Radioactivity Levels Research Articles

Evaluation of the Risk Associated with Drinkable Water Sources Through Analysis of Gross Alpha and Beta Radioactivity Levels in Chosen Locations, Mubi – North

Ionizing radiation refers to a form of radiation with sufficient energy to dislodge tightly bound electrons from atoms, resulting in the formation of ions. It encompasses alpha particles, beta particles, and gamma rays. Exposure to ionizing radiation, especially through ingestion, can have detrimental effects on living organisms, including humans. The primary goal of this research is to measure and analyze the levels of alpha and beta radiation in water samples, using the obtained results to evaluate radiation concentrations. Water samples were collected from five different locations within Mubi-North Metropolis and analyzed using a desktop Alpha/Beta counting machine or detector (MPC 2000B-DP). The analysis results present the alpha and beta radiation activities in each sample location. For example, alpha activities ranged from 0.009844 Bq/L to 0.1821 Bq/L, and beta activities ranged from 0.04922 Bq/L to 10.21 Bq/L across different locations. Sample D recorded the highest alpha effective equivalent dose of 0.037mSv/y, while the lowest dose of 0.002mSv/y was recorded from sample D. Sample C had the highest beta effective equivalent dose of 5.143mSv/y, and the lowest dose of 0.329mSv/y was recorded from sample E. Sample C also recorded the highest total effective dose of 516mSv/y, while the lowest dose of 0.34mSv/y was from sample E. Only sample D exceeded the recommended screening level of 0.1mSv/y for Alpha, and only sample E recorded the lowest effective dose of 0.329mSv/y below the screening limit of 1.0mSv/y, indicating potential cancer risk for all samples except sample E. In summary, the study concludes that alpha activities in all collected samples are below the recommended screening levels for drinking water radioactivity set by organizations such as EPA, WHO, and GEG-FAO. However, beta activities in the samples, except for the one from Federal Polytechnic Reservoir, surpass the recommended screening levels, suggesting a potential health risk for individuals consuming water from those sources. Overall, the research provides valuable insights into alpha and beta radiation levels in water samples from various locations in Mubi-North Metropolis, highlighting the safety of alpha levels but indicating potential hazards in beta radiation levels.

Assessment of Extent of Radiological Exposures in Subsurface Dumpsite Sediments around the Residential Area of Oru-Ijebu South-West Nigeria

Assessment of naturally occurring radionuclides was carried out from 20 sampling points in a dumpsite systematically collected from varying subsurface depth intervals of 0-0.2m, 0.2-0.4m, 0.4-0.6m, 0.6-0.8m and 0.8m-1.0m, while the control samples were taken from two sampling points located 200m away from the dumpsite. The samples were consequently analyzed in the laboratory for natural radioactive emission where each activity concentration measurements of the radionuclides were determined; the natural radionuclides identified were 226Ra, 238U, 232Th, 40K utilizing gamma ray spectrometry with NaI (IT) detector. The mean activity concentrations recorded in Bqkg-1 for 226Ra, 238U, 232Th and 40K in the subsurface soil samples were respectively 2.53±0.60, 31.50±2.01, 27.20±1.63 and 340.39±19.48 in depth 0m−0.2m; 1.96±0.37, 28.2455±2.50, 23.84±3.07 and 320.59±24.07 respectively in depth 0.2m-0.4m; 1.24±0.41, 24.197±3.66, 19.86±2.46 and 290.71±28.99 respectively in depth 0.4m−0.6m; 0.80±0.34 Bqkg-1, 20.10±4.133, 16.10±1.54, and 259.04±34.22 in depth 0.6m−0.8m and 0.68±0.25, 18.509±2.08, 14.50±0.91 and 247±30.13 for 0.8-1.0m. The levels of radioactivity were then used to assess public dose rates and radioactive contamination thereby predicting changes in environmental radioactivity caused by poor waste management, industrial activities, and other human activities. In all the investigated sampling point 40K exhibited the highest activity concentration in 0-0.2m depth with the value of 383.45±19.4883 while Pr exhibited the lowest activity concentration with the value of 0.08±0.4252 in depth 0.8-1.0m. The mean activity concentration of 238U, 232Th and 40K, in the soil samples at the dumpsite were 20.80, 20.3 and 291.54 Bqkg-1respectively for 0-0.2m depth. These results were lower than the world permissible standard stated by UNSCEAR. It was generally observed that the activity concentrations reduced with 0-0.2m having the highest concentration values for both the dumpsite and the control sites, while the mean activity concentrations of 238U, 232Th and40K for the control sites were found to be 31.5045±2.0123, 13.145±1.4637 and 183.415±21.4465 respectively for 0-0.2m depth.

