External Radiation Hazard Research Articles

Industrial Radiography Testing & Technique Safety for Human Body

The use of Industrial Radiography for examining the quality of Weld joints is very popular worldwide. In India, many welding activities like construction and laying the huge pipelines for gas and water transportation and distribution as well construction of storage tanks are performed. The objects are working under high pressure and therefore, it is important to produce the weld beads with high quality. Industrial radiography uses ionizing radiation to view objects in a way that cannot be seen otherwise. The method has grown out of engineering, and is a major element of non-destructive testing (NDT) to inspect materials for hidden flaws. The radiation caused by these facilities is very dangerous however, with the use of new technologies and proper protection, risks of injury and death associated with radiation can be greatly reduced. Use or radiation sources are associated with a certain amount of radiation hazard. With proper card, this can be minimized. Radiation hazards may be broadly classified as external hazards an internal hazard. External hazards occur when the source of radiation is outside the body and internal hazards arise when the source for radiation gets into the human system. Hazard evaluation is necessary in order to adopt suitable measures to control radiation exposure. The problem of internal hazard does not arise in the use of X-ray equipment. It is considerably easy to estimate the external radiation hazard and there are a number of devices suitable for this purpose.

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.

Natural Radioactivity Levels of the Beach Sands of Cleopatra Beach and Damlatas Beach (Türkiye) and Their Impact on Human Health.

HPGe γ spectrometry method was used to measure the natural radioactivity levels (40K, 232Th, and 226Ra) of the beach sand samples from Cleopatra Beach and Damlatas Beach in Antalya (Türkiye). The mean 40K, 232Th, and 226Ra radioactivity levels of the studied samples were calculated as 276.88 ± 17.24, 25.04 ± 2.88, and 17.06 ± 1.68 Bq/kg, respectively. Being below the radiation limits, these values indicate no risk in terms of public health. Moreover, the radiological risk parameters, such as excess lifetime cancer risk, radium equivalent activity (Raeq), absorbed γ dose rate (D), annual effective dose equivalent (Eaed), γ index (Iγ), internal radiation hazard index (Hin), and external radiation hazard index (Hex), were calculated. The values of all of these parameters were found to be below the internationally accepted radiation limit values. In addition, distribution maps showing the radiological situation of the region were generated although they did not pose a hazard to public health. No results were found in the analysis processes related to artificial radioactivity.

A review on radionuclide pollution in global soils with environmental and health hazards evaluation.

Human populations are being exposed to a wide spectrum of radiation from soils as a result of the availability of radiation sources. Assessing the ecological and health effects of radionuclides in soils is crucial to support the optimal soil management practices but large-scale studies are limited. This study compiled data on radionuclides (226Ra, 232Th, 40K, 238U, and 137Cs) in soils located across the world (44 countries and 159 places) between 2008 and 2022 and applied radiological hazards indices and several multivariate statistical approaches. The average activity concentration (Bq/kg) of 226Ra, 232Th, 40K, 238U, and 137Cs were 408.56, 144.80, 508.78, 532.78, and 83.12, respectively, whereas 226Ra, 232Th, 40K, and 238U exceeded the standard limits. The principal component analysis explained more than 91% of variation in soils. Based on the geoaccumulation index, 40K posed moderately to heavy contamination whereas 238U and 226Ra posed moderate contamination in soils. Moreover, the mean values of radiological hazards evaluation such as radium equivalent activity (487.17Bq/kg), external radiation hazard indices (1.32), internal hazard indices (2.15), absorbed dose rate (247.86 nGyh-1), annual effective dose rate (1.82 mSvy-1), activity utilization index (4.54) and excess lifetime cancer risk (63.84 × 10-4) were higher than recommended limit suggesting significant radiological risks in study region soils. The findings indicated that the study area soils were contaminated by radionuclides and unsafe for hazards in terms of the health risks linked with studied radioactive contents. The study is valuable for mapping radioactivity across the globe to determine the level of radioactivity hazards.

