scholarly journals Environmental dose rate assessment from an active fault zone in Western Anatolia, Turkey: towards retrospective epidemiology

2014 ◽  
Vol 2 (1) ◽  
Author(s):  
Mithat Kiyak ◽  
George S. Polymeris ◽  
Nafiye G. Kiyak
Keyword(s):  
Dose Rate ◽  
Human Life ◽  
Epidemiological Studies ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Western Anatolia ◽  
Gamma Spectrometer ◽  
Radiation Background ◽  
Average Value ◽  
Active Tectonic

In this study we present data regarding natural radioactivity from a populated active tectonic area based on site measurements using a field gamma spectrometer. The results will provide data to the scientists for dating studies as well as epidemiological studies towards ancient human life, also termed as retrospective epidemiology. The study area covers an active tectonic region in western Anatolia surveyed using on-site gamma spectrometer. More than 500 sites were measured across the region on a 150- km grid. Radiation background shows relatively non-homogenous level of radiation in the area. The gamma dose rate measured in Gediz graben was found in the range between 0.8120- 1.7540 mGya–1 (94-203 nGyh–1) with an average value of 1.2292 mGy/a (142 nGyh–1), whereas it was in the range between 0.5530-1.1491 mGy/a (64-133 nGyh–1) with an average value of 0.8397 mGy/a (97 nGyh–1) across Buyuk Menderes graben. The relative contribution of 238U decay chain to gamma dose rate is between 0.2002- 0.4630 mGya–1, of 232Th decay series is 0.3089- 0.8136 mGya–1, and of 40K is 0.1270- 0.3468 mGya–1 in the whole studied area. The average annual effective dose equivalents from the calculated outdoor terrestrial gamma radiation was between 90-215 μSva–1, above world average of 70 μSv per year, and the measured outdoor dose rate (terrestrial plus cosmic) on the ground was between 133-257 μSva–1. The significance of all these numbers is discussed in the framework of epidemiological studies, in order to correlate these enhanced dose rate values directly to specific diseases such as cancer.

scholarly journals A preliminary study of geological variation of in-situ gamma dose rate in the vicinity of coal-fired power plants

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 ◽  
...  
Keyword(s):  
Dose Rate ◽  
Power Plants ◽  
Fossil Fuels ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Coal Consumption ◽  
Dose Rates ◽  
Average Value ◽  
Effective Doses ◽  
The Difference

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.

Terrestrial gamma dose rate, radioactivity and radiological hazards in the rocks of an elevated radiation background in Juban District, Ad Dali’ Governorate, Yemen

2016 ◽  
Vol 36 (1) ◽  
pp. 163-177 ◽  
Author(s):  
Wedad Ali Abdurabu ◽  
Ahmad Termizi Ramli ◽  
Muneer Aziz Saleh ◽  
Arien Heryansyah ◽  
Anees Alnhary ◽  
...  
Keyword(s):  
Dose Rate ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Radiation Background ◽  
Radiological Hazards

scholarly journals Measurement of radioactivity in an elevated radiation background area of Western Ghats

2014 ◽  
Vol 29 (2) ◽  
pp. 128-134 ◽  
Author(s):  
P.K. Manigandan ◽  
Chandar Shekar
Keyword(s):  
Dose Rate ◽  
Western Ghats ◽  
Activity Concentration ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Hazard Indices ◽  
Radiation Background ◽  
Naturally Occurring ◽  
Naturally Occurring Radionuclides ◽  
Background Area

As part of monitoring the exposure of the general public to natural radioactivity, the activity concentration of naturally occurring radionuclides in soil samples in an elevated radiation background area of Western Ghats was determined using gamma-ray spectrometry. Average values of the activity concentration of radionuclides, outdoor terrestrial gamma dose rate, annual effective dose equivalent and radiation hazard indices from soil activity were estimated. The activity concentrations of 232Th and average outdoor terrestrial gamma dose rate were found to be higher than the world average, possibly affecting the Western Ghats environment in general. Therefore, radiological risks to the general population from ionizing radiation from the naturally occurring radionuclides in the soil are considered to be significant. How- ever, other radiological hazard indices were found to be within permissible limits.

