Annual Dose Equivalent Research Articles

Radiological hazard assessment of the soil in Daquq district, Kirkuk, Iraq

Abstract This investigation assessed the baseline levels of radioactivity in the soil of Daquq district, Iraq, using the GR-460 radiation detection system. 238U, 232Th, and 40K’s specific activities were measured and the hazard indices’ values determined. The average values of the absorbed dose, annual effective dose equivalent, annual gonadal equivalent dose, and lifetime cancer risk radiological risk factors were estimated. It is important to note that some of these results exceeded the global average levels. Various multivariate statistical techniques were employed to explore the relationships between the radioactive variables and identify potential correlations amongst them. Cluster analysis was utilized to identify clusters or groups of variables that shared similar characteristics. The study aimed to gain insights into the relationships between the radioactive variables and identify any correlations between them. These analyses provided valuable information regarding the associations and patterns within the data, thus contributing to an improved understanding of the radioactive variables and their potential implications.

Assessment of radioactive nuclides and heavy metals in soil and drink water in Lahij city, Yemen

This study was conducted in Lahij city, Yemen, to evaluate the concentrations and potential health risks of natural radioactive nuclides and heavy metals in soil and drinking water. A total of 21 soil samples and 17 water samples were collected from various locations. A high-purity germanium gamma detector HPGe was used to measure the concentrations of 40K, 232Th, and 226Ra in all samples, along with the concentrations of heavy metals. In soil samples, the average concentrations of 40K, 232Th, and 226Ra were 731.5, 30.7, and 28.16 Bq kg−1, respectively. While some samples showed higher than permissible levels for 226Ra and 232Th, the overall average remained within acceptable limits. However, 40K levels were almost twice the recommended global limits. In water samples, the average concentrations of these nuclides were 5.38, 0.73, and 0.66 Bq L−1, all within the global safety limits. Radiological risk assessments for soil indicated an average radium equivalent activity (Raeq) of 124.4 Bq kg−1, absorbed dose rate in air of 59.9 nGy h−1, annual effective dose rate of 0.07 mSv y−1, outdoor excess lifetime cancer risk (ELCR) of 0.26 × 10−3, and annual gonad equivalent dose (AGED) of 336.6 mSv y−1. Risk indices, including the activity concentration index (Iγ), external hazard index (Hex), and internal hazard index (Hin), averaged 0.48, 0.34, and 0.41, respectively, all below global limits except for AGED, which slightly exceeded the recommended level. For drinking water, the total ingestion dose was calculated for different age groups. The average doses for infants, children, and adults were 0.15, 0.27, and 0.19 mSv y−1, respectively. The doses for children and adults exceeded the permissible limits, while those for infants were within safe levels. Heavy metal concentrations were measured in all samples, and the Hazard Quotient (HQ) was calculated. In soil samples, HQ values for all metals >1, indicating potential health risks. In water samples, HQ values were also >1 for all metals except vanadium (V) and iron (Fe). To reduce the dangers associated with radioactive nuclides and heavy metals, regular monitoring and cleanup are crucial, and further research is needed to understand contamination sources and long-term health impacts.

Assessment of radiological contamination due to gold mining in soil and food crops of Babban Tsauni, Gwagwalada, Nigeria.

This work assessed the activity concentrations of 238U(226Ra), 232Th, and 40K and their associated radiological risks due to exposure to soil and consumption of food crops in Babban Tsauni artisanal gold mine, Gwagwalada, Nigeria, using the gamma spectrometry technique. The mean activity concentrations of 226Ra, 232Th, and 40K in the mine soil were 60.2±9.9, 161.4±16.2, and 664.6±138.2, while they were 46.4±4.9, 79.9±39.3, 266.4±185.4 for tubers and 46.9±15.7, 100.5±35.8, 311.4±132.7 (Bq/kg) for grains, respectively. The results reveal that the activity concentrations of radionuclides in all samples exceeded the recommended values set by United Nations Scientific Committee on the Effects of Atomic Radiation (33, 45, and 420 Bq/kg) except 40K, which fell within the acceptable limit in all food crop sample types. Estimated results for radiological hazard parameters, radium equivalent, annual effective dose due to ingestion, and excess life cancer risk were within safe limits, while the annual effective dose due to external gamma radiation in soil and annual gonadal equivalent dose were significantly high in all investigated samples; these call for constant radiological monitoring.

