Effective Dose Equivalent Research Articles

Use GIS Technical to map Natural Radioactivity in Soil Samples for the University of Kufa, Iraq

GIS "Geographic Information System" technology was used to map the specific activity (S.A.) of primordial radionuclides 238U, 232Th, and 40K in selected soil samples for twelve locations at the University of Kufa, Iraq. S.A. values were determined using gamma spectrometry type NaI(Tl) with volume “3×3”. Also, the values of radiological parameters such as Raeq“radium equivalent”, Hex “external hazard index”, Iγr “representative gamma risk index”, Dr “Absorbed Dose rate, AEDEoutdoor “Annual Effective Dose Equivalent in outdoor”, and ELCR “Excess Lifetime Cancer Risk” were determined. The average value of S.A. for 238U, 232Th, and 40K was 10.35±0.9 Bq/kg, 7.31±1.8 Bq/kg, and 256.19±55.7 Bq/kg, respectively. While, the average values of Raeq (Bq/kg), Hex, Iγr, Dr (nGy/h), AEDEoutdoor (mSv/y), and ELCR were 48.00, 0.130, 0.373, 23.70, 0.029, and 0.102×10-3, respectively. The results of S.A. and each radiological parameter of the study area locations were low according to acceptable level reports by UNSCEAR, ICRP, and OCDE. Therefore, it can be concluded that the soil samples of the University of Kufa were safe.

Evaluation of damage discrimination in dopaminergic neurons using dopamine transporter PET tracer [18F]FECNT-d4

BackgroundParkinson’s disease (PD) is a prevalent neurodegenerative disorder worldwide, diagnosed based on classic symptoms like motor dysfunction and cognitive impairments. With the development of various radioactive ligands, positron emission tomography (PET) imaging combined with specific radiolabelling probes has proven to be effective in aiding clinical PD diagnosis. Among these probes, 2β-Carbomethoxy-3β-(4-chlorophenyl)-8-(2-[18F]-fluoroethyl) nortropane ([18F]FECNT) has been utilized as a PET tracer to image dopamine transporter (DAT) integrity in striatal presynaptic dopaminergic terminals. However, the presence of brain-penetrant radioactive metabolites produced by [18F]FECNT may impact the accuracy of PET imaging. In previous research, we developed 2β-Carbomethoxy-3β-(4-chlorophenyl)-8-(2-[18F]-fluoroethyl-1,1,2,2-d4) nortropane ([18F]FECNT-d4), a deuterated derivative with enhanced stability in plasma and the striatum, along with a slower washout rate. In this study, we further investigated the potential of [18F]FECNT-d4 to detect dopaminergic neuron degeneration in Parkinson’s disease. This involved PET imaging in unilaterally-lesioned PD model rats and in vitro autoradiography conducted on postmortem brain sections.ResultsPET images revealed reduced specific uptake in the ipsilateral striatum of rats stereotactically injected with 6-hydroxydopamine hydrochloride (6-OHDA). Compared to the sham group, the ratio of standardized uptake value (SUV) in the ipsilateral to contralateral striatum decreased by 13%, 23%, and 63% in the mild, moderate, and severe lesioned groups, respectively. Dopaminergic denervation observed in PET imaging was further supported by behavioral assessments, immunostaining, and monoamine concentration tests. Moreover, the microPET results exhibited positive correlations with these measurements, except for the apomorphine-induced rotational behavior test, which showed a negative correlation. Additionally, [18F]FECNT-d4 uptake was approximately 40% lower in the postmortem striatal sections of a PD patient compared to a healthy subject. Furthermore, estimated human dosimetry (effective dose equivalent: 5.06 E-03 mSv/MBq), extrapolated from rat biodistribution data, remained below the current Food and Drug Administration limit for radiation exposure.ConclusionOur findings demonstrate that [18F]FECNT-d4 accurately estimates levels of dopaminergic neuron degeneration in the 6-OHDA-induced PD rat model and effectively distinguishes between PD patients and healthy individuals. This highly sensitive and safe PET probe holds promising potential for clinical application in the diagnosis and monitoring of Parkinson’s disease.

