scholarly journals Measurement of Natural Radionuclides and Radon Gas Concentration in Surface Soil samples within Jalingo Metropolis, North East Nigeria

2021 ◽  
Vol 4 (1) ◽  
pp. 139-145
Author(s):  
T Sombo ◽  
F Bibi ◽  
AA Tyovenda

Activity concentrations of radionuclides (226Ra, 232Th, 40K) and radon gas in soil samples collected within Jalingo Metropolis were assessed by gamma spectrometric techniques using Na (TI) scintillation detector. The result showed an average activity concentration of 226Ra, 232Th and 40K to be 18.626±7.31 Bq/kg, 16.709±10.96 Bq/kg and,167.935±389.33 Bq/kg. The concentrations of 226Ra, 232Th were lower than the world average value while 40K was far higher that the recommended value.Most people in the study area use soil for building construction therefore, it was necessary to asses if there are any radiological hazards associated with the soil. This was achieved by determining Radium equivalent activity (Raeq), internal hazard index (Hin) and Annual effective dose rate. The result indicates that the indices are within normal limit. The Radon concentration in soil varies 11.126±1.315 kBq/kg to 30.374±3.331 kBq/kg with a mean value of 17.881±7.019 kBq/kg which is within the safety limits. Generally, the result showed that the soil in the study area might not pose major hazard to the members of the public

2014 ◽  
Vol 955-959 ◽  
pp. 3691-3695
Author(s):  
Gang Song ◽  
Min Xing Lu ◽  
Qiu Ping Zhu ◽  
Di Yun Chen ◽  
Yong Heng Chen

The natural radionuclide (238U, 226Ra, 232Th and 40K) concentrations in 152 soil samples were determined from two major granite areas in Guangzhou, using high resolution γ-ray spectroscopic system based on the characteristic spectral peaks. The mean activity values for 238U, 226Ra, 232Th and 40K were found to be 156.6±98.8, 160.9±96.5, 184.8±101.5 and 832.5±493.1 Bq kg–1 dry mass, respectively. The absorbed dose rate (D) calculated from activity concentration of 226Ra, 232Th and 40K ranged from 53.2 to 497.1 nGy h–1 with a mean of 220.7 nGy h–1. The Radium equivalent activity (Raeq), the outdoor annual effective dose and the external hazard index (Ir), which resulted from the natural radionuclides in soil, were also calculated and found to vary from 119.7 to 1117.2 Bq kg–1, from 0.07 to 0.61 mSv and from 0.33 to 3.07, respectively. The radium equivalent activities and the external hazard index in all the soil samples were same as 64.5% higher than the limit of 370 Bq kg–1 and 1.0, respectively. The outdoor annual effective dose was higher than the worldwide mean value of 0.07 mSv.


2020 ◽  
Vol 43 (2) ◽  
pp. 169-180
Author(s):  
Md Samiul Ehsan ◽  
Md Faisal Rahman ◽  
Nafisa Tabassum ◽  
Md Mahidul Haque Prodhan ◽  
Shikha Pervin ◽  
...  

The study has been carried out to measure the activity concentration of natural and anthropogenic radionuclides in fifteen(15) soil samples of Natore, Kushtia and Pabna district, which are around the 30 km peripheral area of Rooppur Nuclear Power Plant, by gamma ray spectrometry system using a High Purity Germanium (HPGe) detector. It is found that the activity concentration of 226Ra, in the collected sample was from 3.52 Bq/kg to 28.5 Bq/kg with the average value of 12.42 Bq/kg. For 232Th, the range was from 4.18 Bq/kg to 34.5 Bq/kg with the average value of 12.6 Bq/kg. Finally, the activity concentration of 40K, in the collected sample was in the range of 84 Bq/kg to 345 Bq/kg, and the average value was 198.9 Bq/kg. The absorbed dose rate (D) was found to be in the range of 4.59 nGy/h to 40.93 nGy/h with the mean value 21.3 nGy/h. The annual effective dose (E) was in the range of 0.006 mSv/yr to 0.152 mSv/yr with an average of 0.033 mSv/yr. The radium equivalent activity was in the range from 10.02 Bq/kg to 89 Bq/kg with an average of 44.99 Bq/kg. The external hazard index (Hex) was found to be in the range of 0.027 to 0.242 with the mean value of 0.121 and the internal hazard index (Hin) was found to be in the range of 0.044 to 0.302 with the mean value of 0.156. All the values are much below the recommended limit by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 35 Bq/kg for 226Ra, 30 Bq/kg for 232Th and 400 Bq/kg for 40K. According to international and national regulation, the annual dose to members of the public, 1 mSvy-1 and Hex & Hin must be lower than unity. Moreover, no artificial radioactivity was found in the soil samples of this study area. This research concludes that the found values are within the permissible limits as required by the Nuclear Safety and Radiation Control(NSRC) Rules-1997 of Bangladesh and International Atomic Energy Agency(IAEA) Safety Standards- General Safety Requirements (GSR): Part-3. Journal of Bangladesh Academy of Sciences, Vol. 43, No. 2, 169-180, 2019