Assessing radiation hazards associated with natural radioactivity in building materials in Ho Chi Minh City, Vietnam

This study is aimed at assessing radiation hazards associated with natural radioactivity in common building materials used in Ho Chi Minh City, Vietnam. Thirty-six samples from eighteen types of building materials were collected to measure activity concentrations using the gross alpha/beta counting system and gamma-ray spectrometry. The gross alpha and gross beta activity concentrations ranged from 94.7 ? 31.3 to 1045.1 ? 112.3 Bqkg-1 and 104.9 ? 4.7 to 834.4 ? 37.1 Bqkg-1, respectively. In addition, the activity concentrations of 226Ra, 232Th, and 40K were also determined, which ranged from 4.1 ? 0.1 to 53.5 ? 0.4 Bqkg-1, 5.7 ? 0.1 to 83.6 ? 0.8 Bqkg-1, and 14.9 ? 0.8 to 664.9 ? 10.6 Bqkg-1, respectively. The indices including radium equivalent activity, external and internal radiation hazard, gamma and alpha indices, activity utilization index, and annual effective dose, were calculated to evaluate the radiological hazards of natural radioactivity. The results showed that these indices were below the recommended safety limits for most investigated samples except six brick samples, whose activity utilization indexes are slightly higher than the safety limit. Even so, all annual effective doses of the samples were found to be below the world average.

Radiological and Structural Characterization of Raw and Alkali-Activated Wood Ash and Metakaolin Blends

The aim of the presented research was to investigate the application possibility of wood ash and metakaolin to obtain alkali-activated materials as relatively new materials in the building industry. Thus, in order to assess the adequate use of these waste materials, structural and radiological characteristics should be considered. Until now, the focus has been on ash from thermal power plants produced by burning coal, but a large part of households in our country have individual fireplaces in which wood is used as the basic raw material; thus, it is very interesting to measure the activity concentration of radionuclide in wood ash as well as the possibility of reusing that ash for other purposes. All materials were studied, in terms of physical and chemical characteristics, by methods such as X-ray diffraction (XRD), Fourier transform infra-red (FTIR) spectroscopy, and scanning electron microscopy and energy-dispersive X-ray spectroscopy (SEM/EDS). XRD measurements of wood ash samples showed that it consists of calcite and larnite. FTIR spectroscopy revealed a polymeric Si–O–Al framework in alkali-activated materials and Si–O bonding bands corresponding to silicon dioxide. Determination of radionuclide content was performed by means of gamma-ray spectrometry. Results showed that the alkaline activation process led to the decrease in the activity concentration of radionuclides detected in the measured samples. External radiation hazard index (Hex) for wood ash was reduced by more than 50% after alkali activation. The results of activity concentration measurements in alkali-activated materials indicate potential for their safe application in building construction.

Determination of dose derived from building materials and radiological health related effects from the indoor environment of Dessie city, Wollo, Ethiopia

The eight most common construction materials in Dessie City were collected in order to determine the amount of natural radiation released and its effects on humans. This is the first time that such research has been conducted. A B13010 Gamma-ray spectrometry was used to determine the concentration of the daughter element photo peak (High Purity Germanium detector). These studies can be used to track changes in radioactivity caused by industrial and other human activities. The mean radioactivity concentrations of 226Ra, 232Th, and 40K were calculated to be 26.59 ± 3.26, 26.59 ± 2.76, and 115.65 ± 2.73 Bq kg−1, respectively. The calculated Radium equivalent activity (Raeq) and absorbed dose were lower than the global average. The estimated annual effective dose equivalent was 0.08 ± 0.01 mSv y−1. External and internal radiation hazard indices (Hex and Hin), activity utilization indices, alpha indices, and gamma representative indices are all lower than the world's recommended standards. The mean of the ELCR is lower than the global mean. The annual effective dose equivalent is slightly above the global average.

Evaluation of ultra-filtration ceramic membrane plant for the treatment of drinking water from Ram group aquifers in south Jordan

Jordan is facing a severe shortage problem in drinking water resources which is becoming a top governmental priority to meet local water demands. Groundwaters are considered one of the main available resources. At Ram region south of Jordan, deep bedrock group Aquifers provide groundwater with elevated levels of radium isotopes of 226Ra and 228Ra that exceed health-based regulatory standards. The present study investigated the performance of the newly installed ultra-filtration ceramic membrane plant supported with hydrous manganese oxide process. The concentrations of Radium, 226Ra and 228Ra in treated water were 0.157 ± 0.061 Bq/l and 0.328 ± 0.187 Bq/l respectively. During more than 18 months of operation for 12 h daily, maximum removal efficiency achieved for 226Ra was 86.2% and for 228Ra was 92% with 99% of water recovery. The concentrations of 226Ra, 232Th and 40K were analysed in collected soil samples from the dumping area nearby the plant. The radium equivalent activities, external radiation hazard index (Hex) and the internal radiation hazard index (Hin) associated with the natural radionuclides were calculated. For contaminated soil with wastewater from the backwash operation, the radium equivalent value was 3221.6 Bq/kg and both values of Hex and Hin were greater than unity. Recommendations on mentoring and safety procedures were highlighted.