Radiological impact assessment of a dirty bomb using Hotspot Code and AI: Insights from spent nuclear fuel isotopes

This study evaluates the potential radiological effects resulting from the use of a Radiological Dispersal Device (RDD), commonly known as a “dirty bomb,” in Dhamar City, Yemen, focusing on its impact on human health. Seasonal atmospheric variations were analyzed using the HotSpot Health Physics Code to model the Total Effective Dose Equivalent (TEDE) distribution following an explosion. The TEDE’s effect on different human organs was assessed, considering both external and internal radiation exposures. The study demonstrated that winter nights posed the highest radiation risk, with dose distribution areas of 0.018 km2, 0.14 km2, and 3.3 km2 for inner, middle, and outer zones, respectively, surpassing other seasonal and daily values. Conversely, summer recorded the lowest radiation spread. A detailed temporal analysis during winter nights showed an initial TEDE of 9.5 Sv at 0.1 min post-explosion, which decreased exponentially to 1.3 Sv after 2000 min (33.3 h) and further to 0.0038 Sv after 6500 min (108.3 h) with the aid of AI-enhanced “Long Short Term Memory Networks (LSTM)”. The highest radiation doses to human organs within a 100 m2 area during the initial 10 min post-detonation were significantly above permissible limits, with critical organs like the surface bone, liver, and red marrow receiving doses of 68 Sv, 12 Sv, and 5.5 Sv, respectively. These findings underline the need for robust emergency response strategies and long-term health monitoring to mitigate the adverse health impacts of RDDs. The comprehensive assessment presented in this study, enhanced by artificial intelligence, provides essential data for improving public health safety and emergency preparedness in regions susceptible to radiological threats.

Background radioactivity level estimation and passive shield optimization using adjoint Monte Carlo method

The current study proposes a procedure to estimate the activity concentration of natural radionuclides and to optimize passive shielding solutions for HPGe detectors using adjoint Monte Carlo (MC) simulation technique of Geant4 for the first time. The background spectrum is acquired for 1.56 × 106 s using an HPGe detector model (GC3020), set inside a shielding solution, during 2021–2022 to estimate the activity concentration of natural radionuclides inside the shielding. While, a background spectrum for 65,000 s is acquired with shielding removed to estimate the concentration of natural radionuclides in the building materials of the laboratory. The detector design used in the simulations is validated by comparing computed and measured Full Energy Peak Efficiency (FEPE) for point sources 241Am, 152Eu, 137Cs, 133Ba, and 60Co. Adjoint MC simulations are used to compute the activity concentration of natural radionuclides assuming an isotropic distribution. The activity concentration of 40K, 226Ra and 232Th in the building material is found to be 524 ± 140, 83 ± 20 and 65 ± 18 Bqkg−1, respectively. The computed values are found in good agreement with the published data. The natural radioactivity levels of 40K, 226Ra and 232Th measured in lead shielding are 155.7 ± 0.1 mBqkg−1, 24 ± 13 mBqkg−1 and 33 ± 17 mBqkg−1 respectively. The radiological risks arising due to natural radioactivity is assessed by calculating radium equivalent activity (Raeq), indoor radiation hazard index (Hin) and annual effective dose equivalent. All the radiological parameters are found below their permissible limits and building materials may be considered radiologically safe. The optimal lead shield thickness for the detector is determined to be 12 cm, resulting in reduction of background signal by two orders of magnitude compared to an unshielded detector. The adjoint MC simulations in Geant4 are 103-104 times more rapid as compared to normal simulations for shield optimization of HPGe detectors and therefore, are identified as viable computing solution to calculate the activity of the background radiation.

A comprehensive dosimetry analysis of barakah nuclear power plant: Integrating gaseous and liquid radionuclide dispersion across multiple units

Monitoring radioactive releases during the normal operation of power plants is crucial to ensure compliance with safety limits set by regulatory bodies for environmental safety. In the case of the Barakah nuclear power plant in the UAE, comprehensive multiunit dispersion modelling and radiological safety analysis have been conducted. Utilizing the HotSpot Health Physics Code and GENII (Second-generation environmental dosimetry), assessments were made for both 37 gaseous and 51 liquid source terms generated by GALE. Release rates for source terms were determined using GALE based on APR 1400 specifications. HotSpot employed the Gaussian Plume model to simulate the dispersion of gaseous source terms up to 80 km surrounding the plant, calculating Total Effective Dose Equivalent (TEDE) and Committed Effective Dose Equivalent (CEDE) in rural and urban areas. Findings indicated that neither scenario exceeded the 1 mSv threshold for the general public nor the 20 mSv limit for operational workers. Notably, skin, thyroid, and surface bones exhibited the highest CEDE, primarily influenced by iodide radionuclides. GENII's Surface Water module modelled the effects of liquid source terms, accounting for various contamination and exposure pathways such as external exposure and ingestion across different age groups. The calculated doses remained well below FANR's annual limits, with negligible cancer incidences and fatalities predicted for one year of exposure.

