ELEVATION OF GAMMA DOSE RATE BY CONSTRUCTION OF THE ASIAN HIGHWAY 3 (AH3) BETWEEN ULAANBAATAR AND SAINSHAND, MONGOLIA

2018 ◽  
Vol 184 (1) ◽  
pp. 127-134 ◽  
Author(s):  
Yasutaka Omori ◽  
Atsuyuki Sorimachi ◽  
Manlaijav Gun-Aajav ◽  
Nyamdavaa Enkhgerel ◽  
Galnemekh Oyunbolor ◽  
...  

Abstract The present study aimed at examining changes of gamma radiation level associated with road construction in Mongolia. A car-borne survey of gamma dose rate was made for a paved, ~450-km long part of the Asian Highway 3 between Ulaanbaatar and Sainshand. The gamma dose rates ranged from 48 to 173 nGy/h. Elevation of the gamma dose rates was observed only on a 86-km long segment of the survey route which was newly constructed from 2011 to 2013. The gamma dose rates over the newer paved segment were twice as high as those over the bare dirt surface alongside it. Outdoor measurements of gamma-ray pulse height distributions also indicated an abundance of natural radionuclides, especially 232Th-series elements in road materials. These findings suggest that the gamma dose rates were elevated by introduction of road materials containing large amounts of natural radionuclides.

Author(s):  
P. L. Winston ◽  
J. W. Sterbentz

Gross gamma-ray dose rates from six spent TRIGA fuel elements were measured and compared to calculated values as a means to validate the reported element burnups. A newly installed and functional gamma-ray detection subsystem of the In-Cell Examination System was used to perform the measurements and is described in some detail. The analytical methodology used to calculate the corresponding dose rates is presented along with the calculated values. Comparison of the measured and calculated dose rates for the TRIGA fuel elements indicates good agreement (less than a factor of 2 difference). The intent of the subsystem is to measure the gross gamma dose rate and correlate the measurement to a calculated dose rate based on the element s known burnup and other pertinent spent fuel information. Although validation of the TRIGA elements’ burnup is of primary concern in this paper, the measurement and calculational techniques can be used to either validate an element’s reported burnup or provide a burnup estimate for an element with an unknown burnup.


2020 ◽  
Vol 108 (11) ◽  
pp. 913-921
Author(s):  
Nesli Bingöldağ ◽  
Pelin Otansev

AbstractThe concentrations of 226Ra, 232Th, 40K and 137Cs radionuclides in soil samples collected from 323 different regions of Nevşehir province were determined by using a gamma spectrometer with an HPGe detector. The mean gamma activity concentrations (ranges) of 226Ra, 232Th, 40K and 137Cs for districts were determined as 49.45 (7.40–193.90), 54.08 (<2.8–122.50), 698.43 (37.67–1370.20) and 8.26 (0.10–52.60) Bq kg−1, respectively. The mean activity concentrations of 226Ra, 232Th and 40K were higher than the world mean value. According to Kolmogorov–Smirnov test, distributions of 226Ra, 232Th and 137Cs show log-normal distributions. Whereas, 40K shows normal distribution. The mean radium equivalent activity was 181.68 Bq kg−1 which is lower than the recommended maximum value of 370 Bq kg−1. The mean external terrestrial gamma dose rate was found to be 85.12 nGy h−1. The calculated external hazard value was 0.49 and within the acceptable limit which is less than unity (Hex ≤ 1). Thermo Scientific RadEye NBR detector was used to determine environmental gamma dose rates. The gamma dose rates were measured at 445 points at a height of 1 m from land surface. The mean outdoor gamma dose rate (range) was found as 150.13 (50–480) nGy h−1. This mean value was found higher than world mean value. The fact that most of the Nevşehir province is based on volcanic rocks explains why the gamma dose rates are high.


2018 ◽  
Vol 184 (1) ◽  
pp. 116-126 ◽  
Author(s):  
Yasutaka Omori ◽  
Takuma Ishikawa ◽  
Atsuyuki Sorimachi ◽  
Tetsuo Ishikawa

Abstract The spatial distribution of ambient gamma dose rates in a high-rise steel-reinforced concrete building in Fukushima, Japan, was examined relative to the gamma-ray emissions from building materials and radionuclides derived from the 2011 nuclear accident. The results revealed the minor role of accident-derived radionuclides in ambient gamma dose rates ~7 y after the accident. The ambient gamma dose rates were higher in the upper floors because of gamma-ray emissions from natural radionuclides in the floor slabs. The fractional contribution of natural radionuclides to the ambient gamma dose rates indicated compositional differences in concrete between the upper- and lower-floor slabs.