Assessment of Radiation Dose Associated with Background Radionuclides in Quarry Soil at Dawakin-Kudu LGA Kano, Nigeria

Naturally occurring radioactive materials (NORMs) are present in different concentrations in the environment as well as quarry depending on the geological formation of the soil. The assessment of any release of radioactivity into the environment is crucial for safeguarding public health, particularly when this radioactivity has the potential to enter the food chain. The quarry located in Dawakin-Kudu Kano has the potential to exhibit elevated levels of natural radioactivity due to intense mining operations. This study presents the assessment of activity concentration in quarry soil at Dawakin-Kudu with a focus on the transfer mechanism from soil to plant. Soil samples were gathered from a quarry site and farmlands situated around the quarry at Dawakin-kudu, plant samples were also collected from the same farmlands and were all analyzed for natural radioactivity, specifically for 226Ra,232Th, and 40K. The gamma-ray spectrometry method, coupled with the Sodium thallium Iodide NaI (Tl) detector was used to measure the activity concentrations of 226Ra,232Th, and 40K. Activity concentrations of natural radioactivity in soil were generally higher than those recorded in plants. The mean activity concentration of the radionuclides in soil ranges from Highest-to-Lowest values as follows 226Ra: 65.24±1.92 Bqkg-1 – 42.41±1.73 Bqkg-1, 232Th: 182.71±1.44 Bqkg-1 – 114.61±1.25 Bqkg-1, 40K: 597.51±3.81 Bqkg-1 – 321.93±3.55 Bqkg-1. The radiological hazard indices were all determined to assess the radiation hazard of the quarry soil. The radionuclides transfer factor showed a higher value for 40K in the order 40K>232Th >226Ra, this implies high bioconcentration of 40K in plants. The findings suggest that consuming plants grown around the quarry location over an extended period could pose substantial health threats to the public. Consequently, the study area may not be safe for residents in the long run, emphasizing the necessity for continuous monitoring of radioactivity concentrations to mitigate the environmental health implications of accumulated...

Assessment of the Natural Radioactivity Levels in Soils and the Associated Health Risks to the Public in Mbeya City, Tanzania

The objective of this study was to assess the radioactivity levels in soils from Mbeya City and their associated health risks. Samples were collected from selected locations. Then, the samples were analyzed by using an HPGe detector to determine the concentrations of 232Th, 226Ra, and 40K. The concentrations were used to compute the radiation indices. The concentrations ranged from 13.98±1.99 to 275.93±25.88 Bq/kg for 232Th, 5.69±1.48 to 107.49±10.61 Bq/kg for 226Ra and 195.76±21.17 to 1,710.00±161.32 Bq/kg for 40K with an average of 169.55 Bq/kg, 71.86 Bq/kg and 998.42 Bq/kg, respectively. The radium equivalent ranged from 41.10 to 583.93 Bq/kg with an average of 391.19 Bq/kg. The gamma dose rate ranged from 42.97 to 691.85 nGyhr-1 with an average of 467.57 nGyhr-1. The indoor effective dose ranged from 0.21 to 3.39 mSv/y, with an average of 2.29 mSv/y while the outdoor effective dose ranged from 0.05 to 0.85 mSv/y, with an average of 0.57 mSv/y. The internal hazard index ranged from 0.13 to 1.84 Bq/kg with an average of 1.25 Bq/kg while the external hazard index ranged from 0.11 to 1.58 Bq/kg with an average of 1.06.Bq/kg. The results indicate elevated levels of background radiation above the world average and the hazard indices above the ICRP and UNSCEAR recommendations. Therefore, control measures were recommended to protect the public against possible health risks.

