scholarly journals Measuring the concentrations of natural radioactive isotopes and radiation dose rates for Missan Province

2019 ◽  
Vol 13 (27) ◽  
pp. 63-69
Author(s):  
Ahmed A. Hussein Zarkooshi

This research included measuring the concentrations of natural radioactive isotopes U-238 and Th-232 and radiation dose rates for selected areas of Missan province, GR-460 system was used which has the potential to measure the concentrations of natural radioactive isotopes in (ppm) unit and measuring the radiation dose rates in μR/h unit. It was also used with the system the mobile device FH-40 which measures the radiation dose rates in units μSμ/h the measurement results showed the absence of a significant increase in the U-238 and Th-232 concentration where the concentration of isotopes of U-238 and natural Th-232 (3.35-5.46) ppm respectively it is authorized and universally accepted. In terms of radiation dose rates it ranged between 45-65ոSv/հ by GR-460 system and FH-40 device and all these values are within the natural background radiation. Except for one outlying villages that affiliate to the Kahla area were found the radioactive source type 137Cs was left in a swamp of water rancid. Dose rate reached about 6 meters distance from the source 5.3 mSv/h by FH-40 device and GR-460 system 90.6 μR/h where equivalent 815 ոSvհ. The radioactive source has been transferred safely to the main store in AlTuwaitha site.

2019 ◽  
Vol 184 (3-4) ◽  
pp. 290-293 ◽  
Author(s):  
Darwish Al-Azmi ◽  
Sudeep Kumara ◽  
M P Mohan ◽  
N Karunakara

Abstract Elevated levels of natural background radiation due to scattered patches of monazite sand around the beaches of Mangalore, India, have been reported earlier. A comparative study of gamma dose rates was performed in both normal background and high natural background radiation areas around Mangalore using different types of portable gamma dosimeters. In addition to this, gamma-ray energy spectra were acquired, in situ, using a NaI(Tl) based portable gamma spectrometer. Soil and sand samples were collected for laboratory analysis with HPGe detectors. Measurements were carried out during the years 2016–18 revealed that in majority of the locations the gamma dose rates were similar to the normal background regions, whereas, in certain locations the dose rates were higher with values up to 530 nSv/h.


2011 ◽  
Vol 14 (4) ◽  
pp. 16-23
Author(s):  
Thanh Thien Tran ◽  
Tao Van Chau ◽  
Tam Duc Hoang ◽  
Yen Thi Hong Vo

In the analysis of environmental radioactive isotopes using gamma spectrometry, natural background radiation is an important parameter related to the analytical results directly. Therefore, in this work, the influence of natural background radiation was studied for two models: with and without shielding of gamma spectrometer system. The initial results showed that the minimum detectable activity (MDA) of radionuclides such as 234Th, 226Ra, 212Pb, 208Tl, 40K, 214Pb, 214Bi, 228Ac have the difference of two models from 10% to 503%. This is the basis for researches to improve the lead shielding chamber in the future.


BIBECHANA ◽  
2018 ◽  
Vol 16 ◽  
pp. 187-195
Author(s):  
Parkash Pantha ◽  
Tanka Prasad Bhusal ◽  
Budha Ram Shah ◽  
Rajendra Prasad Koirala

The study of natural background radiation dose at thirty two locations of Kathmandu valley has been done successfully using the instrument Radalert 100. The average dose rates and annual effective dose were measured. From the measurements, the least value of average dose rate was found to be (22.3±3.9)×10-3 mR/hr for Sundhara and the greatest value of average dose rate was  found to be (37.7±7)×10-3 mR/hr for Budhanilkantha 3.  As per the annual effective dose, the least value was 0.391 mSv/yr for Sundhara and the greatest value was 0.661 mSv/yr for Budhanilkantha 3. The average annual effective dose of Kathmandu valley was 0.475 mSv/yr ranging from 0.391 mSv/yr to 0.661 mSv/yr. The values thus obtained were compared to the worldwide average value of annual effective dose, 0.48 mSv/yr. Also, the obtained values were compared to the legal dose limit (annual effective dose), 1 mSv/yr set by International Commission on Radiological Protection (ICRP) for non-radiation workers and members of public. Among these thirty two locations, eight locations were chosen such that they had larger range of the observed dose rates. Those eight locations were re-observed. Further, Chi-square test was carried out to test whether the observed dose rates were following normal distribution or not. From the calculation, it was observed that the observed dose rates were following the normal distribution.BIBECHANA 16 (2019) 187-195


2020 ◽  
Vol 70 (340) ◽  
pp. 233 ◽  
Author(s):  
A. Shahrokhi ◽  
M. Adelikhah ◽  
S. Chalupnik ◽  
E. Kocsis ◽  
E. Toth-Bodrogi ◽  
...  

In this study, mass activity of naturally occurring radioactive materials were measured in twenty-three building material samples, use extensively in the area exposed to a high level of natural background radiation (Mahallat, Iran), to determine the radioactivity index and changes to the level of indoor gamma radiation. The mass activity of 232Th, 226Ra and 40K were within the ranges from 18 ± 3 to 44 ± 10 Bq/kg (average of 27 ± 6 Bq/kg), 22 ± 5 to 53 ± 14 Bq/kg (average of 34 ± 6 Bq/kg) and 82 ± 18 to 428 ± 79 Bq/kg (average of 276 ± 58 Bq/kg), respectively. The gamma dose rates for population were estimated between 48 ± 9 and 111 ± 26 nGy/h with exception of radon exhalation from building materials. Since the air kerma rate in the town varies from 0.8 to 4 μGy/h, the attenuation coefficient was calculated for buildings made of the aforementioned materials. Additionally, the annual gamma radiation doses for inhabitants were calculated based on time spent outdoors and indoors.


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