Health risk assessment of radiation dose level in oranges and mangoes fruits from farms in Benue State, Nigeria

The health risk and radiation dose level in Oranges and Mangoes due to ingestion from farm locations in Benue State was assessed. A total of fifty (50) samples were collected in five different farm locations in Benue State, the samples were washed with distilled water to remove dirt, a radiation meter was placed 10cm from the fruits and measurements were taken for 30 seconds, background radiation levels and radiation dose level from the fruits were measured and calculated. The results showed that the radiation dose level for Oranges ranged from 1.489 to 2.365 mSv/hr and 1.122 to 1.899 mSv/hr for mangoes and the Annual Equivalent Doses (AED) for Oranges and Mangoes consumption was estimated to be 0.107 and 0.027 mSv/yr, respectively. Both values exceeded the World Health Organization (WHO) and the United States Environmental Protection Agency (USEPA) recommended limit of 1.0 mSv/yr. The high radiation levels could be attributed to naturally occurring radioactive materials in the soil or water, contamination from nearby sources. The Excess Lifetime Cancer Risk (ELCR) was calculated, with values of 0.2677 for Oranges and 0.683 for Mangoes, which are lower than the safe limit specified by WHO. While there is minimal risk associated with radiation exposure from consuming these fruits, further monitoring and investigation are necessary to ensure food safety and security in the study area.

Calculation of radiological risks for selected soil samples from the north of Kufa district in Najaf, Iraq.

To evaluate radioactivity levels in soil samples and their physical impact on the population. The experimental radiation study was conducted in northern Kufa, Al Najaf Governorate, Iraq, in March 2020 by researchers from the Kufa University, Iraq and comprised soil samples. A gamma spectrometer equipped with a sodium iodide detector activated with a trace amount of thallium was used to calculate the concentration of radium, thorium and potassium. Data was analysed using SPSS 20. There were 30 samples. The average concentration of Radium, Thorium and Potassium was (0.824± 0.392)ppm, (1.536± 0.645)ppm and( 0.597± 0.195)%, respectively, and the radiation hazards were lower than the permissible levels. The reported value of excess lifetime cancer risk was (1.2819 ±0.156)×10-3, and the annual gonadal equivalent dose (AGED) was 116.496± 41.255 (mSv. y-1), which was lower than the recommended limit. There was a positive, strong and significant relationship of radium with all the variables (p<0.05) studied except with potassium (p>0.05). Thorium was positively and significantly associated with all the variables (p<0.05). The study area was found to be safe and there was no relationship between the radiation levels of the studied nuclides and the risk of cancer.

Measurement of radioactivity and hazard index of Gonadal dose in selected Cement samples in Iraq.

Given the importance of cement as a basic material in construction, this study was undertaken to evaluate the level of radioactivity in a selected group of cement samples most used in construction to determine whether they are safe for human health. In this investigative study, nine samples of cement, both domestic and imported, that are often used in construction projects in Iraq were gathered. A NaI (Tl) gamma-ray spectrometer (3"x3") was used to measure the radioactivity in the samples. The average specific activity levels in the tested cement samples were 11.373±0.522, 5.795 ± 0.230, and 179.123±2.207 Bq/Kg, respectively. Also calculated was the average of the radium, which was equivalent to 33.449±1.022 Bq/kg. As for the risk indicators, the internal risk coefficient was 0.121±0.004 and external risk coefficient was 0.090 ±0.002. While studying the radiation doses, the values of effective annual internal dose was 0.080 mSv/y, external dose rates were 0.020 mSv/y, absorbed dose ratio was 16.321±0.476 nGy/h, and gamma index was 0.253±0.007. In the end, and depending on what was studied from various variables, with an average of 115.59 Sv/y, the annual gonadal equivalent dose risk (AGED) was calculated. The world average values were used to compare all the results. Finally, it was discovered that the radiation parameter levels of none of the samples had a detrimental effect on human health.

Determination of Natural Radioactivity Levels and Radiation Hazards from the Soil of Tin Mining in Kyerwa District, Tanzania