Seasonal Variations of Radioactivity Concentrations in Soil and Sediment of Meriç River, Turkey

In this study, natural and artificial radioactivity levels were determined for spring, summer, autumn and winter in soil and sediment samples collected from different sites in the Meriç River using a HPGe detector. The mean radioactivity levels in this study were compared with other activity concentrations in various region’s soils and sediments and also with the world mean values. The mean activity concentrations of 40K were found to be higher than the world mean value in both soil and sediment samples. In addition, 137Cs radionuclide emitted into the atmosphere by the Chernobyl explosion is still present in both soil and sediment. In order to estimate the potential health risk in samples, radiological hazard parameters were calculated for samples and compared with the recommended values.

Radon revealed: The hidden connection between construction and contamination in Jazan region

Indoor radon levels, when high, can silently set the stage for lung cancer. Many are actively searching for the reason behind these spikes in radon in our living spaces. The investigation includes buildings in the picturesque Jazan region, where we use the advanced CR-39 solid-state detector. We explored houses built using two interesting methods: traditional soil compaction, innovative pore filling, and simple columns only. Surprisingly, houses built using soil pressure have always remained safe. However, as summer arrived in the Jazan region, 16% of homes with columns revealed radon levels above international safety lines. Even more surprising is that the summer radiation doses in 32% of these homes exceeded international standards. In contrast, pore-filling homes showed unwavering integrity throughout the year. The results showed that the average concentration of radon gas in the first type decreased from 358.97 Bq/cm3 in summer to 209.36 Bq/cm3 in winter. As for the second type, the concentration of radon gas decreased from 153.67 Bq/cm3 in the summer to 88.67 Bq/cm3 in the winter. This study highlights the profound impact of building and home ventilation strategies on radon levels. By combining soil compaction and the tuff layer, we ensure that Jazan homes have a healthy, radon-free environment. Furthermore, constant, up-to-date ventilation is key to staying healthy and radon-free during the hot summer months. It is advised that research into various building types worldwide be continued to determine the most secure method of construction that can lessen gas leakage from the ground and preserve public health. Future research should also look into how different building designs and ventilation systems affect radioactive contamination levels.

Impurity sensitivity analysis for activated structure materials of OPR-1000

Various kinds of radioactive wastes are expected to be generated resulting from the decommissioning of nuclear power plants. For the safe management of decommissioning wastes, the preliminary classification of radioactive wastes such as very low level, low level, intermediate level, and regulatory clearance has to be performed. In this regard, we intend to conduct an activation analysis and radioactive waste level estimation using a computational simulation code for the structure materials of an OPR-1000, a standard nuclear power plant in South Korea. In addition, the structure material that constitutes the reactor vessel, reactor vessel internals, and bio-shield concrete of the nuclear power plant contains small amounts of unintended impurities. The results of the activation analysis may vary depending on the presence of those impurities. In this study, a detail modeling of nuclear reactor and the activation analysis are carried out combined the MCNP code with the ORIGEN-S code. Based on this methodology, the sensitivity test is done for impurities of structure materials. From the result of the specific activity of activated structure material, the cobalt impurity is found to be the most important contributor in the level determination of radioactive wastes. However, the bio-shield concrete has the highest specific activity when Li impurity is contained. From this study, some impurities affect radioactive waste level, thus it is recommended to consider structure material impurities for decommissioning the nuclear power plants.

Radioactivity of inert construction and demolition waste from Hong Kong and environmental assessment for marine trial reclamation in Guanghai Bay

Inert construction and demolition waste from Hong Kong (HK public fills) has been used for marine trial reclamation in the Guanghai Bay (GHWT) of the Chinese Mainland. However, an environmental assessment of HK public fills is necessary due to higher radioactivity in HK soils than typical global levels. Here, radiation dose rate, gamma radionuclides and gross beta of HK public fills were analyzed. The origin information was explored using natural primordial radionuclides as fingerprints. Our data show that radiation dose rate of HK public fills before disposal was 0.14–0.54 (0.33 ± 0.03) μSv/h (n = 16,722 data with 2787 ships) in 2014, which is less than the GHWT background. Monthly detection of 238U, 226Ra, 210Pb, 232Th, 228Th, 40K, and gross beta in HK public fills was conducted on three random ships. Their specific activities were <6.27–155.5, 58.7–98.7, <7.83–238.2,97.9–168.6, 87.1–136.0, 463.1–1,018, and 1047–1658 Bq/kgDW, respectively. These results suggest that the radioactivity levels of HK public fills are essentially the same as the GHWT background. The study assessed potential risks using various indices icluding Raeq (Radium equivalent activity), Hex (External radiation hazard index), Hin (Internal radiation hazard index), Iγ (Gamma index), AUI (Activity utilization index), AUI (Activity utilization index), E (Annual effective dose), AGDE (Annual gonadal dose equivalent), RLI (Representative level index), Din (Indoor air absorbed dose rate), Dout (Outdoor air absorbed dose rate), and ELCR (Excess lifetime cancer risk). The study suggests that HK public fills should be used for the trial reclamation rather than building-house materials. This provides valuable insights for the resource utilization and minimizing environmental pollution of HK public fills. The aim is to offer fundamental technical assistance for future waste resource utilization, ecological protection, and restoration in the Guangdong-Hong Kong-Macao Greater Bay Area.

