Radiological Health Risk Research Articles

Estimation of radiological health risks due to 226Ra, 232Th, and 40K in foods consumed in Iraqi Kurdistan Region

ABSTRACT This study investigates the activity concentration of natural radionuclides in a diverse range of food samples in the Koya district markets food baskets, including both domestic and imported products. The samples cover annual crops (e.g. coffee, tea, kidney beans), tree nuts (e.g. almonds, pistachios), and other items (e.g. beef, fish, milk) by using a high-purity germanium (HPGe) detector. This research addresses a notable gap by providing baseline data on radionuclide concentrations and assessing potential health risks. Average activity concentrations for ²²⁶Ra, ²³²Th, and ⁴⁰K were 0.943, 0.367, and 191.8 Bq kg−1, respectively. Radium equivalent activity values ranged from 2.88–58.48 Bq kg−1, all below the safety limit. The average excess lifetime cancer risk (ELCR) was 0.154 mSv a−1, indicating safety for most samples, though coffee and tea showed higher levels. This study provides new data crucial for future research and regulatory monitoring, underscoring the need for further investigation into geological impacts on radionuclide levels.

Determination of potentially toxic metals and natural radionuclides in airborne pollens produced different urban environments in Turkey and health risk assessment

ABSTRACT Air pollutants are associated with potentially toxic metals (PTMs) and natural and/or artificial radionuclides, which can pose a major threat to human and environmental health. Pollens can be utilized as a bioindicator to determine the level of air pollution in urban areas. In this study, the concentrations of PTMs and natural radionuclides in 35 airborne pollen samples of 22 species belonging to Pinaceae, Cupressaceae, Araucariaceae, Betulaceae, Salicaceae, and Oleaceae families grown in different urban areas in Turkey were determined using an energy-dispersive X-ray fluorescence spectrometry. For the first time, non-carcinogenic and radiologic health risk assessments for adults were done, estimating hazard index (HI) and annual effective dose (AED), respectively. The concentrations of Fe, Mn, Zn, Ti, Sr, Cu, Ni, Co, Cr, V and Pb analyzed in airborne pollen samples varied from 52.1 to 3078.0, 26.1 to 159.6, 15.6 to 199.7, 9.1 to 282.2, 1.0 to 128.4, 5.0 to 40.1, 5.4 to 23.6, <LD to 11.3, 1.6 to 26.6, <LD to 11.1 and <LD to 5.7 mg/kg, respectively. The average concentrations of K (2%), Th (1.3 mg/kg) and U (1.0 mg/kg) were converted into the activity concentrations (in Bq/kg) of 40K (595.8), 232Th (5.2) and 238U (11.8), respectively. All HI and AED values revealed a very low non-carcinogenic and radiological health risk due to exposure to all PTMs and radionuclides in the pollen samples studied.

Assessment of the Radioactivity, Metals Content and Mineralogy of Granodiorite from Calabria, Southern Italy: A Case Study.

In this paper, an assessment of the natural radioactivity level, radon exhalation, metal contamination, and mineralogy of a granodiorite rock sample from Stilo, in the Calabria region, Southern Italy is presented as a case study. This rock was employed as a building material in the area under study. The specific activity of 226Ra, 232Th and 40K natural radioisotopes was assessed through high-purity germanium (HPGe) gamma-ray spectrometry. Then, several indices such as the absorbed gamma dose rate (D), the annual effective dose equivalent (AEDE), the activity concentration index (ACI) and the alpha index (Iα), were quantified to determine any potential radiological health risk related to radiation exposure from the analyzed rock. Furthermore, E-PERM electret ion chambers and inductively coupled plasma mass spectrometry (ICP-MS) measurements were carried out to properly quantify the radon exhalation rate and any possible metal pollution, respectively. In particular, to further address metal pollution factors, the geo-accumulation index (Igeo) was calculated to properly address the toxicity levels of the ecosystem originating from the detected metals. Finally, with the aim of successfully discriminating the provenance of such naturally occurring radionuclides, a combined approach involving X-ray diffraction (XRD) and µ-Raman spectroscopy was employed for the identification of the main radioisotope-bearing minerals characterizing the investigated granodiorite. The results achieved in this case study can be taken as the basis for further inquiries into background levels of radioactivity and chemical contamination in natural stone employed as building materials.