Monitoring of terrestrial gamma dose rate from the Kumaun Himalayan region of the Bageshwar district in Uttarakhand, India.

The present study is carried out in 42 sampling sites for the measurement of background gamma dose rate in six tehsils of the Bageshwar district that comes under the Kumaun Himalaya, Uttarakhand. The annual effective dose in the pre-monsoon and post-monsoon seasons was estimated from the measured values of the Gamma dose rate. It is found that the minimum and maximum values ranged between 0.01-0.39mSv per y (Arithmetic Mean=0.19mSv per y) in the pre-monsoon and 0.11-0.42mSv per y (Arithmetic Mean=0.20mSv per y) in the post-monsoon season of the year. The finding of the present study shows that the annual effective dose equivalent is higher than the worldwide average value recommended by the United Nations Scientific Committee on the Effects of Atomic Radiation.

Assessment of Natural Occurring Radioactive Materials and Radiological Hazards Exposure in Soil of Ohia in Umuahia South Abia State Nigeria, Using High Purity Germanium (HPGe) Gamma Ray Spectrometry

Evaluation of natural occurring radioactive materials (NORMs) and radiological exposure are important. The main goal of this work was to determine the NORMs level and radiological exposure risk in Umuahia, using High Purity Germanium Gamma Ray Spectrometry at IPEN, Brazil. The radionuclides (RDNs) such as: 40K, 226Ra and 232Th and radiological parametric indices (RPIs) such as: Absorbed Dose Rate in Air (D), Outdoor and Indoor Annual Effective Dose Equivalent (AEDE), Radium Equivalent Activity (Raeq), Annual Gonadal Equivalent Dose (AGED) and Activity Concentration Index (I) were determined. The mean values of 40K, 226Ra and 232Th in Bq kg-1 were: 147, 28, and 31 while the RPIs mean values for D, ,, AGED, Raeq, and I are: 37 nGy h-1, 0.05 mSv y-1, 0.18 mSv y-1, 260 y-1, 83 Bq kg-1 and 0.29 respectively. Mean value of RDNs were found to be lower than 412 Bq kg-1, 32 Bq kg-1 and 35 Bq kg-1 average value while RPIs were also lower than 59 nGy h-1, 0.08 mSv y-1 for , 0.42 mSv y-1, 300 y-1 for AGED, 370 Bq kg-1 for Raeq, and 1 mSv y-1 respectively global safe limit or mean values. It is concluded that the soil is radiological safe for agriculture, building and construction purposes.

Annual Effective Dose Equivalent and Excess Lifetime Cancer Risk from Measured Indoor Background Ionizing Radiation in Pharmacy, Radiotherapy/Oncology and Radiology Departments of Federal Teaching Hospital, Gombe, Gombe State, Nigeria

Annual Effective Dose Equivalent and Excess Lifetime Cancer Risk from Measured Indoor Background Ionizing Radiation in Pharmacy, Radiotherapy/Oncology and Radiology Departments of Federal Teaching Hospital, Gombe, Gombe State, Nigeria

Assessment of Natural Occurring Radioactive Materials and Radiological Hazards Exposure in Soil of Ohia in Umuahia South Abia State Nigeria, Using High Purity Germanium (HPGe) Gamma Ray Spectrometry

Evaluation of natural occurring radioactive materials (NORMs) and radiological exposure are important. The main goal of this work was to determine the NORMs level and radiological exposure risk in Umuahia, using High Purity Germanium Gamma Ray Spectrometry at IPEN, Brazil. The radionuclides (RDNs) such as: 40K, 226Ra and 232Th and radiological parametric indices (RPIs) such as: Absorbed Dose Rate in Air (D), Outdoor and Indoor Annual Effective Dose Equivalent (AEDE), Radium Equivalent Activity (Raeq), Annual Gonadal Equivalent Dose (AGED) and Activity Concentration Index (I) were determined. The mean values of 40K, 226Ra and 232Th in Bq kg-1 were: 147, 28, and 31 while the RPIs mean values for D, ,, AGED, Raeq, and I are: 37 nGy h-1, 0.05 mSv y-1, 0.18 mSv y-1, 260 y-1, 83 Bq kg-1 and 0.29 respectively. Mean value of RDNs were found to be lower than 412 Bq kg-1, 32 Bq kg-1 and 35 Bq kg-1 average value while RPIs were also lower than 59 nGy h-1, 0.08 mSv y-1 for , 0.42 mSv y-1, 300 y-1 for AGED, 370 Bq kg-1 for Raeq, and 1 mSv y-1 respectively global safe limit or mean values. It is concluded that the soil is radiological safe for agriculture, building and construction purposes.

