scholarly journals Application ofin-situgamma-ray spectrometry in the determination of activity concentrations of40K,238U and232Th and mean annual effective dose rate levels in southeastern cities in Nigeria

2005 ◽  
Vol 40 (4) ◽  
pp. 489-501 ◽  
Author(s):  
N. N. Jibiri ◽  
I. P. Farai
Author(s):  
Emilija Fidanchevski ◽  
Biljana Angjusheva ◽  
Vojo Jovanov ◽  
Pece Murtanovski ◽  
Ljubica Vladiceska ◽  
...  

AbstractHuge quantities of fly ash and bottom ash are generated from thermal power plants and it presents great concern for country, mainly due to the environmental effects. In this study, fly ashes and bottom ash were characterized from technical and radiological aspects. Health effect due to the activity of radionuclides 226Ra, 232Th and 40K was estimated via radium equivalent activity (Raeq), external hazards index (Hex), the external absorbed dose rate (D) and annual effective dose rate (EDR). The specific surface area (40.25 m2 g−1), particle density (1.88 g cm−3) and LOI (23.49%) were typical for bottom ash. Siliceous fly ash contained 32% reactive silica. The annual effective dose rate for all ashes is ≤ 0.2 mSv y−1. Both, fly ash and bottom ash present potential secondary raw materials to be used for building purposes as result of their technological and radiological assessment.


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.


2018 ◽  
Vol 106 (2) ◽  
pp. 161-168 ◽  
Author(s):  
Şeref Turhan ◽  
Elif Gören ◽  
Fatma Aysun Uğur ◽  
Muhammet Karataşlı ◽  
Zehra Yeğingil

AbstractIn this study, a detailed γ-ray spectrometer survey was performed to obtain the baseline data on natural and fallout radioactivity in soil samples (10–30 cm depth) collected from Iğdır which is a province in Eastern Anatolia Region of Turkey and located along the border with Armenia. Metsamor Nuclear Power Plant in Eastern Armenia is only about 20 km away from Iğdır province. The average activity concentrations of226Ra,232Th,40K and137Cs in the soil samples were found as 19.1±0.6 (range: 12.8–31.2 Bq kg−1), 21.9±0.6 (range: 11.6–36.8 Bq kg−1), 437.7±10.3 (range: 285.0–613.7 Bq kg−1) and 11.8±1.1 Bq kg−1, (range: 2.5–51.1 Bq kg−1), respectively. The radiological hazards caused by ionizing radiation emitted from these radionuclides on the population living in the region were assessed by estimating radiological parameters such as absorbed γ dose rate in outdoor and the corresponding annual effective dose rate from external exposure, annual effective dose rate from inhalation of radon and excess lifetime cancer risk. The results revealed that there is no significant radiological hazard for human population because the average values of radiological parameters are within the recommended limits.


2014 ◽  
Vol 29 (4) ◽  
pp. 307-312 ◽  
Author(s):  
Abd-Elmoniem Elzain

Exposure to natural sources of radiation, especially 222Rn and its short-lived daughter products has become an important issue throughout the world because sustained exposure of humans to indoor radon may cause lung cancer. The indoor radon concentration level and radon effective dose rate were carried out in the dwellings of Medani, El Hosh, Elmanagil, Haj Abd Allah, and Wad Almahi cities, Gezira State - Central Sudan, in 393 measurements, using passive integrated solid-state nuclear track devices containing allyl diglycol carbonate plastic detectors. The radon concentration in the corresponding dwellings was found to vary from (57 ? 8) Bq/m3 in Medani to 41 ? 9 Bq/m3 in Wad Almahi, with an average of 49 ? 10 Bq/m3. Assuming an indoor occupancy factor of 0.8 and 0.4 for the equilibrium factor of radon indoors, we found that the annual effective dose rate from 222Rn in the studied dwellings ranges from 1.05 to 1.43 mSv per year and the relative lung cancer risk for radon exposure was 1.044%. In this research, we also correlated the relationship of radon concentration and building age. From our study, it is clear that the annual effective dose rate is larger than the ?normal? background level as quoted by UNSCEAR, lower than the recommended action level of ICRP, and less than the maximum permissible dose defined by the International Atomic Energy Agency.