Evaluation of Environmental Radioactivity and Estimation of Radiation Exposure in the Niankhene Agricultural Field in Senegal

The presence of radioactivity, originating from both natural and human-induced sources, is widespread in varying degrees throughout the Earth&amp;apos;s crust. Soil, as a fundamental component of the Earth&amp;apos;s crust, serves as an ongoing source of exposure to humans. The level of radioactivity in soil is influenced by factors such as soil composition and land usage. It is expected that barren soil exhibits distinct radioactivity levels compared to cultivated soil. To investigate the radioactivity levels within barren soil, a study was conducted on approximately 11 hectares of soil samples located in Niankhene. Utilizing gamma ray spectrometry methodology with a high purity germanium gamma-ray detector, activity concentration levels of radionuclides including &amp;lt;sup&amp;gt;40&amp;lt;/sup&amp;gt;K, &amp;lt;sup&amp;gt;137&amp;lt;/sup&amp;gt;Cs, &amp;lt;sup&amp;gt;226&amp;lt;/sup&amp;gt;Ra, and &amp;lt;sup&amp;gt;232&amp;lt;/sup&amp;gt;Th were evaluated. A total of 16 soil samples were collected at depths ranging from 0 to 40 cm with 20 cm intervals. The activity concentrations of the radionuclides were observed as follows: &amp;lt;sup&amp;gt;40&amp;lt;/sup&amp;gt;K ranged from below the limit of detection to 34.7 Bq.kg&amp;lt;sup&amp;gt;-1&amp;lt;/sup&amp;gt;; &amp;lt;sup&amp;gt;137&amp;lt;/sup&amp;gt;Cs varied from 0.06 to 0.80 Bq.kg&amp;lt;sup&amp;gt;-1&amp;lt;/sup&amp;gt;; &amp;lt;sup&amp;gt;226&amp;lt;/sup&amp;gt;Ra measured was between 7.49 and 101.56 kg&amp;lt;sup&amp;gt;-1&amp;lt;/sup&amp;gt;; and &amp;lt;sup&amp;gt;232&amp;lt;/sup&amp;gt;Th ranged 0.33 and 12.68 Bq.kg&amp;lt;sup&amp;gt;-1&amp;lt;/sup&amp;gt;. The total dose radiation exposure were 27 nGy/h in this study. Before conducting radiometric measurements, chemical analyses were performed to determine the concentrations of Na, Ca, and Mg, along with measurements of electrical conductivity and pH levels of the soil samples.

A review of naturally occurring radioactive elements in coastal regions of Bangladesh