Author(s):  
Loat Bui Van

We have determined activity concentrations in 33 soil samples collected from Bolikhamxay Province, Laos. The activity concentrations of the natural radionuclides 226Ra,232Th and 40K in soil samples were measured by a gamma spectrometer with a HPGe detector. The average activity concentrations of the natural radionuclides 226Ra, 232Th and 40K are 43.8 ± 5.6, 57.0 ± 7.3 and 426.4 ± 23.1 Bq.kg-1, respectively. The average activity concentrations of 226Ra and 232Th in this work are higher than those of the world average values. Meanwhile, the  activity concentration of 40 K is almost the same of the world average value. The estimated average outdoor annual effective dose (E) and radium equivalent actitvity (Raeq) are 0.17 ± 0.02 mSv.yr-1 and 154.8 ± 16.1 Bq.kg-1, respectively.


2021 ◽  
Vol 9 (1) ◽  
pp. 95-102
Author(s):  
Zakariya A. Hussein ◽  
Najeba F. Salih ◽  
Shalaw Z. Sedeeq

This paper investigates the activity concentration of radionuclides (226Ra, 232Th, 40K and 137Cs) in the wheat grain samples using a high-purity germanium detector. Thirty-six wheat grain samples were collected from different locations of Koya City, Iraqi Kurdistan region. Average activity concentrations of 226Ra, 232Th and 40K in wheat grain are found to be 0.407 ± 0.097 Bq.kg-1 for 226Ra, 0.36 ± 0.14 Bq.kg-1 for 232Th and 109.25± 2.214 Bq.kg-1 for 40K, respectively. The measured activity concentrations for the radionuclides are compared with the reported data from other countries. In addition, the fallout radionuclide of 137Cs has no detection of in the wheat grain samples. The radium equivalent activity Raeq, internal and external hazard indices Hin and Hex, and annual gonadal dose equivalent are calculated for the measured samples. The total ingestion dose is 113.19 µSv.y-1, which is below the world average value of 290 µSv.y-1.


This work was undertaken with the purpose of measuring natural radioactivity, due to 238U, 232Th and 40K in 30 soil samples collected from two hospitals in the governorate of (AL-Najaf), in Iraq. The samples were distributed (15) samples per hospital, and Radiation risks were also calculated for all soil samples. The natural radioactivity was measured using NaI (Tl) detector, the results of the specific activity at the Al Sadr Hospital were 238U ranged from (5.89±0.36 to 21.38±0.69) (Bq/kg) with average value 12.60±0.51 (Bq/kg). 232Th from (0.44±0.06 to 14.67±0.37) (Bq/kg) with average value (4.46±0.19) (Bq/kg), and 40K from (252.14±2.54 to 478.24±3.50) (Bq/kg) with average value (346.95±289) (Bq/kg). AL-Forat AL-Aosat hospital results were 238U ranged from (0.69±0.12 to 27.63±0.74) (Bq/kg) with average value (12.84±0.51) (Bq/kg), 232Th from (1.47±0.11 to 9.3±0.31 (Bq/kg) with average value 6.19±0.24 (Bq/kg), and 40K from (192.88±2.27 to 338.52±3.08) (Bq/kg) with average value (254.29±2.54) (Bq/kg). The radiation risks calculated, Radium Equivalent (Raeq), external Hazard index (Hex), absorbed dose rate (ADr), total Annual Effective Dose Equivalent (AEDE), and the Excess Life Cancer Risk (ELCR). The results were for Al Sadr Hospital (45.7063(Bq/kg), 0.1234, 23.0648(nGy/h), 0.0283(mSV/y), 1.247439702×10-3) respectively. For AL-Forat AL-Aosat hospital were (41.2655 (Bq/kg), 0.111, 20.3772 (nGy/h), 0.0250(mSV/y)`, 1.102083688×10-3) respectively. The results in the two hospitals were compared with the global allowable values ratio within the permissible ranges specified by UNSCER, OCDE, and ICRP; we concluded that all the sites in this study are safe.