ASSESSMENT OF INDOOR GAMMA RADIATION AND DETERMINATION OF EXCESS LIFETIME CANCER RISK IN TEHRAN IN WINTER AND SPRING 2017

2018 ◽  
Vol 184 (2) ◽  
pp. 148-154 ◽  
Author(s):  
Marjan Hashemi ◽  
Leila Akhoondi ◽  
Mohammad Hossien Saghi ◽  
Akbar Eslami
Keyword(s):  
Cancer Risk ◽  
Gamma Radiation ◽  
Dose Rate ◽  
Annual Effective Dose ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Lifetime Cancer Risk ◽  
Average Value ◽  
Excess Lifetime Cancer Risk

Abstract Natural radiation is a feature of the environment in which we live. One of the contributions of human exposure to ionizing radiation due to natural sources arises from gamma radiation. Therefore, present study was aimed to evaluate and map indoor gamma dose rate in Tehran. The corresponding annual effective dose (AED) and excess lifetime cancer risk (ELCR) were also calculated. All measurements were performed by a Geiger Muller detector in 43 dwellings in Tehran. The average indoor gamma dose rate in Tehran was appointed as 343.2 nGy/h. AED and ELCR were calculated as 2.4 mSv and 10.3 × 10−3, respectively. The evaluated indoor gamma dose rate and calculated AEDs and lifetime cancer risk were found higher than the world average value.

Radon concentration in water, soil and sediment of Hemavathi River environments

2017 ◽  
Vol 27 (5) ◽  
pp. 587-596 ◽  
Author(s):  
Kaliprasad C. Shivanandappa ◽  
Narayana Yerol
Keyword(s):  
Dose Rate ◽  
Radon Concentration ◽  
Mean Value ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Average Value ◽  
Effective Doses ◽  
The Mean ◽  
Radon In Water ◽  
Soil And Sediment

The present paper discusses the systematic study on gamma dose rate, radon exhalation, radium content in soil and sediment and radon concentration in water of Hemavathi River environments. The Gamma dose rate in the air in the study area varied from 98 to 202 nGy h−1 with mean value 145 nGy h−1. The measured dose rate was above the world and Indian average. The mean value of radium activity in soil and sediment was found to be 366.61 and 328.36 mBq kg−1, respectively. The mean value of radon in soil and sediment was found to be 373.90 and 334.90 Bq m−3, respectively. The radon concentration of water ranges from 0.20 to 1.60 kBq m−3 with an average value of 0.67 kBq m−3. The radon in water contributes to dosage in stomach and lungs. The effective doses of radon were calculated and compared with international recommended values. The results show that sediment and water are safe to use for construction and drinking purpose.

scholarly journals Inter-calibration of gamma dose rate detectors on the European scale

2009 ◽  
Vol 44 (5) ◽  
pp. 777-784 ◽  
Author(s):  
U. Stöhlker ◽  
M. Bleher ◽  
T. Szegvary ◽  
F. Conen
Keyword(s):  
Dose Rate ◽  
Gamma Dose ◽  
Gamma Dose Rate

Primary Shielding Design for an Optimized Molten Salt Reactor

2013 ◽  
Author(s):  
Zhihong Zhang ◽  
Xiaobin Xia ◽  
Jianhua Wang ◽  
Changyuan Li
Keyword(s):  
Molten Salt ◽  
Dose Rate ◽  
Gamma Dose ◽  
Acceptable Level ◽  
Gamma Dose Rate ◽  
Molten Salt Reactor ◽  
Thermal Shield ◽  
Oak Ridge ◽  
The Core ◽  
Shielding Design

Molten salt reactor (MSR) system, a candidate of the Generation IV reactors, has inherent safety, on-line refueling and good neutron economy as typical advantages. An optimized MSR is developed by changing the size of fuel channel and the graphite-to-molten salt volume radio, based on the Molten-Salt Reactor Experiment (MSRE), which was originally developed at the Oak Ridge National Laboratory (ORNL). In this paper, shielding calculations for the optimized MSR are presented. The goal of this study is to determine the necessary shielding to decrease the neutron and gamma dose rate to the acceptable level according to national regulations. The operating temperature of the optimized MSR is designed in the range of 500 °C–700 °C, heat removal is also considered in the shielding design. The shielding calculations are carried out by using Monte Carlo method. The shielding system of the optimized MSR consists of 7 zones: the core, the core can, the reactor vessel, the thermal shield, the reactor cell containment, the shield tank and the concrete wall. The combinations of shielding materials in the thermal shield were evaluated. The thermal shield filled with carbon steel balls and circulating water gets an excellent shielding performance and heat removing effects. The neutron spectra and dose distributions, as well as the energy deposition over different shields have been analyzed. The total neutron dose rate outside the thermal shield is attenuated by a factor of about 104, and the gamma dose rate by a factor of about 103. These results show that the shielding design could low dose rate to an acceptable level outside the shielding and far below dose limit required.

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