Radiological hazard assessment of soil from Kasik oil refinery, Nineveh, Iraq

This study explored soil samples in a depth about 10–15 cm, 20 Soil samples were collected systematically from various locations to ensure a comprehensive assessment of the site within Kasik oil refinery, Nineveh Governorate, Iraq, whereby the determination of three natural radionuclides' specific activities was carried out via A p-type coaxial HPGe γ-ray spectrometer, manufactured by CANBERRA, USA. Natural radioactivity in soil is a significant factor for assessing environmental radiation exposure and potential health risks. The 226Ra, 232Th, and 40K radionuclides' mean specific activities in the soil samples were in the 13.10–33.43 Bq/kg, 10.58–22.76 Bq/kg, and 104.90–442.16 Bq/kg ranges, respectively, with overall means of 21.44 Bq/kg, 15.96 Bq/kg, and 255.50 Bq/kg, which are within the worldwide mean levels. The mean radium-equivalent activity (Raeq) was 63.94 Bq/kg, and thus below the 370 Bq/kg international limit. All of the samples' representative level index (Iɣ) and internal and external hazard indices (Hin and Hex) were below the limit of unity, indicating low radiation hazards. The absorbed dose rate resulting from the three primordial radionuclides was in the 19.92–41.46 nGy/h range (mean: 30.20 nGy/h), with an annual effective dose of 0.04 mSv/y. The mean excess lifetime risk of cancer was found to be 0.15 × 10⁻³, and thus under the 0.29 × 10⁻³ world average. The study's results indicate that the natural radionuclides' measured specific activities in the soil samples are below the world recommended values, suggesting that the investigated area is safe in terms of radiological health risks.

Radioactivity of Technosols on thermal power station ash disposal sites: Assessment of potential radiological human‐health risk

AbstractSoil radioactivity is a poorly recognized form of land degradation; however, there are regions all around the world where it can be dangerous to the environment and human health. The aim of the study was to analyze the radioactivity of Technosols developed on thermal power station (TPS) ash disposal sites. Total concentration of uranium (U), thorium (Th), and cesium (Cs), as well as the radioactivity of select radionuclides in Technosols were determined to recognize the level of radioactivity and to assess the potential radiological health risk. Total U, Th and Cs concentrations in Technosols were in ranges 1.5 to 11.3, 4 to 22.9, and 0.2 to 21.3 mg·kg−1, respectively. The radioisotope activities in Technosols (in Bq·kg−1) were in the 1.6–25.5 (137Cs); 29.2–1265 (40K); 26.2–99.9 (228Th); 27.9–100 (228Ra); 20.5–134. (226Ra); 32.8–177 (210Pb); 23.9–144 (238U); 1.2–7.0 (235U) ranges. The activity concentrations were slightly higher than the activities of non‐contaminated soils. Technosols developed from bituminous coal ash had higher 40K, 228Th, and 228Ra activity concentrations than soils developed from lignite ash. Artificial 137Cs occurred in surface horizons of Technosols due to fall of atmospheric dust enriched in 137Cs. Annual effective dose (AED) in Technosols amounted 0.07–0.16 mSv·a−1 and was somewhat higher than the global and Polish average (0.06 and 0.07 mSv·a−1, respectively) for outdoor external terrestrial radiation. The radioactivity of the investigated Technosols is slightly above the average radioactivity of native soils. The radiological human‐health risk related to the analyzed soils is low.