2019 ◽  
Vol 184 (3-4) ◽  
pp. 510-513
Author(s):  
Y Omori ◽  
S Inoue ◽  
T Otsuka ◽  
Y Nagamatsu ◽  
A Sorimachi ◽  
...  

Abstract In the present study, variations in ambient gamma dose rate associated with snow cover were examined in a radioactive-contaminated site in Fukushima Prefecture, Japan. The ambient gamma dose rates decreased with increasing snow depth. The reduction trends were different between fresh snow (0.1–0.2 g/cm3) and granular snow (0.3–0.4 g/cm3) depending on snow density. Snow cover water content (snow water equivalent) calculated from snow depth and density was a key parameter governing the reduction in the ambient gamma dose rate. The ambient gamma dose rates reduced to 0.6 and 0.5 at 4 g/cm2 and 8 g/cm2 of snow water equivalent, respectively. Based on gamma-ray flux density distributions, the ambient gamma dose rates from the primary gamma rays decreased more compared to those from scattered gamma rays due to snow cover.


2012 ◽  
Vol 39 (1) ◽  
pp. 40-47 ◽  
Author(s):  
Guillaume Guérin ◽  
Norbert Mercier

Abstract The determination of gamma dose rates is of prior importance in the field of luminescence dating methods. In situ measurements are usually performed by the insertion of dosimeters or a portable gamma spectrometer cell in sediments. In this paper, Monte-Carlo simulations using the Geant4 toolkit allow the development of a new technique of insitu gamma dose rate evaluations: a spectrometer cell is placed on the surface of sediments under excavation to acquire successive spectra as sediments are removed by excavations. The principle of this non-invasive technique is outlined and its potential is discussed, especially in the case of environments in which radioelements are heterogeneously distributed. For such cases, a simple method to reconstruct gamma dose rate values with surface measurements using an attenuator is discussed, and an estimation of errors is given for two simple cases. This technique appears to be applicable, but still needs experimental validation.


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.


Author(s):  
P. K. Manigandan ◽  
K K Natrajan

Assessments of naturally occurring radionuclides in soil collected from a tropical rainforest forest of western Ghats, India were conducted. These radionuclides were distributed unevenly in the forest soil. For all soil samples, the terrestrial gamma dose rate and the corresponding outdoor annual effective dose equivalents were evaluated. The activity concentration of 232Th and average outdoor gamma dose rates were found to be higher than the global average which appears to affects Western Ghats environment in general, the radiological hazard indices were found to be within the International Commission on Radiological Protection recommended limits. Hence, obtained results for natural radionuclides in the forest soils were within the range specified by UNSCEAR (2000) report for virgin soils except 232Th.


2021 ◽  
Vol 23 (4) ◽  
pp. 1810-1817
Author(s):  
Vu Ngoc Ba ◽  
Bui Ngoc Thien ◽  
Truong Thi Xuan Truong ◽  
Nguyen Quang Dao ◽  
Le Xuan Thuyen ◽  
...  

Introduction: The utilization of fossil fuels in coal-fired power plants (CFPPs) for electricity generation could lead to the release of additional natural and artificial radioisotopes into the surrounding environment and consequently, increase the gamma dose rate at these areas. Methods: In this study, the geological variation of gamma dose rate in the vicinity of Duyen Hai CFPP complex and Vinh tan CFPP complex were evaluated. Results: The obtained gamma dose rates were in the range from 0.07 to 0.22 μSv h-1 with the average value of 0.13 μSv h-1 for Duyen Hai area and in the range from 0.14 to 0.34 μSv h-1 with the average value of 0.21 μSv h-1. The results indicated that the gamma dose rate in Vinh tan area is higher than the corresponding value of Duyen Hai area. Both natural aspects, such as the geological differences as well as geomorphology and weathering process, and anthropogenic aspects, such as the difference in operational scale, coal consumption and ash discharge between Duyen Hai and Vinh Tan CFPP complex, might significantly contribute to the variation of gamma dose rate in the investigated locations. Conclusion: Overall, the calculated outdoor annual effective doses of two studied areas showed that the radiological impacts of both Duyen Hai and Vinh Tan CFPP complex to the environment and public health are negligible.


Sign in / Sign up

Export Citation Format

Share Document