Extensive and systematic study has been carried out globally to get a thorough understanding of the underlying dynamics of radionuclides in the environment. This study was aimed to examine the natural radioactivity level in coastal areas of Bangladesh by combining the main research carried out on environmental radioactivity, predominantly employing established nuclear methods and methodologies during the past. The concentrations of important radionuclides, including 226Ra, 232Th, 40K, 238U, and 235U, were measured in those investigations. Soil samples showed the highest concentration of 226Ra at Inani Beach, Cox's Bazar (21°8ʹ N latitude, 92°4ʹ E longitude), with a value of 61.66 Bqkg-1. On the other hand, Cox's Bazar Sea Beach has the lowest 226Ra concentration at 10.8 Bqkg-1. In contrast, Cox's Bazar had the highest 226Ra activity in the sand and silt samples (147.93 Bqkg-1), whereas Kuakata Sea Beach (21° 48ʹ N latitude and 90° 10ʹ E longitude) had the lowest (2.82 Bqkg-1). The research found that 226Th activity varied from 1085.99 Bqkg-1 to 27.4 Bqkg-1 in soil samples from Cox's Bazar Sea Beach. In Cox's Bazar, the sand and silt samples showed the highest 226Th activity at 1085.9 Bqkg-1. In contrast, Kuakata Sea Beach has the lowest radioactivity at 9.22 Bqkg-1. Soil samples showed that 40K content was highest at Inani Beach (21°13ʹ N latitude and 92°3ʹ E longitude), Cox's Bazar (1304.11 Bqkg-1) and lowest at Cox's Bazar Sea Beach (25.16 Bqkg-1). The sand and silt sample from Kuakata Sea Beach had the greatest 40K activity, measuring 852 Bqkg-1. However, the sample from Cox's Bazar Sea Beach had the lowest amount (21.9 Bqkg-1). Soil samples from Cox's Bazar Sea Beach showed 238U activity of 455.99 Bqkg-1 and 110.84 Bqkg-1, respectively. The highest 238U activity sand sample was found in Cox's Bazar, measuring 460.5 Bqkg-1. The Patenga region (22°14ʹ N latitude and 91°47ʹ E longitude) in Chattogram has the lowest radioactive level, 45.2 Bqkg-1. The study's findings have been meticulously recorded as crucial foundational knowledge for forthcoming investigations on radionuclides in this coastal area. A comprehensive evaluation of prior published analyses of naturally occurring radioactive elements in the coastal regions of Bangladesh has shown that the level of activity is completely non-hazardous. The experimental areas' soils are ideal for a variety of agricultural and other purposes. Bangladesh J. Nuclear Agric, 37(2): 135-152, 2023

Levels of naturally occurring radioisotopes in local and imported bottled drinking water available in Québec City, Canada

Consumption of local and imported bottled water in Canada has greatly increased during the past three decades. While the presence of natural radioactivity is often overlooked when dealing with the water quality of these bottled products, it could contribute substantially to the uptake of radionuclides especially when sourced from regions with higher radioactivity levels compared to where it is consumed. In this study, the activity of several naturally occurring radionuclides (i.e., 210Po, 226,228Ra, 230,232Th, 234,235,238U) were measured in bottled water available in Québec, Canada after sample pretreatment and analysis by either radiometric or mass spectrometry approaches. 230,232Th and 228Ra concentrations were below minimum detectable activity levels in all samples tested. Analytical results for 234U, 235U, 238U, and 226Ra showed concentrations that ranged from 0.38 to 115 mBq/L, (2.2–313) x 10−2 mBq/L, 0.48–58.4 mBq/L, and 1.1–550 mBq/L, respectively. 210Po was detected in only 5 samples and its activity ranged from 2 to 26 mBq/L. To determine variability in activity within brands, the same brands of bottled water were purchased during two consecutive years and analyzed. The possible radiological impact of the consumption of these types of water was assessed based on different drinking habit scenarios. Some of the imported water brands showed higher activity concentrations than local sources or tap water, suggesting that individuals drinking predominantly imported bottled water would receive a higher radiation dose than those who drink mainly local water.

Influence of the industrial pollutant on water quality, radioactivity levels, and biological communities in Ismailia Canal, Nile River, Egypt

In the twenty-first century, numerous forms of pollution have adversely impacted freshwater and the entire aquatic ecosystem. The higher population density in urban areas also contributes to increased releases of substances and thermal contaminants, significantly stressing the ecosystem of industrial companies. This study aimed to assess the potential pressure of industrial and municipal activities on water quality, radioactivity levels, and biological diversity, focusing on the consequences of radionuclides on periphytic diatom communities. Furthermore, the environmental impact of pollutants will be evaluated to monitor the ecological condition of the Ismailia Canal. Chemical analyses employed various instruments and methods to identify and quantify matter, with radionuclide elements measured by gamma spectrometry and diatoms counted and identified by inverted microscopy. Our results revealed that the canal was classified as excellent for irrigation, aquatic life, and drinking water based on FAO, CCME, and EWQS water quality indices, with high nutrient levels at Abu Za’baal fertilizer company. The activity concentration of 226Ra-series, 232Th-series, and 40K in the water and sediment samples for two seasons was within the guideline values, except for a few stations in the zone [B] (the industrial zone). Fertilizer samples (raw material) showed a high value of the 226Ra-series activity. Diatom community structure significantly varied across the different canal locations regarding the presence or absence of industrial activities, with no discernible variations between the study seasons. A specific variety of algal species was found to be predominant at the highest radioactive sites. Redundancy analysis (RDA) showed a significant correlation between parameters (pH, Na, TDS, PO4, SO4, SiO2, K, and CO3), radionuclides, environmental conditions, and the composition of the diatom community, especially in the area affected by industrial discharges. Moreover, the radiological hazard index in water and sediment remained below the maximum for two seasons. This research provides valuable data and information for communities and decision-makers, suggesting the strategic use of phycoremediation as a water biotreatment process to protect the valuable economic resources of the Ismailia Canal.