Forensic GIS γ-Radiation Mapping and Associated Radiological Health Risk Assessment of the Premier Cities of Sapele, Oghara and Koko; South-South Nigeria

The GIS mapping of the terrestrial γ -radiation levels and evaluation of the radiological health hazard to residents of Sapele, Oghara and Koko cities in Nigeria have been carried out, using a Digilert nuclear radiation survey meter, geographical positioning system (GPS) and arc ArcGIS software. In Sapele (4 zones), the measured average gamma radiation levels ranged from 0.011 ± 0.003 mR h − 1 to 0.014 ± 0.005 mR h − 1 , while in Oghara (5 zones), the average gamma radiation levels ranged from 0.013 ± 0.002 mR h − 1 to 0.026 ± 0.009 mR h − 1 and for Koko(4 zones), the values obtained ranged from 0.018 ± 0.003 mR h − 1 (1.54 ± 0.11 mSvy − 1 ) to 0.023 ± 0.008 mR h − 1 respectively, with overall mean value of 0.017 ± 0.006 mR h − 1 (1.43 ± 0.51 mSvy − 1 ) . The mean absorbed gamma dose rate for three cities of Sapele, Oghara and Koko are 106.50 ± 22.33 nGy h − 1 , 167.28 ± 22.59 nGy h − 1 and 176.80 ± 24.74 η Gyh − 1 respectively. The mean annual effective dose rate (AEDR) for the three cities is 0.13 ± 0.03 mSvy − 1 , 0.20 ± 0.07 mSvy − 1 and 0.22 ± 0.06 mSvy − 1 mSvy − 1 respectively , while the mean excess lifetime cancer risk (ELCR) values are (0.47, 0.72 and 0.77) x10−3 respectively. The results obtained in the cities indicate that the BIR levels, and corresponding estimated health risk parameters in Koko > Oghara > Sapele. The estimated effective dosage to organs shows that liver receiving the least dose of 0.07mSvy−1 (11%) while testes got the highest dose of 0.12 mSvy−1 (19%). The overall results obtained show that all the thirteen zones’ BIR levels and their estimated risk parameters exceeded their recommended limits for the public and were also higher than reported values in previous studies reviewed. The reported significant elevation of the obtained background ionizing radiation (BIR) values may not necessarily establish any immediate likelihood of radiological health risk, but call for caution on possible accumulative radiation effects in future on the residents of the study area.

On transfer factors of natural radionuclides and radiological health risks assessment of some fruit samples

Abstract In this study, the activity concentration of artificial and natural radionuclides such as 137Cs, 40K, 226Ra, and 232Th was measured in the soil under the roots; leaves; and fruits of six different fruit trees namely mulberry, fig, apricot, olive, black and white grapes in Koya district, Erbil province, Iraq. For this purpose, a high-resolution gamma spectroscopy consisting of a high-purity germanium (HPGe) detector was used. In addition, the associated radiological risks from soil and fruits were assessed by calculating several radiological indices such as radium equivalent (Raeq.s), absorbed dose (Ds), indoor (AEDEs indoor ) and outdoor annual effective doses (AEDEs outdoor ), internal and external hazard indices, gamma index and the excess lifetime cancer risk (ELRCs). The results show that consuming these fruits is radiologically safe because they can cause an annual effective dose of about 61.72 μSv y−1 and excess lifetime cancer risk of 0.06 × 10−3 Sv y−1. On the other hand, transfer factors of radionuclides from soil to leaves; and from soil to fruits were studied. The transfer factor analysis revealed that among the studied fruits and radionuclides, apricot and mulberry exhibited the highest transfer factors for 40K, with values of 1.85 and 1.87, respectively.

Examining the Radiological Health Risks Associated with Water Sourced from the Ogwashi-Uku Earth Dam in Ogwashi-Uku, Delta State, Nigeria

Given the increased human activities and population growth in Ogwashi-Uku, there is a possibility of potential contamination of the water in the dam with elevated levels of alpha and beta radiation. Therefore, this study aimed to assess the radiological health risks associated with water obtained from the Ogwashi-Uku Earth dam by analyzing the concentrations of gross alpha and gross beta activity in the water. The results indicate that the measured activity concentrations of gross alpha and gross beta in the water samples are below the permissible limits of 0.1 Bq/l and 1.0 Bq/l respectively. Additionally, the average annual effective dose equivalent calculated for all the water samples is lower than the recommended dose limit of 0.1 mSv for radionuclides in water. These findings suggest that the assessed life cancer risk associated with the water consumption is low, indicating that the water from the Ogwashi-Uku Earth dam is safe for consumption.

