebaiya city is higher than that obtained for the west because of higher concentrations of tri-calcium phosphate in the soil. The studied area is not significantly affected by the industrial activities, except for a few isolated spots.


2015 ◽  
Vol 26 (4) ◽  
pp. 567-575
Author(s):  
H. A. Abdel Ghany ◽  
A. El-Shershaby ◽  
A. Sroor ◽  
M. Abdel-Samei

This work presents the results of the absorbed dose rates and estimated effective doses of the surface soils samples collected from different factories in the industrial region of Suez City, Egypt using high resolution gamma spectrometry system (HpGe) detector. The average activity concentrations of 226Ra, 238U, 232Th and 40K in fertilizer factories were: 74.54 ± 3.7, 26.54 ± 1.3, 14.68 ± 0.73 and 233 ± 11.68 Bq kg−1, respectively, in Ceramic factories were: 75.91 ± 3.7, 31.35 ± 1.56, 20.34 ± 1.01 and 255 ± 12.76 Bq kg−1, respectively, in textile factories were: 121 ± 6.07, 36.22 ± 1.81, 25.80 ± 1.29 and 1076 ± 53.83 Bq kg−1, respectively, in oil factories were: 76.24 ± 3.81, 25.90 ± 1.29, 15.26 ± 0.7 and 266 ± 13.31 Bq kg−1, respectively, and in steel factory were: 79.72 ± 3.98, 35.22 ± 1.76, 11.95 ± 0.59 and 163 ± 8.16 Bq kg−1, respectively. The calculated absorbed dose rates in factories were: 31.13 ± 1.55, 37.86 ± 1.89, 79.04 ± 3.95, 32.64 ± 1.63 and 29.99 ± 1.49 nGy h−1, respectively. Also, the annual effective dose in the above factories were: 0.03 ± 0.001, 0.04 ± 0.002, 0.09 ± 0.004, 0.03 ± 0.001 and 0.036 ± 0.001 mSv y−1, respectively. Also, the exposure of workers to radon was studied using solid state nuclear track detectors (CR-39). The results indicate that feeding materials variably affect the radioactivity measurements of the surface soil in different factories.


Author(s):  
Somsavath LEUANGTAKOUN

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.


2019 ◽  
Vol 34 (2) ◽  
pp. 149-156 ◽  
Author(s):  
Aybaba Hancerliogullari ◽  
Madee Ali ◽  
Ash Kurnaz ◽  
Seref Turhan

Sepiolite is a naturally occurring clay mineral of sedimentary origin and is a magnesium hydrosilicate. Sepiolite has been widely used as an additive raw material in ceramics and cement industry, pharmaceutical, cleaning-detergent, paper, paint, cosmetic agriculture, fertilizer, etc. In this study, the natural radioactivity levels, radon emanation coefficients and radon exhalation rates of 30 sepiolite samples collected from open three sepiolite quarries (Beylikova, Polath and Sivrihisar) in Central Anatolia region of Turkey were determined by using a gamma-ray spectrometry with an HPGe detector. The average absorbed gamma dose rates directly measured in Beylikova, Polath and Sivrihisar open three sepiolite quarries located in Central Anatolia region of Turkey were found as 59, 65, and 64 nGyh?1, respectively. The average activity concentrations of 226Ra, 232Th, and 40K in 30 sepiolite samples collected from those quarries were found as 38.6, 12.4, and 67.4 Bqkg?1, respectively. The average emanation coefficient and exhalation rate of radon of sepiolite samples were determined as 22 % and 0.065 Bqkg?1h?1, respectively. Also, radiological parameters (outdoor absorbed gamma dose rate, annual effective dose rate, external and internal index) were estimated to evaluate the use of sepiolite samples as additive raw materials in the building sector.


2021 ◽  
Author(s):  
Eyakifama Hazou ◽  
Benjamin Zorko ◽  
Milohum Mikesokpo Dzagli ◽  
Essolakina Manakrihèa Haliba ◽  
Cebastien Joel Guembou Shouop ◽  
...  

Abstract Natural radionuclides activity concentrations of 226Ra, 228Ra, and 40K in soil and grass samples, statistical analysis of these radionuclides and transfer factors (TFs) from soil to the grass were carried out from phosphate mining and processing sites in southern areas of Togo using gamma-ray spectrometry-based High Purity Germanium (HPGe) detector. The average activity concentrations of 226Ra, 228Ra, and 40K were found within the range usually measured worldwide. Statistical analysis was done by investigating the skewness, the kurtosis, and the density distribution of radionuclides in the study areas. Both skewness and kurtosis displayed that the activity concentrations of soil and grass samples in the dischargement waste site (Kpémé) and mining site (Hahotoé) exhibited slightly positively skewed, negatively skewed, leptokurtic, and platykurtic distributions. The TFs for 226Ra, 228Ra, and 40K from dischargement waste soil to grass were evaluated. The average transfer factors of 226Ra, 228Ra, and 40K in the phosphate processing area were found to be 0.16, 0.32, and 8.42, respectively. 226Ra and 228Ra TFs values were found to within the limit of worldwide measure values while that of 40K was to be larger than the values measured in other countries. The average TF value of 8.42 for 40K was 8 times higher than the average value of unity, showing its large intake by vegetables. The high TFs for 40K could be explained by the extensive application of phosphate fertilizers to soils when growing vegetables.


2018 ◽  
Vol 106 (7) ◽  
pp. 611-621 ◽  
Author(s):  
Şeref Turhan ◽  
Elif Gören ◽  
Ahmed M.K. Garad ◽  
Aydan Altıkulaç ◽  
Aslı Kurnaz ◽  
...  

Abstract Lignite coal (LC) is a key energy source for electricity generation in Turkey. During lignite burning, huge amounts of fly ash (FA), bottom ash and slag are produced as by-products which contain radionuclides in the natural radioactive series of uranium and thorium, and radioactive potassium. These radionuclides may lead to radiological exposure of workers and the public and cause environmental problems. Therefore, finding diverse uses for the by-products in the construction sector and earthwork applications has considerable economic and environmental importance. In this study, the activity concentrations of 226Ra, 232Th and 40K in and radon emanating power (EP) and radon mass exhalation rate (EXRM) from LC, slag and FA obtained from the Kangal lignite-burning power plant with a power of 457 MWe were measured using gamma-ray spectroscopy. The major chemical components (SiO2, Al2O3, Fe2O3, CaO and MgO) of fly ash samples were analysed using an energy dispersive X-ray fluorescence spectrometer. The annual effective doses received by workers and members of the public were estimated using different scenarios specified in Radiation protection 122. The average activity concentrations of 226Ra, 232Th and 40K in LC, slag and FA samples were 187±21, 16±1 and 99±9 Bq kg−1, 620±18, 41±2 and 330±13 Bq kg−1, and 937±30, 38±2 and 272±17 Bq kg−1, respectively. The average values of EP and EXRM of the lignite, slag and FA samples were 8 %, 7 % and 10 %, and 0.1, 0.3 and 0.7 Bq kg−1 h−1, respectively. The highest average of the total annual effective dose is estimated at 153 μSv for members of the public and 74 μSv for workers, lower than the recommended annual limit of 1000 μSv.


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