2014 ◽  
Vol 65 (2) ◽  
pp. 189-197 ◽  
Author(s):  
Nataša B. Sarap ◽  
Marija M. Janković ◽  
Dragana J. Todorović ◽  
Jelena D. Nikolić ◽  
Milojko S. Kovačević

AbstractIn the 1999 bombing of the Federal Republic of Yugoslavia, NATO forces used ammunition containing depleted uranium. The cleaning of depleted uranium that followed was performed in southern Serbia by the Vinča Institute of Nuclear Sciences between 2002 and 2007 at the locations of Pljačkovica, Borovac, Bratoselce, and Reljan. This paper presents detailed results of radioactivity monitoring four years after cleaning (2011), which included the determination of gamma emitters in soil, water, and plant samples, as well as gross alpha and beta activities in water samples. The gamma spectrometry results showed the presence of natural radionuclides 226Ra, 232Th, 40K, 235U, 238U, and the produced radionuclide 137Cs (from the Chernobyl accident). In order to evaluate the radiological hazard from soil, the radium equivalent activity, the gamma dose rate, the external hazard index, and the annual effective dose were calculated. Considering that a significant number of people inhabit the studied locations, the periodical monitoring of radionuclide content is vital.


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.


2018 ◽  
Vol 2018 ◽  
pp. 1-11 ◽  
Author(s):  
Rasha S. Ahmed ◽  
Raghad S. Mohammed ◽  
Rana O. Abdaljalil

Clay soil samples (0, 30, and 60 cm depths) were collected from two districts (Abu Al Khasib and Ad Dayr) in Basrah governorate in southern Iraq for gamma-ray spectroscopy. The activity concentrations for natural existing radionuclides in 18 soil samples were measured using high-purity germanium detector HPGe. From the obtained results of γ-ray spectroscopy, the 238U activity concentrations were found to be ranging from 2.4 to 5.6 ppm with an average of 3.5 ppm in Abu Al Khasib and ranging from 2.1 to 4.5 ppm with an average of 2.9 ppm in Ad Dayr. 232Th concentrations were ranging from 3.6 to 7.5 ppm with an average of 4.7 ppm in Abu Al Khasib and ranging from 3.7 to 7.9 ppm with an average of 5.0 ppm in Ad Dayr. 40K concentration was ranging from 0.1% to 2.0% with an average of 1.2% in Abu Al Khasib and ranging from 0.9% to 1.8% with an average of 1.3% in Ad Dayr. High 238U and 226Ra concentration levels were recorded in both study regions. The concentrations of 232Th are within the normal limits in both regions. High levels of 40K were recorded in some locations. Generally, in most locations, 40K activity was within normal ranges. The radium equivalent activity, the external hazard index, the internal hazard index, and the radioactivity level index were calculated to estimate the radiation hazard in Basrah. The estimated radiation hazard indices were within normal limits, except the radioactivity level index, which shows elevated values. The obtained results were compared with other countries and with the worldwide median certified values.


2020 ◽  
Vol 189 (2) ◽  
pp. 234-241 ◽  
Author(s):  
Jahan Zeb ◽  
Mohammad Wasim ◽  
Sardar A Shah ◽  
Safia Khanam ◽  
Hajira Tahir ◽  
...  

Abstract Chemical phase and distribution of natural radionuclides (226Ra, 232Th and 40K) were determined for sand samples collected from ten different beaches of Karachi. All samples, except one, were identified with major and minor phases as SiO2 and CaCO3, respectively. The average activity concentrations were 24.9, 25.0 and 239 Bq kg−1 for 226Ra, 232Th and 40K, respectively. Including all samples, the average radium equivalent activity was 79.1 Bq kg−1. The external and internal radiation hazard indices and representative level index were all found below unity. The average air absorbed dose rate at 1 m above the sand due to the natural radionuclides was 18.3 nGy h−1, which was less than the world average for soil. The corresponding annual effective dose rate was 22.4 μSv y−1. It was found that Raeq had positive significant correlation with the amount of quartz present at the beaches.


2011 ◽  
Vol 26 (2) ◽  
pp. 110-114 ◽  
Author(s):  
Marija Jankovic ◽  
Dragana Todorovic

The natural radioactivity in imported zircon samples used as glaze for ceramic tiles in the ceramics industry has been presented in this paper. The measurements were made by gamma spectrometry with a high purity germanium detector. The average activity concentrations of 238U and 232Th determined in the measured samples (3250 Bq/kg, and 556 Bq/kg, respectively) are much higher than the concentrations found in the Earth?s crust. The activity concentration of 226Ra is also high in all analyzed samples, while 40K was not detected. The gamma index, I, the external hazard index, Hex, the internal hazard index, Hin, and the radium equivalent activity, Raeq, were calculated. Due to relatively high activity concentration level of uranium in imported zircon samples, specific regulations are necessary for zircon compound used in ceramic industry. It can be concluded that the investigated samples can be used as the component of ceramic glaze in the concentrations not above 3%.


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