Determination of radon concentrations and physicochemical parameters of non-alcoholic carbonated beverages consumed in Türkiye and assessment of radiological health risk

ABSTRACT The strategy for controlling the existence of radionuclides in drinking water depends upon an individual dose criterion (IDC) of 0.1 mSv/y, which represents a very low level of risk that is not expected to cause any identified adverse health effects. Radon gas, considered a carcinogenic radionuclide, can dissolve and accumulate in drinking water. Non-alcoholic carbonated beverages (NACBs), which mainly contain drinking water, phosphoric acid, citric acid, caffeine, and sugar, represent one of the most consumed groups worldwide and in Türkiye. In this study, the radon activity concentration and some physicochemical characteristics of 45 NACB samples from 24 most preferred commercial brands in Türkiye were determined to assess the radiological health risk associated with the ingestion of these samples. Radon activity concentrations measured in NACB samples using the AlphaGUARD radon analyzer ranged from 22.8 ± 0.7 to 54.9 ± 1.7 mBq/L. The pH, conductivity, total dissolved solids, and brix values in NACB samples ranged from 2.31 to 7.29, 401 to 3281 μSv/cm, 355 to 2453 mg/L, and 0.10 to 12.95%, respectively. Total (ingestion and inhalation) annual effective doses and the corresponding excess lifetime cancer risks estimated for adults to assess the radiological health risk are significantly below the IDC and advised safety limit (10−3), respectively.

Natural Radioactivity in Raw Building Materials for Underground Parking Lots and Assessment of Radiological Health Risk for the Population.

This article reports the results of an investigation into the activity concentration of natural radionuclides in raw building materials for underground parking lots, together with the assessment of the radiation hazard for the public related to exposure to ionizing radiations. To this purpose, high-purity germanium (HPGe) γ-ray spectrometry was employed in order to quantify the average specific activity of 226Ra, 232Th, and 40K natural radioisotopes. With the aim to assess any possible radiological health risk for the population, the absorbed γ-dose rate (D), the annual effective dose equivalent outdoor (AEDEout) and indoor (AEDEin), the activity concentration index (I), and the alpha index (Iα) were also estimated, resulting in values that were lower than the maximum recommended ones for humans. Finally, the extent of the correlations existing between the observed radioactivity and radiological parameters and of these parameters with the analyzed samples was quantified through statistical analyses, including Pearson's correlation, a principal component analysis (PCA), and a hierarchical cluster analysis (HCA). As a result, three clusters of the investigated samples were recognized based on their chemical composition and mineralogical nature. Noteworthily, this paper covers a certain gap in science since its topic does not appear in literature in this form. Thus, the authors underline the importance of this work to global knowledge in the environmental research and public health fields.

Assessment of radiological hazards from radioactivity natural of cement used in Dwellings in Rio de Janeiro, Brazil

Brazil is the fourth largest cement consumer in the world and the largest producer in Latin America, around 1.3% of global production. The main inputs in the manufacture of cement are limestone and clay. Few studies have been carried out in the country on the risk of these materials used in civil construction. Therefore, the objective of this present work is to evaluate the radiological danger that they can present to society. Gamma spectrometry analysis on 16 samples of different brands of cement used as construction material in Rio de Janeiro (Brazil) was performed in this study, using an HPGe detector and the Genie 2000 data acquisition software. Samples were set to count for an accumulation time of 14,400 s (4 h) and all measurements were corrected to eliminate background and backscattering. Activity concentrations are determined for 226Ra was from (41.2 ± 1.6 to 174.9 ± 3.9) Bq kg−1, 232Th was from (15.7 ± 0.5 to 43.1 ± 0.7) Bq kg−1 and 40K was from (82.6 ± 7.2 to 254 ± 17) Bq kg−1. To assess radiological health risks: mean values of Radium Activity Equivalent 150.0 ± 3.4 Bq kg−1, Annual Gonadal Dose Equivalent 468 ± 11 μSv year−1 and Lifetime Excess Cancer Risk (ELCR) 2.42 ± 0.06 were calculated. Total Absorbed Dose Rates ranged from 72.2 ± 1.7 to 225.1 ± 5.2 nGy h−1. The damage to collective health was also estimated from the annual effective dose rates with an estimated total cost of damage to health of US$ 130 million. Values are generally within global limits reported by UNSCEAR.