2021 ◽  
Vol 0 (0) ◽  
Author(s):  
Mohammad Wasim ◽  
Sardar Ali Shah ◽  
Arfan Tariq ◽  
Manzoor Ali

Abstract Distribution of natural and anthropogenic radionuclides (226Ra, 232Th, 137Cs and 40K) was determined in 32 samples from Ghizer, an Eastern Hindukush district at an altitude of 2286 m in Pakistan using high resolution gamma-ray spectrometry. Mineralogical analysis by X-ray diffractometry identified quartz, calcite, albite and anorthite as major phases whereas actinolite, chlorite serpentine and kaolinite as minor phases. The activity concentrations for 226Ra, 232Th, 137Cs and 40K varied from 25.2 ± 1.7 to 145.3 ± 10.1 Bq kg−1, 24.9 ± 1.1 to 197 ± 9 Bq kg−1, 2.03 ± 0.21 to 16.7 ± 1.1 and 252 ± 6 to 1433 ± 35 Bq kg−1, respectively. The samples yielded average radium equivalent activity as 178.4 ± 23.3 Bq kg−1. The majority of the samples revealed external hazard index and representative level index less than one. The average air absorbed dose rate was 91.2 ± 13.6 nGy h−1 corresponding to the annual effective dose rate 111.8 ± 17.4 μSv y−1. These values were higher than the world averages for air absorbed dose rate and outdoor annual effective dose rate. Principal component analysis was applied to obtain distribution pattern within the samples and among the radionuclides.


2015 ◽  
Vol 2015 ◽  
pp. 1-5 ◽  
Author(s):  
Ali Abid Abojassim Al-Hamidawi

This paper presents the measurements of thoron and the progeny in fifteen buildings in Kufa Technical Institute, Iraq, from June 2015 to April 2015 using RAD-7 detectors. Also, annual effective dose rate was calculated in all buildings under study. The thoron concentration varies from05.35±0.58 Bq/m3to53.50±1.82 Bq/m3with an average18.39±4.18 Bq/m3. The concentration of thoron daughters was found to vary from 0.14 mWL to 1.44 mWL with an average0.53±0.11 mWL. The annual effective doses due to thoron mainly vary from 0.042 mSv/y to 0.81 mSv/y with an average0.20±0.06 mSv/y. The preliminary results in this study indicate that they may be suitable for evaluating the indoor220Rn and its progeny concentrations whenever the public exposure to220Rn and its progeny is taken into account. During this survey, the continuous difficulty in measuring thoron was also pointed out, due to its short half-life and faults in the measuring system.


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.


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.


Materials ◽  
2020 ◽  
Vol 13 (12) ◽  
pp. 2824
Author(s):  
Tomasz Drzymała ◽  
Aneta Łukaszek-Chmielewska ◽  
Sylwia Lewicka ◽  
Joanna Stec ◽  
Barbara Piotrowska ◽  
...  

The measurements of the specific activity of natural radioactive isotopes of radium (226Ra), thorium (232Th) and potassium (40K) in chosen samples of imported (China, Finland, Spain, India, Sweden) and Polish (Izerski, Karkonosze, Siedlimowicki, Strzegomski, Strzelinski) granites were performed. The measurements were carried out with 2 × 2” NaI(Tl) scintillation detector. The measured specific activity on natural radioactive isotopes were within the following ranges: 5.8–312 [Bq kg−1], 5.5–189 [Bq kg−1] and 109–1590 [Bq kg−1] for 226Ra, 232Th and 40K, respectively. Obtained concentrations of radioactive isotopes allowed to perform the analysis of the exposure of the humans from the ionizing radiation emitted by the granites. The determination of the exposure consisted in the calculation of absorbed gamma dose rate (D) [nGy h−1] for each sample, which fell in the range between 20 and 511 [nGy h−1], annual effective dose rate (AED) [mSv year−1] ranging between 0.10 and 2.50 [mSv year−1], radium equivalent activity (Raeq) [Bq kg−1] with values between 22 and 570 [Bq kg−1], external and internal hazard indices (Hex) and (Hin) falling in the ranges 0.06−1.53 and 0.08–2.41 respectively, as well as gamma (Iγ) and alpha (Iα), representative level indices with values 0.08–2.0 and 0.029–1.56, respectively. Moreover, obtained results were compared with the international standard values given by the European Commission (EC), the United Nations Scientific Committee on the Effects of Atomic Radiation given in UNSCEAR Reports, and the results of research from other laboratories.


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