Health risk assessment for soil radioactivity around Shidaowan nuclear power plant in Shandong, China.

Monitoring radioactivity levels in the environment around nuclear power plants is of great significance to assessing environmental safety and impact. Shidaowan nuclear power plant is currently undergoing commissioning; however, the baseline soil radioactivity is unknown. The naturally occurring radionuclides 238U, 232Th, 226Ra and 40K, and artificial radionuclide (AR) 137Cs in soil samples around the Shidaowan nuclear power plant were measured to establish the baseline levels. Human health hazard indices such as external hazard indices (Hex), Radium equivalent (Raeq), outdoor absorbed dose rate (Dout), annual effective dose (AED) and excess lifetime cancer risk (ELCR) were estimated. The average concentration of 232Th, 40K, 137Cs, 238U and 226Ra were 42.6±15, 581±131, 0.68±0.38, 40.13±9.07 and 40.8±12.8Bq per kg, respectively. The average Hex, Raeq, Dout, AED and ELCR were 0.40, 146Bq per kg, 68.8 nGy per h, 0.09mSv per y and 3.29E-04, respectively. These data showed an acceptable level of risk to residents near the nuclear power plant and that the current radioactivity in the soil may not pose immediate harm to residents living close to the nuclear power plant. The observed lower AED and 40K and 137Cs concentrations were comparable to other studies, whilst ELCR was higher than the world average of 2.9E-04. The commissioning of the Shidaowan nuclear power plant is potentially safe for the surrounding residents; further continuous monitoring is recommended.

Radionuclides distribution and radiation hazards assessment of black sand separation plant’s minerals: a case study

This study assessed the radioactivity levels and associated risks in the black sand-separated products obtained from the black sand separation plant in Delta, Egypt. A total of sixteen samples were taken from hot spots during and after the separation process. These include water samples and other samples that represent monazite, rutile, zircon, granite, ilmenite, and silica products. The hot spots included the area where the ore was stored. The activity concentrations of 232Th\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{232}Th$$\\end{document}, 226Ra\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{226}Ra$$\\end{document}, and 40K\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{40}K$$\\end{document} were determined in these samples using a p-type HPGe detector. Based on gamma spectrometric analysis, samples of rutile, zircon, and monazite had the highest amounts of radioactivity because they contained the highest NORM’s activity concentrations. In addition, it indicated that the radiological hazard indices of the collected samples were higher than the average world limits for sand texture. These findings suggest that the black sand separation process reveals potential risks to human health and the environment, and therefore, appropriate measures need to be taken to mitigate these risks, especially for the safety of the workers on-site. Reducing the risk associated with those sites should be controlled by implementing the recommendations declared for the series of International Basic Safety Standards of the International Atomic Energy Agency (GSR) Part 3, as affirmed in Document No. 103 of 2007 by the International Commission on Radiological Protection (ICRP) as will be presented in the paper body.

Radiological safety assessment for transportation of reactor pressure vessel during decommissioning of a nuclear power plant in Korea