Evaluation of natural radioactivity level in Delanta-Dawunt, Wollo District, Ethiopia

ABSTRACT In the Delanta-Dawunt district of Ethiopia’s northern eastern Amhara region, twenty-one different environmental samples (gemstones) were gathered. This is one of the opal-mining (gemstone) locations in Ethiopia. We divided the 21 obtained samples into seven groups. The study’s major goals were to quantify the activity concentration of gemstones (opals) and examine the health implications. For 226Ra, the activity concentration ranged from 11.97 ± 2.46 to 62.44 ± 14.99 Bq kg−1, 25.69 ± 3.69 to 137.84 ± 13.23 Bq kg−1 for 232Th, and 184.84 ± 3.59 to 968.56 ± 18.16 Bq kg−1 for 40K. 226Ra, 232Th, and 40K were found to have mean radioactivity concentrations of 29.84 ± 6.53, 68.44 ± 18.94, and 390.87 ± 6.09 Bq kg−1, respectively. Radium equivalent activity (Raeq), absorbed dose, annual effective dose equivalent, external and internal radiation hazard (Hex and Hin) index, and activity utilisation index have mean values of 151.68 19.46 Bq kg−1, 72.19 8.48 nGy h−1, 0.07 0.01mSv y−1, 0.43, 0.51, 0.57 0.08, and 0.29 0.03. 232Th has higher specific activity than the global average, while 40K has the same. Meanwhile, the absorbed dose is higher than the world’s means value. The average value of excess life cancer risk found in this study is the same as the world’s average value.

Pietra Leccese and Other Natural Stones in Puglia Region: A New Category of Building Materials for Radiation Protection?

In this paper, an in-depth and systematic study of the radiological characterization of three types of Puglia region natural limestones (Pietra Leccese, Pietra Mazzara and Carparo) was carried out. The investigation was performed by XRF spectroscopy for a chemical analysis, and gamma spectroscopy of the specific activity concentration of natural radionuclides 226Ra, 232Th, and 40K. Although the limestone does not fall within the category included by Italian Legislative Decree 101/2020, the gamma index was calculated using the results of the gamma spectroscopy measurements. For Pietra Mazzara and Carparo stones, the gamma index was found to be less than the reference value; conversely Pietra Leccese was found to be higher. To obtain a more complete evaluation of the external exposure, radium equivalent activity and external radiation hazard were calculated for all analyzed stones. The results suggest the need to broadly consider the radiological risk for these stones, and for limestone more generally, when used as a building material.

Assessment of Radioactivity Contents and Radiological Effects of Marble, Granite, and Ceramic Used in Alexandria City, Egypt

The main aims of the present study are to analyze and internationally comparing the radioactivity contents of (226Ra, 232Th, and 40K) in marbles, granites, and product and raw materials of ceramics utilized in different construction purposes in Alexandria city, additionally, the associated radiological hazard indices have been assessed. Measurements have been performed by using high-resolution gamma rays spectrometer equipped with (HPGe) detector. The mean levels of the radioactivity of (226Ra, 232Th, and 40K) in marbles were 26.87, 4.30 and 19.13 Bqkg-1; respectively, and in granites were 42.90, 58.40, and 933.36 Bqkg-1; respectively, while in ceramic were 47.73, 66.09, and 385.59 BqKg-1; respectively. Results of ceramic raw materials showed the highest levels for 226Ra and 232Th as 16307.46, and 1738.69 Bqkg-1 both are recorded in zirconium, while the highest of 40K as 1760.62 Bqkg-1 in feldspar. Radiological hazards were assessed by radium equivalent activity, external and internal radiation hazard indices as well as the annual effective dose. The maximum values of indices were observed in Baltic Brown granite samples to be 425.92 Bqkg-1, 1.15, and 1, 48 for radium equivalent, external and internal hazard indices; respectively. The observed highest external effective doses in marble, granite, and ceramic were 396.53, 2109.81, and 1495.06 µSvy-1; respectively. From the obtained results is clear that granite may pose health risks as well, additional regulating the amount of zircon adding to ceramic industries is highly required.