Evaluation of radiation dose associated with underground uranium mining activities in east Singhbhum, Jharkhand, India

This paper presents the effect of ventilation parameters on the 222Rn inhalation dose in an underground uranium mine located in east Singhbhum of Jharkhand, India. This study reveals that the airflow rate variable statistically significantly predicts the 222Rn dose variable in the mine. On the other hand, no significant effect of other ventilation parameters such as barometric pressure, dry-bulb, and wet-bulb temperatures on 222Rn inhalation dose in the stopes was observed due to negligible variations in their values. Therefore, the airflow rate plays a significant role in reducing the effective radiation dose level in mines. In this study, the Equivalent Equilibrium Radon concentration (EER) and total effective radiation dose received by the miners involved in different mining activities in the various locations of the mine were found to be in ranges of 130–420 Bq m−3 and 0–3.17 mSv y−1, respectively. It also reveals that the miners involved in the stope preparation and timbering were exposed to more radiation than other mining activities. Under the existing ventilation conditions, the total effective radiation dose was far below the safe limit of 20 mSv y−1 recommended by the International Commission of Radiological Protection.

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.

Calculate the Rate of Natural Radioactivity in the Soil of Some Schools Using the NaI(Tl) Detector in the City of Hilla-Iraq

Activities and risk markers in 15-20 cm soil samples from Hilla City schools were thoroughly examined. This was made possible by the NaI(Tl) detector. The results indicated that the specific activity values for 238U from 2.244±0.06 Bqkg-1 to 23.637±0.60 Bqkg-1, with an average value of 11.70±0.39 Bqkg-1. Similar to 232Th, the average specific activity level was 8.53±0.31 Bqkg-1, ranging between 1.603±0.09 Bqkg-1 and 21.503±0.56 Bqkg-1. For 40K, its specific activity range was 222.96±2.72 to 441.824±2.78 Bqkg-1, with an average of 375.32±2.71 Bqkg-1. The average radiative forcing of the radium equivalent (Raeq) was calculated to be 52.80 Bqkg-1. The external risk index (Hex) was 0.14, and the internal risk index (Hin) was 0.17. The gamma risk index (Iγ) was determined to be 0.41. Also, the average outdoor absorbed dose level Dout is 26.35 nGyh-1, while the average indoor absorbed dose level Din is 50.54 nGyh-1. The average annual values of effective dose equivalents (internal and external) are 0.03 and 0.25 nGyh-1. The additional lifetime cancer risk ELCR(t) due to natural radioactivity in the models was 0.93x10-3. Note that the global average permissible nuclide concentration was 30, 32, and 420, and the danger index values were 1, 1, 6, 59, 84, 0.4, 0.07, and 1.45, respectively, based on the report of the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). After carefully comparing the study results with permissible global averages, they fit well within the recommended range.

37 years after the chernobyl: the current radiation status in Kocaeli, Turkey

This study aims to assess the artificial and natural radiation dose levels in certain districts of Kocaeli province within the Marmara region, 37 years after the Chernobyl nuclear accident, and evaluate the current status prior to potential nuclear leakage events from Zaporijya or other nuclear power plants. Radioactive concentrations of 232Th, 238U, 40K and 137Cs were determined using HPGe gamma spectrometry in 26 soil samples collected from the region of interest. The average concentrations were found to be 22.35 Bqkg−1 for 238U, 26.36 Bqkg−1 for 232Th, 368.34 Bqkg−1 for 40K, and 2.44 Bqkg−1 for 137Cs. Furthermore, the study revealed an absorbed dose rate of 41.73 nGyh−1, an annual effective dose equivalent of 51.18 µSvy−1, and an excess lifetime cancer risk of 0.00018.

