Distribution of naturally occurring radionuclides in soil around a coal-based power plant and their potential radiological risk assessment

2019 ◽  
Vol 107 (3) ◽  
pp. 243-259 ◽  
Author(s):  
Md. Ahosan Habib ◽  
Triyono Basuki ◽  
Sunao Miyashita ◽  
Wiseman Bekelesi ◽  
Satoru Nakashima ◽  
...  

Abstract Coal-fly-ash is one of the major byproducts of coal-based power plant in which naturally occurring radioactive materials (NORMs) are drastically enriched compared to those of feed coals. Thus, improper management of fly-ash may introduce additional radioactivity to the surrounding environment and cause radiological risk. So, in order to study the distribution of radionuclides in soil around a coal-based power plant and to evaluate their radiological risk, soil, coal and fly-ash samples were analyzed by using a HPGe detector for U-238, Ra-226, Th-232 and K-40 radioactivity concentrations. Furthermore, soil minerals were also studied by X-ray diffractometer to assess the mineralogical provenance of the radionuclides. Mean radioactivity concentrations (in Bq·kg−1) of U-238, Ra-226, Th-232 and K-40 in soil samples are 102.9±41.4, 63.6±7.4, 103.4±13.9 and 494.2±107.5, respectively which are comparatively higher than the typical world mean value. Elevated levels of radioactivity are likely due to the presence of illite, kaolinite, monazite, rutile and zircon minerals in the soil samples rather than technogenic contributions from the power plant. Furthermore, mean soil contamination factor (CF) are close to unity and mean pollution load index (PLI) is below unity while the average radium equivalent activity (Raeq in Bq·kg−1), external hazard index (Hex), absorbed γ dose rate (D in nGyh−1), annual effective dose rate (E in mSv·y−1) and excess lifetime cancer risk (ELCR in Sv−1) are 249.5±21.7, 0.67±0.06, 114.2±9.4, 0.20±0.02, 4.9×10−4±0.4×10−4, respectively, which are within the permissible limit. Thus, in terms of radioactivity concentrations and associated environmental and radiological indices, the effect of the power plant is insignificant.

2021 ◽  
Vol 7 (2) ◽  
pp. 89-96
Author(s):  
P. Lamichhane ◽  
B. Rijal ◽  
P. Shrestha ◽  
B. R. Shah

This study was conducted to determine the amount of naturally occurring radioactivity in the soil of Nepal's Kathmandu valley. The activity of naturally occurring radionuclides was determined in these soil samples using a sodium iodide detector. Activity concentrations of 238U, 232Th, and 40K were found in the range: 32.00-111.38 Bq kg-1, 33.52-130.04 Bq kg-1, and 342.50-897.71 Bq kg-1, respectively. These values are well within the permissible range as recommended by UNSCEAR. The soil samples with the highest activity concentrations were primarily found in the valley's northern region. The activity concentrations were also used to calculate the radiation hazard indices: the mean value obtained were 96.63 nGy hr-1 for Absorbed Gamma Dose Rate in Air, 200.04 Bq kg-1 for Radium Equivalent Activity, the 0.12 mSv yr-1 for Annual Effective Dose, and 0.55 for External Hazard Index. These calculated hazard indices were used to estimate the potential radiological health risk from the soil, and the dose rates associated with it were significantly less than their permissible limit. The overall findings indicate no radiological threat to the population's health in the study area. Additionally, the findings of this study provide baseline information on potential radionuclides that contribute mostly for radiation exposure from natural sources.


Author(s):  
Iman Tarik Al-Alawy ◽  
Monar Deya Salim

The specific activity of natural radionuclides in 24 soil samples collected from antiquities area of Ur city in Dhi-Qar province (31.0459863N, 46.2534257E) in southern Iraq have been studied and evaluated. Experimental results were obtained by using a Gamma ray spectrometer analysis system consists of a scintillation detector Sodium Iodide activated by Thallium NaI(Tl) of (3"×3") crystal dimension at the laboratory of radiation detection and measurement in Science Collage, University of Kufa. The spectrometer has been calibrated for energy by acquiring a spectrum from four standard sources of gamma radiations supplied by spectrum techniques (LLC). The measuring time of all soil samples is 18000 seconds; it was found that, the soil specific activity ranges from 29.93±2.97 to 9.99±2.56Bq/kg for 238U, from 25.66±2.55 to 7.77±2.24Bq/kg for 232Th and from 397.38±12.06 to 215.75±8.91Bq/kg for 40K, with mean values of 17.9±3.02Bq/kg, 13.66±2.41Bq/kg and 314.62±11.3Bq/kg, respectively. The results have been compared with the acceptable data of the worldwide literatures. In order to evaluate the radiological hazard of the natural radioactivity, the radium equivalent activity (Raeq), the gamma absorbed dose rate (AD), the annual effective dose rate and the both (external and internal) hazard index have been calculated and compared with the acceptable values of the worldwide average (UNSCEAR 2000).