Gamma spectrometry was used to determine the activity concentrations of the natural radionuclides 226Ra, 232Th, and 40K in soil samples from the Tin mining in Kyerwa District, Tanzania. The study findings revealed that the mean activity concentrations of 226Ra, 232Th, and 40K were 90.68, 65.45, and 630.95 Bq/kg, respectively. These values were all greater than the average global activity concentrations for 226Ra, 232Th, and 40K which are 32 Bq/kg, 45 Bq/kg, and 420 Bq/kg, respectively. Assessments of the radiological risks associated with these naturally occurring radionuclides were done. In this case, the radium equivalent activity (Raeq), external hazard index (Hex), internal hazard index (Hin), and radioactivity level index (Iγ) were calculated. The results show that the mean values of Raeq, Hex, Hin, and Iγ were 230.6 Bq/kg, 0.628, 0.861, and 0.831, respectively. These results were below the global criteria levels for Raeq, Hex, Hin, and Iγ, which are 370 Bq/kg, 1, 1, and 2, respectively. Estimates for the absorbed dose rate in the air (DR), the annual effective dose equivalent (AEDE), and the annual gonadal equivalent dose (AGED) were also made. The findings revealed that the corresponding mean values for DR, AEDE, and AGED were 106.8 nGy/h, 1.07 mSv/y, and 744.4 μSvy-1. The mean values exceeded the global average value of 57 nGy/h for DR, 0.07 mSv/y for AEDE, and 2984 Sv/y for AGED. Therefore, Tin mining activities in the Kyerwa District could endanger the mining community from natural radioactive sources. In this study, therefore, we recommend performing a periodic inspection of the mining areas, monitoring the mining workers, and determining the level of activity and concentrations of different radionuclides in the mining area.

Radioactivity characteristics of lignite and hard coals: Case study of Zonguldak (Kozlu), Konya (Karapınar) and Antalya (Pamucakyayla) in Türkiye

Abstract In this study, the radioactivity contents of Carboniferous Zonguldak-Kozlu hard coals, Carboniferous Antalya-Pamucakyayla hard coals and Pliocene Konya-Karapınar lignites were determined, then compared with the limit values determined by the authorized institutions and their hazard indexes were determined. The range of measured activity concentrations was from 16.2 Bq·kg−1 to 227.6 Bq·kg−1 for 238U, 20.6 Bq·kg−1 to 67.5 Bq·kg−1 for 232Th and 211.9 Bq·kg−1 to 515.5 Bq·kg−1 for 40K. The calculated mean absorbed gamma dose rate (D), radium equivalent activity (Raeq) and annual equivalent dose (AED) were 105.7 nGy·h−1, 227.9 Bq·kg−1 and 129.6 μSv·h−1, respectively. Although 238U and 232Th radionuclide activity concentrations are comparable to literature values, 40K activity concentrations were around three or four times higher than in UNSCEAR (2000) reports. As it poses a radiological risk, it is necessary to take the necessary precautions to reduce the negative effects on the environment and human health due to use of coals from Konya-Karapınar, Antalya-Pamucakyayla basins and to burn in a controlled manner.

Assessment of natural radioactivity levels and hazard indicators in Tarakeshwor Municipality, Nepal through in-situ technique and multivariate analysis

The evaluation of primordial radionuclide concentrations in rapidly urbanized and concrete-laden areas through the importation of construction materials from various regions of Nepal is both important and essential. This study utilized a portable gamma-ray spectrometer (PGIS 2) to analyze the distribution of three natural radionuclides: uranium (238U), thorium (232Th), and potassium (40K) in Tarakeshwor Municipality, Kathmandu, Nepal. The measured dose rates ranged from 70.22 nSv hr−1 to 163.66 nSv hr−1, with an average of 124.65±20.29 nSv hr−1, surpassing the global average of 59 nSv hr−1. The activity concentrations of 40K, 238U, and 232Th exceeded global averages, indicating relatively higher natural radioactivity concentrations in the region. Specifically, the average values for 40K, 238U, and 232Th were 935.26±172.30 Bq kg−1, 80.47±15.53 Bq kg−1, and 80.44±18.58 Bq kg−1, respectively. The calculated radium equivalent (Raeq) ranged from 132.26 to 351.22 Bq kg−1, and the annual gonadal equivalent dose (AGED) varied from 372.61 to 1028.81 μSv yr−1. The annual effective dose rates for indoor and outdoor environments were 0.54±0.09 mSv yr−1 and 0.15±0.03 mSv yr−1, respectively, both exceeding the global average. The representative level index (RLI) within the study area averaged 1.96±0.32, indicating an elevated radiation risk. The excess lifetime cancer risk (ELCR) values for outdoor and indoor environments were 0.52×10−3 ±0.09 ×10−3 and 1.87 ×10−3 ±0.31×10−3, respectively, surpassing the world average. Additionally, external hazard indices (Hex) ranged from 0.36 to 0.59, while internal hazard indices (Hin) ranged from 0.38 to 1.20, both indicating values higher than UNSCEAR recommendations. These findings underscore the necessity for further experimental analysis employing ex-situ equipment. The data generated in this study can provide a valuable baseline for future assessments and interventions in radiation risk management guidelines within the country.