Assessment of radiological consequences to a hypothetical accident of the 3-MW TRIGA Mark-II nuclear research reactor of Bangladesh

The radiological consequences to a hypothetical accident are assessed for the 3-MW TRIGA Mark-II Nuclear Research Reactor of Bangladesh for both wet and dry seasons. Accident simulations are crucial for assessing the potentialrisks in the event of a nuclear accident. ORIGEN code was used to carry out the facility's radionuclide inventory. In the event of a hypothetical accident, the Total Effective Dose Equivalent (TEDE) is assessed using HotSpots. The findings indicate that for stability class A during the rainy season, the selected radionuclides arrived at a downwind distance of 0.03 km with an arrival time of less than one minute, and the highest TEDE, respiratory time-integrated air concentration, and ground deposition activity, respectively, were marked at 2.8E-12 Sv, 9.4E-01 Bq-sec/m3, and 2.4E-05 kBq/m2. In the case of I-131 at 0.03 km from the source, the thyroid gland is the most sensitive human organ, followed by the lung, esophagus, thymus, surface bone, skin, and breast. The estimated Committed Effective Dose Equivalent (CEDE) from I-131 is 9.1E-11 Sv. In contrast, the adrenal was the most sensitive organ with a maximum CEDE of 1.3E-13 Sv in the case of Cs-137 at a downwind distance of 0.03 km. The highest TEDE values for the general public and the vicinity around the TRIGA Mark II reactor facility are lower than the annual dose limits.

Radiological environmental impact analysis of the uranium mining site in Mika, Nigeria using time series forecast model.

This study employs time series forecasting, specifically Seasonal Auto-Regressive Integrated Moving Average, to predict the radiological impact of uranium mining in Mika, Nigeria. By utilizing meteorological data to model the dispersion of radioactive emissions to receptors, allowing for a comprehensive assessment of potential health and environmental consequences. The study observed a slight change in the Total Effective Dose Equivalent (TEDE) at the nearest residence northeast receptor between the actual and the forecasted data. The findings could be largely because of the basement complex rock formations that characterized the Mika region. The study recommend proper monitoring and evaluation should be done before full-scale mining can be carried out. However, the TEDE is generally below the International Atomic Energy Agency recommended level of 1mSv per y for public exposure. The research demonstrates the significance of predictive modeling in managing and mitigating the radiological risks associated with uranium mining activities. Findings contribute to informed decision-making and sustainable resource extraction practices in Mika, Nigeria.

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.

A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities

The survivability of the domestic nuclear power industry depends on the cost-competitiveness of safe and secure nuclear power generation. Advanced reactor design concepts aim to have increased safety margins over traditional large light water reactors (LWRs). With increased safety margins comes the potential for a corresponding decrease in off-site risk to the general public from a hypothetical release of radioactivity due to sabotage or theft. Without sacrificing safety or security, advanced reactor designers may be able to achieve operational cost improvements over current LWRs in part by designing less burdensome physical protection systems (PPSs) and by replacing on-site response forces with off-site response forces. To accommodate these developments, the U.S. Nuclear Regulatory Commission is drafting new rulemakings for physical security when licensing through the current frameworks in 10 CFR 50 or 10 CFR 52 along with drafting an entirely new licensing framework: 10 CFR 53. A novel technology-inclusive consequence-informed methodology for the selection of the optimal licensing path for the design of PPSs at advanced fixed-site commercial nuclear power facilities is presented herein. This methodology proposes integrating security considerations at the beginning of a reactor facility design effort to streamline the licensing process. Off-site total effective dose equivalents at the exclusion area and low population zone boundaries were identified as the key metrics when determining a design’s most appropriate licensing path that in turn affects the design requirements placed upon the PPS. Given these metrics, source-term generation of potential adversary-induced physics-based sabotage actions utilizing severe accident modeling software and off-site plume dispersal modeling were identified as appropriate for determining siting constraints, potential target sets for hypothetical sabotage events, and their subsequent off-site dose consequences. The methodology proposes using the consequence results from the sabotage modeling, in combination with desired cost-saving PPS characteristics, to help inform the licensing path selection. Once a licensing path is chosen, the methodology utilizes the Design and Evaluation Process Outline to evaluate an effective PPS following the licensing requirements placed on the facility. This paper also presents examples of hypothetical commercial nuclear power facilities with varying consequence levels and demonstrations of how to select the optimal licensing pathways for each.