2020 ◽  
Vol 65 (1) ◽  
pp. 1-18
Author(s):  
Branislava Mitrovic ◽  
Dragana Todorovic ◽  
Jelena Ajtic ◽  
Borjana Vranjes

This review paper discusses the content of natural (40K, 238U, 226Ra, and 232Th) and artificial (137Cs) radionuclides in the soil of the mountains of Maljen, Tara and Kopaonik in the Republic of Serbia over 2002-2015. In addition, the paper gives radiation hazard parameters, i.e., radium equivalent activity, absorbed dose rate, annual effective dose equivalent, external hazard index, annual gonadal dose equivalent, and excess lifetime cancer risk outdoors that we calculated from the obtained content of the natural radionuclides in the soil samples. We compared the parameters to previously published results for different parts of the country and looked into the radioecological status of the investigated areas.


Atmosphere ◽  
2021 ◽  
Vol 12 (8) ◽  
pp. 1024
Author(s):  
Phachirarat Sola ◽  
Uthaiwan Injarean ◽  
Roppon Picha ◽  
Chutima Kranrod ◽  
Chunyapuk Kukusamude ◽  
...  

A total of 223 sand samples collected from seven provinces in Northeastern Thailand were analyzed for their gamma radioactivity from naturally occurring radioactive materials (NORMs), and the data were used to calculate the concentrations of Ra-226, Th-232, and K-40. Radiological safety indicators such as the indoor external dose rates (Din), the annual indoor effective dose (Ein), the activity concentration index (I), the radium equivalent activity (Raeq), the external hazard index (Hex), the internal haphazard index (Hin), and the excess lifetime cancer risk (ELCR) were calculated. The activity concentrations were found to be 36 ± 10 Bq/kg for Ra-226, 2.64 ± 0.58 Bq/kg for Th-232, and 323 ± 168  Bq/kg for K-40. Din is 62 ± 23 nGy/h. The Ein is 0.30 ± 0.11 mSv/y. The activity concentrations and other indicators were reported by each province and compared with the safety standards and are found to be within the safe limits in this study. The results can be used to develop the standard guideline levels for choosing building materials in Thailand.


2021 ◽  
Author(s):  
Mahmoud A. Hussein ◽  
Mahmoud khattab ◽  
Waleed A. El-Said ◽  
Neveen S. Abed ◽  
A. F. Tawfic

Abstract Radioactivity of U, Th series and 40K in the collected samples from Abu Garadi area were measured using Hyper Pure Germanium detector Gamma spectrometer (HPGe). 232Th, 226Ra, 40K and 238U contents were determined in the different samples that indicating high uranium high thorium type of these granites. The activity concentrations of 232Th, 238U, 234U/238U activity ratio of the studied altered granites ranged between 1.98 to 4.25 with 2.89 as an average, indicating that the samples passed from the incipience of the oxidation-reduction zone (234U/238U=1.98) to the reduction zone (234U/238U= 4.52). 238U/235U activity ratios showed broad range as a result of the alteration processes. 226Ra and 40K are very important in determination of different environmental hazard impacts. The activity concentrations average of 238U, 232Th, 226Ra and 40K were 6553.7 ± 3.1 Bq kg− 1, 3944 ± 0.9 Bq kg− 1 201.3 ± 1.1 Bq kg− 1 and 619.4 ± 0.02 Bq kg− 1. The absorbed gamma dose rate (D), external hazard index (Hex), annual effective dose rate equivalent, radium equivalent (Raeq), internal hazard index (Hin), gamma index (Iγ) as well as Excess Lifetime Cancer Risk (ELCR) were applied based on the measured radionuclide concentration of the 238U, 232Th, 226Ra and 40K.


2014 ◽  
Vol 979 ◽  
pp. 35-38
Author(s):  
Prasong Kessaratikoon ◽  
Ruthairat Boonkrongcheep ◽  
Supphawut Benjakul ◽  
Suchin Udomsomporn

The specific activity of the natural (40K, 226Ra and 232Th) and anthropogenic (137Cs) radionuclides have been studied and evaluated for 97 surface soil samples collected from 7 districts of Phang Nga province in the south of Thailand. High-purity germanium (HPGe) detector and gamma ray spectrometry analysis system were employed to measure and analyze the experimental results. It was found that, the ranges of specific activities of 40K, 226Ra, 232Th and 137Cs in surface soil samples are 251.50 – 15740.34, 15.21 – 791.42, 18.14 – 854.34 and < 0.33 – 16.91 Bq/kg with average values are 2886.77 ± 225.93, 165.71 ± 8.45, 160.36 ± 7.93 and 5.76 ± 2.49 Bq/kg, respectively. The results were also compared with some research data in national and global radioactivity measurement and evaluations. Furthermore, the radiological hazards of Phang Nga province were calculated through the radium equivalent activity (Raeq), the external hazard index (Hex), the gamma absorbed dose rate (D) and the annual effective dose rate (AEDout) and also compared with research data in the south of Thailand and the safety limits recommended values by United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). Moreover, the radioactive contour maps of the natural (40K, 226Ra and 232Th) and anthropogenic (137Cs) radionuclides have been also created for the investigated area.