Activity concentration, transfer factor and radiological health risk assessment of natural radionuclides in soil and maize in oil producing areas in Akwa Ibom state, Nigeria

The activity concentration (AC) of 238U, 232Th, 40K of soil and maize in oil producing areas has been studied. Also studied are the transfer factor (TF) from soil to maize and the radiological health risk associated with consumption of maize. The equipment used was the Sodium Iodide-Thallium (NaI(TI)) detector. The mean activity concentration (AC) (Bqkg-1) of 238U, 232Th, 40K in soil are 12.77±0.25, 41.36±0.70 and 458.61±8.04 while that of maize are 14.36±0.27, 19.23±0.46 and 425.25±7.87 respectively. Transfer factor (TF) from soil to maize of 238U, 232Th and 40K are 1.14, 0.50 and 0.94 correspondingly. Other useful results obtained in this research include the Radium Equivalent (Raeq), Absorbed Dose Rate (ADR), Annual Effective Dose (AED) and Excess Lifetime Cancer Risk (ELCR) as 74.59 Bq/kg, 37.14 nGy/h, 0.05 mSv/y and 0.16 respectively. The average values of soil activity concentration from the oil producing areas are within world permissible limits given by UNSCEAR (2000) as 420 Bqkg-1 for 40K, 33 Bqkg-1 for 238U and 45 Bqkg-1 for 232Th. However, 238U and 232Th from maize activity concentration are far higher than world permissible limits of 0.02 Bqkg-1 and 0.003 Bqkg-1 respectively. The mean value of the radiological hazard indices was below the WMPV given as 370 Bq/kg for Raeq, 59 nGy/h for ADR, 1 mSv/y for AED and 0.29×10-3 for ELCR. This clearly shows that radiation doses exposed to Akwa Ibomites through the consumption of maize cultivated in this area poses very little to no effect to their health as only about 16 out of every 100,000 persons may likely have cancer fatality in their time.

Radiometric survey of sediments and health risk assessments from the southern coastal area of Delta State, Nigeria

Over the years, the release of potential radiological components around the oil exploration environment has increased with potential health implications.Yet; the mechanism and health associated assessment have remained fuzzy to most experimental scientists. The current study determines the activity concentration of radionuclides in sediments and the corresponding health risk assessments from the hydrocarbon exploration environment of the southern coastal area of Delta State, Nigeria. A Sodium-iodide NaI(Tl) detector, with a well-calibrated multichannel analyzer (MCA) to ensure efficiency and energy was utilized. A total of seventy-five sediment samples (Five sediment samples each per community) were collected from the southern coastal area of Delta State, Nigeria. The mean activity concentrations of 40K, 238U, and 232Th of the sediment samples were 3361.48 ± 194.26 Bqkg−1, 40.11 ± 16.17 Bqkg−1, and 45.73 ± 19.27 Bqkg−1 respectively. The obtained mean values exceeded the world standard limit of 400 Bqkg−1, 35 Bqkg−1, and 30 Bqkg−1 respectively. Also, the computed mean radiological health hazard risk of radium equivalent activity (Raeq), representative level index (Iyr), external hazard index (Hex), internal hazard index (Hin), absorbed gamma dose rate (D), annual effective dose equivalent outdoor and indoor (AEDE) and lifetime cancer risk (ELCR) values are 363.94 ± 32.37 Bkgl−1, 2.9657 Bkgl−1, 0.9839, 1.0919, 175.82 nGyh−1, 2.1556 mSvyr−1, 0.8625 mSvyr−1, and 7.5447 mSvyr−1 respectively. The values were found to be slightly higher than the world standard limit. Therefore, the residents that are using the sediments of the southern coastal area for the construction of buildings as well as dwelling in houses built with such sediments are exposed to these radiological materials. This may pose a radiological health risk concern. The obtained results will serve as radiation and radiological baseline data for sediments of the southern coastal area of Delta State, Nigeria.