In Korea, decommissioning of nuclear power plants and transportation of the decommissioning waste are expected to expand in the near future. It is necessary to confirm that radiological risks to the public and workers are not significant through radiological safety assessment. The objective of this study is to assess the radiological safety for transportation of RPV waste, which is a major decommissioning waste with relatively high level of radioactivity. It was assumed that the waste would be transported to the Gyeongju disposal facility by land transportation. First, the source term and transportation method of the RPV waste were determined, and the external dose rates from the waste were calculated using MCNP. Then, transportation scenarios were assumed under both normal and accident conditions. Under the scenarios, radiation doses were calculated using the RADTRAN. Under normal operation scenarios without a transportation accident, assuming 40 shipments per year, the average individual doses for the public ranged from 6.56 × 10−6 to 2.18 × 10−2 mSv yr−1. The maximum individual doses for only a single shipment ranged from 2.43 × 10−6 to 3.14 × 10−1 mSv. For cargo handlers and vehicle crew members, the average doses were 2.26 × 101 mSv yr−1 and 2.95 mSv yr−1, respectively. Under transportation accident scenarios, average individual radiological risks which are product of the radiation doses and the annual accident rates ranged from 1.14 × 10−11 to 1.61 × 10−10 mSv yr−1 by transportation route segment when considering the transportation accident rate. Average individual doses assuming transportation accident occurrence ranged from 2.62 × 10−4 to 1.42 × 10−3 mSv. The maximum individual dose under accident conditions was 7.99 × 10−2 mSv. The calculated doses were below the regulatory limits in Korea. However, relatively high doses were observed for cargo handlers and vehicle crew members because of conservative assumptions. This study results can be used as basic data for the radiological safety assessment for the decommissioning waste transportation in the future.

Accumulation of Heavy Metals and Determination of Natural Radioactivity in the Soil-Thyme System in Omerli, Istanbul: Assessment of Ecological and Health Risk

A significant pathway for human exposure to environmental pollutants is the metal transfer from soil to plants. In this study accumulation of different metals was investigated and natural radioactivity levels were measured in the soil–thyme system. It was found that the soil had higher concentrations of Br, Cr, Mn, Ni, and Pb than the world average and P, Ca, and Zn had higher transfer factors. The natural radioactivity level in the soils is similar to the World average. For thyme samples the average values for 226Ra, 232Th and 40K were found as 22.7 ± 10.9 Bqkg-1, 61.3 ± 19.9 Bqkg-1 and 722 ± 391 Bqkg-1, respectively. The health and ecological risks of soil were evaluated. The total hazard index of the child was 1.453 on average, greater than that of the adult (0.175), primarily due to the contribution of Cr. Ecological risk assessed based on various indices indicated that Pb and Ni show environmental contamination risk. Our findings confirm that metal concentrations in plants are influenced by metal concentrations in soil, and that metal interactions are important for pollution risk management.

210Po and 210Pb radioactivity levels in local and imported tobacco used in Palestine and Jordan.

This study aimed to assess the concentrations of 210Po and 210Pb in various tobacco samples from Palestine and Jordan. Cigarette smoking is recognized as a significant contributor to the radiation dose received by individuals, primarily due to the elevated levels of 210Pb and 210Po found in tobacco. The analysis revealed that the average concentrations of 210Po in locally sourced tobacco and cigarette samples in Palestine are 16.8 ± 2.3mBq/g and 18.5 ± 2.0mBq/g, with a total average of 17.8 ± 7.4mBq/g (15.5mBq/cigarette). Similarly, the average concentrations of 210Pb in these samples are 18.5 ± 2.6mBq/g and 20.3 ± 2.2mBq/g, with a total average of 19.6 ± 8.1mBq/g (17.0mBq/cigarette). In Jordan, the average concentrations of 210Po in cigarette samples and narghile tobacco are 20.1 ± 2.4mBq/g and 18.3 ± 4.1mBq/g, with a total average value of 19.6 ± 9.9mBq/g (18.0mBq/cigarette), while the average concentrations of 210Pb are 22.2 ± 2.6mBq/g and 20.2 ± 4.5mBq/g, with a total average value of 21.6 ± 10.8mBq/g (19.9mBq/cigarette). The annual effective doses resulting from inhalation were calculated for smokers of these samples. The findings revealed that the levels of 210Po and 210Pb radioactivity in certain investigated samples exceeded the results of studies in many countries of the world. The associated effective doses per year from smoking for all brands products in Palestine range from 34.7μSv/y to 186.5μSv/y with an average of 109.5μSv/y, while in Jordan 54.5μSv/y to 289.1μSv/y with an average of 130.9μSv/y.