2018 ◽  
Vol 106 (11) ◽  
pp. 927-937 ◽  
Author(s):  
Sema Arıman ◽  
Hasan Gümüş

Abstract Artificial and natural radionuclide pollutants of the marine environment have been recognized as a serious environmental concern. In this study, the activity concentrations of terrestrial and anthropogenic radionuclides in the soil and sediment samples collected from Bafra Kızılırmak Delta were measured by using gamma spectrometry with an NaI (Tl) detector. The average specific of activity concentrations for 238U, 232Th and 40K were found to be 28.59, 17.48 and 150.59 Bq kg−1, respectively. On the other hand, 137Cs was also measured in some samples. 137Cs (t1/2=30.17 years) is a man-made radionuclide released from nuclear fission and activation processes. It has a mean value of 5.32 Bq kg−1. From the activity concentrations, the radium equivalent activity (Raeq), the absorbed gamma dose rates (DR), the annual gonadal dose equivalent, annual effective dose equivalent, internal (Hin), external hazard index (Hex) and excess lifetime cancer risk were estimated. This study can be used as a base line for future investigations and the data obtained in this study may be useful for natural radioactivity mapping and also be used as a reference data for monitoring possible radioactivity pollutions in future.


2020 ◽  
Author(s):  
Aurélie Diacre ◽  
Anne-Lare Faure ◽  
Agnès Moureau ◽  
Olivier Marie ◽  
Nina Griffiths ◽  
...  

&lt;p&gt;The Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident that occurred in March 2011 released significant quantities of radionuclides in the environment. So far, most of the research focused on radio-cesium and rarely on actinides. Until now, most of the studies on uranium and plutonium released by FDNPP were conducted on bulk environmental samples (soil, sediment, biota, etc.) and rarely on individual particles The investigation of individual particles allows working on the FDNPP signature alone compared to studies of bulk material which may also incorporate the signature of global fallout. Accordingly, the objective of the current research is to identify and characterize actinide-bearing particles in soil samples collected in the vicinity of FDNPP to get a better understanding of their formation mechanisms and of their fate in the environment. In order to identify and locate actinide-bearing particles in soil samples, we developed and implemented a method based on alpha-autoradiography (Jaegler et al., 2019), which allows identifying and locating specifically alpha-emitters, including plutonium isotopes 239Pu, 240Pu and 241Pu using a CR39 SSNTD device (Solid State Nuclear Tracks Detector).&lt;/p&gt;&lt;p&gt;Before alpha-autoradiography samples were dried, grinded with an agate mortar and sieved to several cutoffs: 1mm, 700&amp;#181;m, 400&amp;#181;m, 200&amp;#181;m, 100&amp;#181;m and 63&amp;#181;m. Cutoffs were chosen according to the sizes of actinide-bearing particles detected by Satou et al (2018). The absence of significant loss of uranium particles by the sieving process was demonstrated by the analysis of a test soil sample with a &lt;sup&gt;137&lt;/sup&gt;Cs activity below 650 Bq/kg spiked with depleted uranium reference particles. After sieving, the test sample was deposited onto a carbon planchet for secondary ion mass spectrometry analysis in order to determine the particle recovery yield.&lt;/p&gt;&lt;p&gt;Then, the detection of actinide-bearing particles by means of alpha autoradiography was performed on various soil samples collected in the vicinity of FDNPP. Longer exposure times logically improve the detection efficiency of alpha-emitters-bearing particles. However, the exposure time should not exceed two months to limit the impact of emissions from naturally-occurring alpha-emitters.&lt;/p&gt;&lt;p&gt;We will present here the first results of detection of alpha-emitting particles in the analyzed soil samples. &amp;#160;Relative impacts of naturally-occurring alpha-emitters (&lt;sup&gt;234&lt;/sup&gt;U/&lt;sup&gt;238&lt;/sup&gt;U, &lt;sup&gt;235&lt;/sup&gt;U, &lt;sup&gt;232&lt;/sup&gt;Th and daughter nuclides) and of plutonium isotopes on alpha-radiography trace observation will be discussed.&lt;/p&gt;&lt;p&gt;The next steps of this study will be to develop and implement methods to sample and isolate alpha-emitting particles from the soil matrix and to characterize them in size, morphology, elemental and isotopic compositions. Full characterization of individual particles will be very helpful to determine their origin and to provide an understanding of their formation process and to determine their mobility and life-duration in the environment.&lt;/p&gt;&lt;p&gt;References:&lt;/p&gt;&lt;ol&gt;&lt;li&gt;H. Jaegler, F. Pointurier, et al., 2019. Method for detecting and characterising actinide-bearing micro-particles in soils and sediment of the Fukushima Prefecture, Japan. Journal of Radioanalytical and Nuclear Chemistry, 321 (2019), 57&amp;#8211;69. doi:10.1007/s10967-019-06575-w&lt;/li&gt; &lt;li&gt;Y. Satou, K. Sueki,et al., 2018. Analysis of two forms of radioactive particles emitted during the early stages of the Fukushima Dai-ichi Nuclear Power Station accident. Geochemical Journal, 52 (2018), 1-7. doi:10.2343/geochemj.2.0514.&lt;/li&gt; &lt;/ol&gt;


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.


Sign in / Sign up

Export Citation Format

Share Document