Radioactivity estimation of baobab (Adonsonia digitata) in katsina metropolis, katsina state Nigeria

Radioactivity estimation of baobab plants was carried out in Katsina metropolis, Katsina State, Nigeria. Samples of soil, roots, and leaves were collected, prepared and analyzed to estimate the activity concentration of the natural radionuclides of U-238, Th-232, and K-40using NaI (TI) gamma ray spectrometry detector. The results obtained showed that the activity concentration ranged from 0.1 Bq/kg to 33.26 Bq/kg, 1.98 Bq/kg to 64.98 Bq/kg and 65.89 Bq/kg to 1009.69 Bq/kg with overall mean values of 11.35, 18.87 and 545.14 in Bq/kg for U-238, Th-232 and K-40 respectively. In order to assess the radiological parameters of the natural radioactivity; the radium equivalent activity (Raeq), an absorbed dose rate and the measured annual effective dose equivalent were calculated and lies in the ranges of 18.83 to 183.22 (Bq/kg), 9.07 to 85.90 nGy/h and 0.011 to 0.105 mSv/y respectively; mean values obtained are 87.20 Bq/kg, 40.55 nGy/h and 0.050 mSv/y respectively. However, the calculated values obtained for all the radiological parameters falls below the world acceptable limits of 370 Bq/kg for Raeq; 89 nGy/h for the absorbed dose rate and 1 mSv/y annual effective dose rate for the general public; for the annual effective dose due to ingestion or inhalation of NORMS in the soil, medicinal plants and food is 0.07 mSv/y and the value is within the acceptable limit of intake; external and internal hazard index were calculated and found to have values of 0.23 Bq/kg for Hex and 0.30 Bq/kg for Hin and are lower than unity set by ICRP. Base on the radiological hazards evaluations, there is no any health risk due to radiation from the natural sources in using the roots and leaves parts of baobab plants for any purposes in the study area. Moreover, the measured soil around the study area was found to be safe and will not pose any radiation exposure to the population. Hence, the research will serve as the baseline for detection of any future released activities of related natural radionuclides especially around the consumable plants. However, effort should be made to ensure that the radiological parameters of the study area are kept as low as reasonably achievable.

Radiological consequence assessment from long term station blackout nuclear accident on Buyende nuclear power plant of Uganda

Uganda’s energy policy of 2023 and Vision 2040 plans to address the country’s electricity shortage by introducing nuclear power of 24,000 MW capacity by 2040. The pioneer nuclear power plants with a generation capacity of 8,400 MW will be built in Buyende District. This study focused on assessing the radiological consequences of potential nuclear accident on any of the four technologies of APR1400, VVER1200, HPR1000, and APR1000. Evaluation of acute and chronic radiation effects from a long-term station blackout accident using RASCAL and GENII codes identified the order of minimum health risks to the public as APR100, HPR1000, VVER1200, and APR1400 if single units are constructed. The total effective dose equivalents and thyroid doses at the exclusion area boundary and emergency protection zone were within the regulatory limits of 250 mSv and 3,000 mSv, respectively for all the reactor technologies.

Real-Time Radiological Practice: Dose Descriptors and Fatal Risk of Cancer Estimates in Adult Patient from Most Frequent Radiological Procedures in Ondo State, Nigeria

Background: The inspiration in establishing dosimetric methods for radio-diagnosis is based on the curiosity to estimating health risks to patient subjected to a given type of examination, using ionizing radiation. So, to establish strong relation between risks and benefits of a new diagnostic modality, study assessed real-time radiological practice by evaluating dose descriptors and fatal risks of cancer from most frequent radiographs. Patients and Methods: Mathematical approach was adopted to determine dose to 3,587 adult patients while PCXMC version 2.0, was employed in estimating their effective dose equivalent. Results: Low ESD and DAP recorded as 0.618 mGy (Ankle) and 0.124 Gycm2 (Hand AP) while high as 6.263 mGy (LS LAT) and 2.866Gycm2 (LS AP). The average estimated effective doses across radiographs confirmed Knee joint LAT and Ankle AP recording same low value of 0.001mSv and high as 0.822mSv from LS LAT. The range factor for the probability of fatal risks of cancer evaluated across radiographs was 10.142. Thus, low average lifetime risks of cancer ratio recorded as 1:27,778(Ankle AP) and high for LS LAT as 1:2,739, and the risks of cancer inducement estimates from this study fall within very low and low category of risks. Comparison of study results with some published values show good geometry but revealed high spread in values across radiographs studied. The study trend demonstrates the significance for awareness creation among the radiographic staff and the policies maker on quality control testing of equipment and adjustment of protocols. Conclusion: The need to bring the radiological practice in the State in line with National and European guidelines on quality criteria for diagnostic radiological images becomes very essential, for good radiological practice to be embraced.