Assessment of radioactivity level and associated radiological hazard in riverbed samples within industrial areas

ABSTRACT Terrestrial gamma radiation is one of the major outdoor radiation exposures to the general public that varies substantially based on the type and geological properties of the soil. The objective of this study is to evaluate the naturally occurring radioactive materials (NORMs) distribution and assess the hazard parameters in the riverbank soil within various industrial zones in the densely populated Dhaka and Chattogram cities of Bangladesh. The mean activities of 226Ra (37 ± 3), 232Th (58 ± 4), and 40K (1129 ± 18) Bqkg−1 in the assessed soil samples were found to be slightly higher than the world average values 32, 35, and 420 Bqkg−1, respectively. The mean radium equivalent activity (207.49 Bqkg−1) and the external and internal hazard indices were within the recommended limits of 370 Bqkg−1 and <1, respectively. The mean absorbed dose rate (99.47 nGyhr−1), annual effective dose (0.12 mSva−1), ELCR (4.27 × 10−4), and gamma level index (1.58) exceeded the world average values 59 nGyhr−1, 0.07 mSva−1, 2.9 × 10−4, and 1 respectively. However, the studied areas are safe from a radiological viewpoint with no radiation health hazard to the people. The results of this study can be utilized to produce factual baseline data for future studies.

Environmental and mineralogical studies on the stream sediments of Baltim–El Burullus coastal plain, North Delta, Egypt

This work is mainly concerned with the effect of anthropogenic activities and natural radioactivity due to the presence of highly radioactive black sand spots, factory construction, and shipping, in addition to other activities like agriculture on human beings. Forty samples were collected along Baltim–El Burullus coastal plain to detect the effect of these problems and determine the suggested solutions. The black sand of the Baltim–El Burullus coastal plain exhibits a considerable amount of economically heavy minerals, their ratio relative to the bulk composition in the investigated samples ranges from 3.18 to 10.5% with an average of 5.45%. The most important of them are magnetite, ilmenite, rutile, leucoxene, garnet, zircon and monazite. The existence of some radioactive-bearing accessory mineral deposits like zircon and monazite led to measuring the naturally occurring radionuclides 226Ra, 232Th and 40K to evaluate the excess lifetime cancer risk (ELCR). The results showed that these concentrations are 19.1 ± 9.73, 14.7 ± 9.53 and 211 ± 71.34 Bq kg−1 were lower than the corresponding reported worldwide average of 35, 45, and 412 Bq kg−1 for each radionuclide (226Ra, 232Th, and 40 K). The gamma hazard indices such as absorbed dose rate (Dair), the annual effective dose (AED), and excess lifetime cancer risk (ELCR) factor were computed in the investigated sediments and all the results were found (Dair = 26.4 nGy h−1, AED = 0.03 mSv year−1, ELCR = 0.0001) to be lower than the values suggested by the United Nations Scientific Committee on the effect of Atomic Research (59 nGy h−1, 0.07 mSv year−1 and 0.0029 for Dair, AED and ELCR, respectively). The study suggests that the black sand is safe to use in various infrastructure applications at Baltim–El Burullus coastal plain. The levels of radioactivity are not high enough to pose a risk to human health.

Analysis of 238U, 232Th, 222Rn and 220Rn contents in medical drugs, petroleum products and petrol/gas-oil exhaust fumes by using CR-39 and LR-115 type II nuclear track detectors – Experimental and new Monte Carlo simulation approaches

Petroleum products and medical drugs have been studied in order to determine 238U, 232Th, 222Rn, 220Rn and their progenies contents in them using mean absolute detection efficiency based Solid State Nuclear Track Detectors (SSNTDs) experimental method. In the present paper, a Monte Carlo code based theoretical approach has been also developed to determine mean absolute detection efficiencies of SSNTDs; this theoretical approach has been combined with experimental one for deriving levels of natural radioactivity inside different materials studied. The dependence of CR-39 and LR-115 type II mean absolute detection efficiencies on initial alpha particle energy, removed thickness of SSNTDs and SSNTDs areas for different natural materials studied has been highlighted as well. The mean absolute detection efficiency depends clearly on the initial alpha particle energy and the removed layer while it does depend neither on the detector surface nor on the nature of the material being studied. The results obtained using the present method and those obtained by mean critical angle based SSNTD technique and isotope dilution mass spectroscopy (IDMS) are in good agreement with each other: our method has less relative uncertainties, which do not exceed 4%, than the other methods, whose the relative uncertainties exceed 9% and 7%, respectively.