Radiometric evaluation of annual effective dose in water from Zobe Dam, North-Western, Nigeria

The communities located closed to the Zobe Dam which flows through many tributaries in Kastina State, utilizes the dam water for irrigation, drinking and other domestic activities. The level of radionuclide in water varies due to human factors, geological and geographical locations. There is need to evaluate the radiological health risk of the communities that uses the water for domestic activities, due to extensive farming around the dam. The annual effective dose (ADE) due to gross alpha and beta particles assists to estimate the radiological risks connected with making use of water in Zobe Dam for domestic purposes, were estimated. The low background Gas-less Alpha/Beta counting system (MPC 2000DP), was used to evaluate the alpha and beta activity concentration of the sample. The alpha activity ranged was 0.735±0.43 to 11.401±0.29 Bq/L, while the beta activity ranged from BDL to 11.891±0.57Bq/L. The AED varied from 0.150 to 8.319 mSv/year for adults, 0.075 to 4.160 mSv/year for children, and 0.038 to 2.080 mSv/year for infants, respectively. The average AED in adults, children and infant exceeded the ICRP dose limits of 0.1mSv/year. Water utilized for domestic purposes from the Dam could be quite risky because of intense farm activities and existence of natural radionuclide, if sufficient steps are not performed.

Assessment of outdoor gamma exposure levels at some borehole and well sites in Dutse, Nigeria

The lives on the earth are continuously exposed to ionizing radiation originating mainly from natural sources. Fortunately, the associated health hazard is not an acute problem globally. However, health complications are inevitable in areas assumed to have high background ionizing radiation levels. The present study aims to unveil the scenarios of outdoor gamma radiation levels at Dutse, the northwestern part of Nigeria. In this study, gamma exposure levels (GEL) across sixty-six (66) selected boreholes and local wells located in the said region have been measured using a well-calibrated hand dosimeter (Radiation Alert Inspector). Using the GEL values some significant radiation parameters were calculated to determine the possibility of radiological health risks to the local people. The measured gamma exposure level around the boreholes is seen to vary from 1.1 - 1.9 μrem/hr with a mean of 1.5 μrem/hr and around the wells it ranges between 1.1 – 1.8 μrem/hr with a mean of 1.5 μrem/hr. For boreholes, the estimated annual effective dose (AED) varies between 13.50 – 23.31 μSv/yr with a mean of 17.29 μSv/yr and for wells the same resulted 13.50 – 22.08 μSv/yr with a mean of 17.92 μSv/yr. All the obtained dose values are lower than the UNSCEAR proposed world average level of 70 μSv/yr. The estimated average ELCR values was found to be 0.061 × 10-3 and 0.064 × 10-3 for boreholes and wells respectively. All findings were below the UNSCEAR recommended world average level of (0.29 × 10-3). In summary, this work indicates a low risk of exposure to outdoor ionizing radiation among the inhabitants around the study locations.

Evaluation of radiological health risk caused by the use of fly ash in cement and concrete production and its storage

ABSTRACT As a result of firing pulverized coal in thermal power plants, enormous amounts of fly ash (FA) are produced as industrial waste. The release into the atmosphere and storage of this industrial waste remains one of the major environmental problems that threaten human health by contributing to air, water, and soil pollution. The recovery and reuse of FA in the construction industry is the only economic solution to the existing problem. In this study, the potential radiological risk caused by the usage of FA in concrete and cement production as a main component and its storage in landfill sites was evaluated for people and works by estimating radiological parameters (activity concentration and alpha index, annual effective doses, and the corresponding excess lifetime cancer risks) based on activity concentrations of terrestrial radionuclides in FA. Also, the radiological risk to the workers working in the FA landfill site was evaluated using the Residual Radioactivity Onsite 7.2 code. The average activity concentrations of terrestrial radionuclides in FA samples from the Tunçbilek lignite coal-fired thermal power plant at Kütahya province of Turkey were measured as 417, 156 and 454 Bq kg−1 for 226Ra, 232Th and 40K, respectively. When using up to 35% by mass of FA in cement and concrete, the average values of the radiological parameters revealed that they were within the recommended safety limits. However, code estimations showed that a regular worker in FA storage would be exposed to a total effective dose rate greater than 3 mSv y−1.