Multivariate statistical approach on distribution of natural and anthropogenic radionuclides and associated radiation indices along the north-western coastline of Aegean Sea, Greece

A comprehensive radiological survey using multivariate statistical analysis was carried out to evaluate the distribution of 40K, 232Th, 226Ra, 235U, and 137Cs, and associated radiation indices in beach sand samples of the coastal area of the Aegean Sea. The activity concentration of selected radionuclides was measured and no clue of recent migration of radiocaesium by not only precipitation but also through an indirect way, such as ocean runoff, was found. As part of radiological risk assessment, external radiation hazard index, radium equivalent activity, effective dose, and absorbed dose rate were estimated. Pearson correlation, cluster, and PCA analysis were used by processing observed radiological parameters to determine the correlation between the radiological parameters and locations. Pearson correlation shows a strong association between all parameters and activity of 226Ra and 232Th. A spatial distribution map was provided to a distinct visual representation of the distribution of radionuclide contents in the study area.

Characterization of the health and environmental radiological effects of TENORM and radiation hazard indicators in petroleum waste –Yemen

The technologically enhanced naturally occurring radioactive materials (TENORM), i.e., 40K, 232Th, and 226Ra in waste petroleum scale, sludge, and produced water in Ma’rib Refinery - Yemen - were measured using spectroscopy with HPGe detector. To determining the radiation hazard of TENORMs in waste petroleum, The radium equivalent activity (Raeq), gamma-ray index (Iγ), external radiation hazard index (Hex), internal radiation hazard index (Hin), absorbed dose rate (ADR), annual effective dose (AED), annual gonadal dose equivalent (AGDE), alpha index (Iα) excess lifetime cancer risk (ELCR), and activity utilization index (AUI) are calculated to determine the radiation hazard of TENORMs in waste petroleum. The radiological data were analyzed using multivariable statistical methods to determine the discrepancies and similarities between the various samples. Frequency distributions have been studied for all radionuclides. There were fourteen variables measured in the data studied. The results of the Pearson correlation coefficient showed a positive correlation between all concentrations of TENORMs and all radiation hazard indicators. Factor analysis results in a two-component representation of the data obtained from waste petroleum samples. The dendrogram resulting from the Hierarchical Cluster Analysis divided the twenty-eight waste petroleum samples into three main groups using fourteen variables.

CHARACTERIZATION OF SAND SAMPLES FROM KARACHI BEACHES USING GAMMA SPECTROMETRY AND XRD.

Chemical phase and distribution of natural radionuclides (226Ra, 232Th and 40K) were determined for sand samples collected from ten different beaches of Karachi. All samples, except one, were identified with major and minor phases as SiO2 and CaCO3, respectively. The average activity concentrations were 24.9, 25.0 and 239Bq kg-1 for 226Ra, 232Th and 40K, respectively. Including all samples, the average radium equivalent activity was 79.1Bqkg-1. The external and internal radiation hazard indices and representative level index were all found below unity. The average air absorbed dose rate at 1m above the sand due to the natural radionuclides was 18.3 nGy h-1, which was less than the world average for soil. The corresponding annual effective dose rate was 22.4μSv y-1. It was found that Raeq had positive significant correlation with the amount of quartz present at the beaches.

Natural radioactivity and radon exhalation rate of Sardinian dimension stones

Due to the ever-growing public concern about radon risk arising from building materials, the radon exhalation rates and the natural radioactivity of eighteen dimension stones mostly used in Sardinia and widely exported worldwide have been estimated by means of laboratory tests. Some of the quarrying companies that operate within the Sardinian territory provided the samples to be tested, which include twelve granitoids, four pyroclastic rocks and two basalts. The Activity Concentration Index (Iɤ), the External Radiation Hazard Index (Hex) and the Radium equivalent activity (Raeq) were calculated for each rock sample under investigation, based on the estimated values of 222Rn exhalation rate and 226Ra, 232Th and 40K radioactivity concentration. A poor correlation between radon release rates and 226Ra radioactivity concentrations was found. The contribution to indoor radon accumulation was also simulated for the stone with the highest 222Rn exhalation rate and the resulting concentration compared with the limit value establish by the 2013/59/Euratom Directive. These findings can be extended to rocks formed in similar geodynamic settings that are likely to produce igneous rocks with similar petrographic and geochemical features.