Occupational Radiation Dose Trends in U.S. Radiologic Technologists Assisting with Fluoroscopically Guided Interventional Procedures, 1980–2020

PurposeTo summarize dose trends from 1980 to 2020 for 19,651 U.S. Radiologic Technologists who reported assisting with fluoroscopically guided interventional procedures (FGIPs), overall and by work history characteristics. Materials and MethodsA total of 762,310 annual personal dose equivalents at a 10-mm reference depth (doses) during 1980–2020 for 43,823 participants of the U.S. Radiologic Technologists (USRT) cohort who responded to work history questionnaires administered during 2012–2014 were summarized. This population included 19,651 technologists who reported assisting with FGIP (≥1 time per month for ≥12 consecutive months) at any time during the study period. Doses corresponding to assistance with FGIP were estimated in terms of proximity to patients, monthly procedure frequency, and procedure type. Box plots and summary statistics (eg, medians and percentiles) were used to describe annual doses and dose trends. ResultsMedian annual dose corresponding to assistance with FGIP was 0.65 mSv (interquartile range [IQR], 0.60–1.40 mSv; 95th percentile, 6.80). Higher occupational doses with wider variability were associated with close proximity to patients during assistance with FGIP (median, 1.20 mSv [IQR, 0.60–4.18 mSv]; 95th percentile, 12.66), performing ≥20 FGIPs per month (median, 0.75 mSv [IQR, 0.60–2.40 mSv]; 95th percentile, 9.44), and assisting with high-dose FGIP (median, 0.70 mSv [IQR, 0.60–1.90 mSv]; 95th percentile, 8.30). ConclusionsOccupational doses corresponding to assistance with FGIP were generally low but varied with exposure frequency, procedure type, and proximity to patients. These results highlight the need for vigilant dose monitoring, radiation safety training, and proper protective equipment.

Assessment of occupational external radiation exposure of workers in the Southwest of Libya using portable NaI detector

In this study, gamma dose rates generated from the naturally occurring radioactive materials (NORM) were measured in the waste streams of a large scale and sludge onshore petroleum operations. Measurements conducted in this work involved: sludge recovery from separation tanks, sludge forming, NORM storage, scaling in oil tubulars, scaling in gas production and sedimentation in produced water evaporation ponds. Field work was carried out in many places of different terrain of an operation oil exploration and production in Murzuq basin in the Southwest of Libya. The radiation dose rates were measured using portable InSpector-1000. A total of 400 dose rates were acquired. The highest dose rate was 70 μSv/h acquired in sludge stored in barrels. The estimated mean annual equivalent doses in this field were in the range of 0.2–2.8 mSv/y in the first scenario, while in the second scenario the calculated mean annual equivalent doses were in the range of 0.04–0.68 mSv/y. It is assumed that workers may face various exposures in the field where measurements took place, considering the total annual effective dose to be 1.53 mSv/y. The main radioisotopes detected in these samples indicated by the display of the measuring device were 226Ra and 228Ra but detecting both radioisotopes in the same run is not achievable by using the display of the screen.

RADIOACTIVE CONTAMINATION OF WILD MUSHROOMS IN CHERNIHIV POLESIE

Purpose. We continue our retrospective investigations of radioactive contamination of wild mushrooms from Ukrainian Polesie. The aim of the current study is an assessment of radioactive contamination of wild mushrooms from some locations of Chernihiv Polesie in 1991-2021. Methodology. A study of radiocaesium activity in 66 wild mushroom species (edible, inedible, conditionally edible, poisonous) (from 2 to 25 fruitbodies per sample) and soils (0-5 cm of upper mineral layer, taken by the envelope method) from 14 locations of Chernihiv Polesie was carried out with γ-spectrometry (Ge-detector Canberra GLX 4019, USA). In some mushrooms, 90Sr activity was determined radiochemically on the basis of 90Y accumulation according to the standard method. Scientific novelty. The results of γ-spectrometric studies of the activity of radiocaesium in 66 species of wild mushrooms from the localities of Chernihiv Polesie over a 30-year period are given, the coefficients reflecting the bioaccumulation activity of each species counted, the hyperaccumulator species of radiocaesium are determined, and the potential annual equivalent doses for adults are calculated under the conditions of consumption of some valuable culinary-medicinal mushrooms (B. edulis, C. cibarius, I. badia, Suillus spp, T. equestre). Conclusions. Activity levels of 137Cs in wild mushrooms of Chernihiv Polesie varied over the years 1991-2021 depending on the mushroom species, its ecological affiliation, radioecological situation at the sampling sites, showing a certain tendency to decrease over time. Hyper-accumulative properties in relation to 137Cs are demonstrated by Cortinarius, Sarcodon, Paralepista, Tricholoma, Lactarius, Suillus spp. Widely distributed on the territory of Ukrainian Polesie - I. badia, P. involutus and L. rufus, remain representative bioindicators of radiocaesium contamination. A potential calculated annual effective doses due to the mushrooms consumption by adults, considering only the effect of the 137Cs, reached a high values in Suillus spp., T. equestre, and I. badia – 0.041, 0.035 and 0.025 mSv, respectively, which indicates a relatively insignificant dose load when consuming mushrooms in these localities compared to other localities of Ukrainian Polesie that have higher levels of soil contamination with radionuclides. However, radiation monitoring can still be recommended during mushroom procurement and mass collections.