Age-dependent annual effective dose and radiological health risk from salt and soil collected from Padag, Chaghi, Balochistan, Pakistan

ABSTRACT This study aimed to investigate the annual effective dose for different age groups and health hazards associated with natural radioactivity in salt and soil collected from Padag, Chaghi, Balochistan. All samples were analysed by using high-purity germanium (HPGe) and sodium iodide (NaI) detectors. The average values of concentration of 226Ra, 232Th and 40K in salt samples were found to be 10.49, 9.6 and 169.65 Bq.kg−1, respectively, using HPGe detector, while in case of NaI detector, these values were found to be 10.48, 9.89 and 161.73 Bq.kg−1, respectively. Similarly, the average values of concentration of 226Ra, 232Th and 40K in soil were found to be 24.59, 24.89 and 391.72 Bq.kg−1, respectively, using HPGe detector, while in case of NaI detector, these values were found to be 24.46, 24.71 and 358.31 Bq.kg−1, respectively. Significant correlations were found between the results obtained from HPGe and NaI detectors. The values of total annual effective dose due to ingestion of salt were found to be 2.46 × 10−5, 2.45 × 10−5, 3.55 × 10−5 and 1.13 × 10−5 μSv.y−1 using HPGe detector and 2.43 × 10−5, 2.44 × 10−5, 3.55 × 10−5 and 1.13 × 10−5 μSv.y−1 using NaI detector for the age groups (2–7 years), (7–12 years), (12–17 years) and (≥17 years), respectively. The highest value of annual effective dose was found in the age group 12–17 years and minimum was found in the age group ≥ 17 years. However, all values were found to be below the recommended value of 0.29 mSv. Total average radiological risk due to ingestion of salt for all age groups was found to be lower than the reported value.

Assessment of the radiological health risk from radionuclide presence and transfer factor from soil to corn in some selected non-oil producing riverine areas of Akwa Ibom state

The main objective of this study was to estimate the activity concentration (AC) of 238U, 232Th and 40K, assess the health risk information from radionuclides presence in the soil and corn and the transfer influence from soil to corn. The key device used for the analysis was a Sodium Iodide Thallium detector. 238U AC in soil ranges from 14.09±0.27 Bqkg-1 to 18.70±0.31 Bqkg-1 with mean value of 15.69±0.28 Bqkg-1; 238U AC in corn varies from 9.36±0.22 Bqkg-1 to 14.78±0.27 Bqkg-1 with mean value of 11.53±0.24 Bqkg-1. 232Th AC in soil is from 12.32±0.46 Bqkg-1 to 48.76±0.91 Bqkg-1 with mean value of 35.97±0.76 Bqkg-1. 232Th AC in corn ranges from 8.26±0.37 Bqkg-1 to 35.19±0.77 Bqkg-1 with average value of 17.86±0.53 Bqkg-1. 40K values from the soil samples varies from 313.61±6.81 Bqkg-1 to 472.63±8.36 Bqkg-1 with mean value of 384.672±7.52 Bqkg-1. 40K varies from 374.85±7.45 Bqkg-1 to 478.55±8.41 Bqkg-1 with average value of 425.51±7.93 Bqkg-1from corn samples. The mean transfer factor for 238U, 232Th and 40K was obtained as 0.73, 0.62 and 1.13 respectively. The mean values for the Radium equivalent, absorbed dose, annual effective dose, and excess lifetime cancer risk from soil are 96.75 Bqkg-1, 47.05 nGyh-1, 0.06 mSvy-1, 0.20×10-3 correspondingly [values from corn are 69.83 Bqkg-1, 35.04 nGyh-1, 0.04 mSvy-1, 0.15×10-3 respectively]. These values clearly showed, the radiation doses exposed to Akwa Ibomites through the consumption of corn cultivated in these areas and inhalation of soil poses no effect to their health. Therefore, there is no radiological risk of ingestion.