Analysing radionuclide content in soil samples and radiological risks in the clayey material surrounding of the “Zbegovi” deposit, Donje Crniljevo, Serbia

This paper presents the results of analyses of radionuclide content in the samples of the surrounding soil and clayey material of ?Zbegovi? open-pit mine in Donje Crniljevo, Serbia. Samples from 78 sites were collected and prepared. The activity concentrations were determined for radionuclides: 238U, 232Th, 40K, 226Ra, and 137Cs. The mean values obtained are as follows: 23 Bqkg?1, 89 Bqkg?1, 372 Bqkg?1, 56 Bqkg?1, and 11 Bqkg?1, respectively. Concentrations of 238U, 40K, and 226Ra in the studied area do not deviate from the values obtained for the soil in Serbia. The concentration of 232Th in the studied area is slightly higher relative to average values for soil, and slightly lower compared to similar deposits of clayey material in the world. Measurements performed showed that the open-pit mine of clayey material is completely uncontaminated surface as far as 137Cs is concerned, while there are sites where measured 137Cs concentrations are significantly higher, which is due to topographic differences and inhomogeneous surface contamination of land after the Chernobyl accident. To assess the radiological risks in the observed area, the following indices were determined: absorbed dose rate, annual outdoor effective dose, absorbed dose for biota, excess lifetime cancer risk outdoors as well as external radiation hazard index. The mean value of the estimated absorbed dose rate in the given area amounts to 80.1 nGyh?1, and the annual outdoor effective dose ranges from 46.9 to 134 Sv. Absorbed dose rate for biota in the studied area is 1.31 10?4 Gyd?1. The mean excess lifetime cancer risk outdoors for the population is 3.8 10?4, and t he mean value of the external radiation hazard index obtained in this study is 0.48, which is consistent with the world average. A low dose of radiation will not pose a risk to the population and biota in the studied area.

A study on radionuclides content and radon exhalation from soil of Northern India

Radioactivity dispersed in indoor environment is a consequence of exhalation of radioactive gas radon from soil, building materials, and rocks containing primordial radionuclide. The health risk for population from the radionuclides and radon exhalation rates of soils from different places in vicinity of Kurukshetra in Northern India is estimated. Radionuclides content and radon exhalation rate of the soil samples are measured using gamma and alpha spectroscopy, respectively. Various doses (absorbed gamma dose and annual effective dose) and associated index (Alpha, Gamma, External, and Internal Radiation Hazard Indices) with radionuclide contents present in soil samples are also estimated. Radiological hazards are calculated by two different approaches; one based on radionuclides content and emanation factor and other on the basis of exhalation rates and room dimensions. The results of radioactivity content and exhalation rates are found below the level recommended by United Nation Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). Alpha equivalent dose (HE) is also estimated as per the recommendations of UNSCEAR and found well below the safe limit. The study is helpful to determine the soil potential to exhale carcinogenic gas radon at the surface and also for radon and thoron mapping.

Measurement of Radioactivity Levels and Health Risks in the Surrounding Soil of Shazand Refinery Complex in Arak, Iran, Using Gamma-Ray Spectrometry Method

ntroduction: The purpose of this study was to measure the radioactivity in the agricultural soil of south-east of Shazand Refinery Complex to determine both reliable baseline data on the radiation level and the radiation dose exposure to the farmers and inhabitants of the studied area. Material and Methods: This study was conducted on 21 soil samples collected from two different lands. Sampling spots in each land were selected for the assessment of specific activities of radionuclides of 226Ra, 232Th, 40K, and137Cs by using high purity germanium detector setup. Standards of International Atomic Energy Agency references material gamma ray uranium, reference gamma-ray thorium, and reference gamma-ray potassium were used for quality control and determining efficiency calibration. All samples were examined for radium equivalent, absorbed gamma dose rate, internal hazard index, external radiation hazard, annual gonadal dose equivalent, indoor and outdoor annual effective dose equivalent, and excess lifetime cancer risk. Results: The specific activities of radionuclides 226Ra, 232Th, 40K, and 137Cs varied from13.12 to 33.03, 11.3 to 35.86, 257.82 to 605.5, and 1.28 to 13.36 Bq/kg, respectively. Moreover, the results of this study were compared with those reported from other countries and worldwide average. Conclusion: Although all samples were polluted by the 137Cs fission product, the measured values were within the global reported safety limits. Therefore, there is no risk for farmers and inhabitants in this region.