Evaluation of radiological health risk due to ingestion and inhalation of radon in commercial packaged fruit juices consumed in Turkey

ABSTRACT Fruit juices (FJs) are among the most popular beverages frequently preferred by consumers, believing FJs contain the nutritional values, minerals, phytochemicals, vitamins, and antioxidants necessary for a healthy life. However, FJs may contain natural radionuclides such as radon (222Rn), which originates from the fruit and water utilized in their production, at levels that may pose a health risk to people. Inhalation and ingestion of 222Rn gas increases the risk of lung and stomach cancer. In this study, commercially packaged FJs from the seventeen most popular brands consumed in Turkey were analyzed for physicochemical properties and 222Rn activity concentrations to evaluate the radiological health risk. The values of pH, brix and 222Rn activity concentrations in FJ samples varied from 2.68 to 4.28, 2.50 to 14.30%, 9.6 ± 1.1 to 25.2 ± 2.5 mBq/L, respectively. The radiological health risk caused by internal exposure was evaluated for children and adults by estimating the ingestion and inhalation annual effective dose. The average values of the total annual effective dose for children and adults were found as 0.039 µSv and 0.056 µSv, respectively, which are much lower than the recommended dose of 100 µSv for drinking water.

Radiolysis of water by α- and β-particles from spent nuclear fuel

When water is subjected to radiolysis by charged ionising radiation particles (β and α-particles) from nuclear plants, they generate H2 as one of the radiolytic byproducts which has highest Gvalues than other radiolytic products. The Gvalues obtained by α-radiolysis used are listed in brackets next to their respective nuclides which are: 237Np (2.551E−01), 241Am (2.269E−01), 242mAm(2.370E−01). In addition to a high Gvalue, it also has high calorific value (141 MJ/kg) which can be used in hydrogen energy generation (HEG). Hence, apart from the radiological health risk of nuclear plants, if H2 released nuclear plants is harvested and used in hydrogen energy generation it can result in great cogeneration opportunities where nuclear energy supplies hydrogen, which would otherwise be wasted, to a hydrogen energy generation plant for additional power generation.This is even more advantageous if one takes into consideration that hydrogen Gvalues (G(H)) values from nuclear plants increase with an increase in duration of water exposure to ionising radiation and also that it, i.e. (G(H)values also increase with an increase in radiation flux to which water is exposed. Hence the longer the nuclear plant is running and the higher the power reactor is increased (and consequently the radiation flux) the higher the Gvalues of hydrogen and therefore the higher the power output of hydrogen energy generation.The idea of cogeneration becomes even more lucrative if we consider that hydrogen energy generation is clean (also known as green energy) because of its insignificant contribution to environmental pollution. Therefore, as energy demand increases and the need to curb climate change by reducing over reliance on power generation that release large quantities of CO2 to the atmosphere is heightened; the more sense it makes from energy generation/supply and environmental protection point of view for cogeneration of hydrogen energy and nuclear energy.This article presents the results of radiochemical events/processes that occur when water is exposed to ionising radiation of charged particles (β and α-particles). These results supplement the fluctuation in effective dose theory/hypothesis of a previous study on time-dependent variations in the radiological health impact of an interim SNFS facility presented in 2021 (Leotlela, 2021). It also provides an analysis of factors that cause radiation damage by studying the effects of the dose rate on both high and low linear energy transfers (LETs). High LET radiation refers to all those particles with a track-average LET higher than a few eV nm−1. These include alpha particles, protons, neutrons, and heavy ions. Low LET, on the other hand, refers to particles with a track-average LET lower than 1 eV nm−1. These include beta, gamma, x-rays and electrons.