Radiation precautions for inpatient and outpatient 177Lu-DOTATATE peptide receptor radionuclide therapy of neuroendocrine tumours

Background177Lu-DOTATATE peptide receptor radionuclide therapy is administered to patients on an inpatient and outpatient basis for the treatment of well-differentiated, metastatic neuroendocrine tumours. Following administration, these patients present an external radiation hazard due to the gamma emissions of lutetium-177. The purpose of this study was to determine precautions to be observed by 177Lu-DOTATATE patients to restrict the dose received by patients’ family members to less than 5 mSv in 5 years and members of the public to less than 1 mSv per year in line with the current UK legislation. Retrospective data from therapeutic administrations of 177Lu-DOTATATE (Mallinckrodt Pharmaceuticals) and Lutathera® (Advanced Accelerator Applications) were analysed to measure activity retention at discharge. Patient dose rate measurements were assumed to follow the same activity decay curve as that derived from a least squares fit of geometric mean counts in planar whole-body scans performed at four time points post-administration. Combining this with social contact times, the cumulative dose received through contact with the patient was estimated and an iterative process used to determine the length of contact restrictions to ensure the relevant dose constraints are not exceeded.ResultsOn average, 36% of the administered activity was retained at the time of discharge for inpatients receiving 177Lu-DOTATATE (Mallinckrodt). Retentions of 24% and 38% were measured for Lutathera® inpatients and outpatients respectively. Inpatients should restrict day contact and sleep separately from their partner for 15 days and remain off work for 5 days post-therapy. Contact with children for whom the patient is the main carer should be restricted for 16, 13 and 9 days for children below 2, 2–5 and 5–11 years respectively. One additional day is added to outpatient restriction periods, except for children aged 2–5 years which remains 13 days. No private transport restrictions are required. Patients should limit travel by public transport to 1 h on the day of discharge.ConclusionRestrictions are necessary to limit radiation dose to members of patients’ household and the public. Proposed precautions for inpatient and outpatient 177Lu-DOTATATE therapy protocols restrict the dose received to less than the limit imposed by the UK legislation.

Natural Radioactivity and Radiological Impact Assessment of Soil, Food and Water around Iron and Steel Smelting Area in Fashina Village, Ile-Ife, Osun State, Nigeria

This study assessed the natural radioactivity and radiological health impact of thirty-eight (38) samples of soil, food and water in Fashina village, Ile-Ife, Osun State, Nigeria using portable survey meter with a Global Positioning System (GPS) and well-calibrated NaI(Tl) detector system The mean exposure rates in the study area were 0.14 μSv hr -1 and 0.12 μSv hr -1 in soil/food and water samples respectively. The mean radioactivity content obtained for 238 U, 232 Th and 40K were 12.14 ± 4.17Bq kg -1 , 23.23 ± 7.67 Bq kg -1 and 270.14 ± 61.79Bq kg -1 respectively in soil samples and 8.56 ± 2.80Bq kg -1 , 13.17 ± 4.48Bq kg -1 and 89.41 ± 24.15Bq L -1 respectively for 238 U, 232 Th and 40K in water samples. The mean values of 30.91, 15.64 and 12.47 nGy h -1 were obtained for the absorbed dose rate in soil, food and water, respectively, while 37.90, 178.79 and 1085.23 μSv y -1 were obtained for the Annual Effective Doses (AED). Similarly, the Radium equivalent (Raeq) were 66.16 Bq kg -1 , 34.28Bq kg -1 and 27.31BqL -1 , in soil, food and water, respectively. The external and internal radiation hazard indices were 0.18 and 0.21, 0.09 and 0.12, 0.07 and 0.09, respectively for soil, food and water. The values obtained for the Excess Lifetime Cancer Risk (ELCR) in (x 10 -3 ) were also 0.13, 0.63 and 3.80 for the soil, food and water samples, respectively. It was found that the values of some exposure rate, radioactivity contents and radiological impact parameters in the study area which were higher than those of the control area and the world average values poses a serious health risk to the environment and its inhabitants. Keywords : Radioactivity, Scrap Metal, Gamma Spectrometry, Radiological Impact Parameter