Assessment of natural and anthropogenic radioactivity levels and their radiological hazards in surface soil samples around oil refinery, Little Aden City, Yemen

The activity concentration of global fallout of 137Cs and naturally- occurring radioactive materials (NORM), which primarily due to the geological and geographical condition of soil. and maybe occur from oil and gas burring processes and consequently accumulate on surface soil around the oil refinery in Aden Assoghra city, Yemen were studied by use the gamma-ray spectrometer equipped with a high purity germanium (HPGe) detector and specially designed shield. The average concentrations of 226Ra, 232Th, and 40K expressed in (Bq kg−1) of the studied samples were (13 ± 0.44) Bq kg−1, (22.1 ± 0.64) Bq kg−1 and (509 ± 9) Bq kg−1, respectively. Low concentrations of 137Cs were noted from some sample in the study area, where ranged from (0.3 ± 0.2) to (1.7 ± 0.2) Bq kg-1. The average values of calculated radiological hazard indices were 40.6 nGy h−1 (absorbed dose rate outdoors), 0.05 mSv y−1 (annual effective dose outdoors), 0.279 mSv y−1 (annual effective dose indoors), 83.7 Bq kg−1 (radium equivalent), 0.23 (external hazard index), 0.26 (internal hazard index), 0.65 (representative level index), 0.174×10-3 (the excess lifetime cancer risk ELCR) and 0.292mSv y−1 (annual gonadal equivalent dose, AGED).

Assessment of Radionuclide Concentrations in Oil Producing Communities in Bayelsa West Senatorial District, Bayelsa State, Nigeria

An assessment of radionuclide concentration in oil producing areas in Bayelsa West Senatorial District, Bayelsa State have been evaluated. In this study, a total of twenty five (25) soil, samples were collected for laboratory analysis. The survey was achieved using a factory calibrated Gamma Scout radiation meter and a Gamma Spectroscopy with Sodium Iodide (NA(TI) Detector used for counting and detection of radionuclide contentration of all samples. The results obtained in the study showed that the average concentrations for 40 K, 238 U and 232 Th in soil samples are valued at 520.888 ± 134.119 ???? ?1 , 18.495 ± 4.983 ???? ?1 and 11.463 ± 2.472 ???? ?1 respectively. The ?? ?? has an average value of 74.675 ± 16.934 ???? ?1 . The ? ?? has an average value of 0.21 ± 0.049 while the average value of ? ?? is 0.26 ± 0.064 which falls below the permissible level. The absorbed dose rate (D) due to 40 K, 238 U and 232 Th in soil samples has an average of 37.23 ± 8.692 ???? ?1 . This was also below the world average of 60???? ?1 . Annual effective dose equivalent (AEDE) has an average value of 45.66 ± 10.654 µ??? ?1 . This was also below the world average value. Annual Gonadal Equivalent Dose (AGED) and Representative Gamma Index (? ? ) were valued at 269.13 ± 63.095 ???? ?1 and 0.59 ± 0.117 respectively. Generally, the obtained value of 40 K was higher than the permissible level while 238 U and 232 Th where lower than the recommended standard value of 400 ???? ?1 , 33 ???? ?1 and 35 ???? ?1 (UNSCEAR, 2000). Therefore, the use of the soil for industrial and domestic poses no radiological threat to human health.

Measurement of natural ambient gamma radiation levels and estimation of population dose in tobacco-growing places of Karnataka state

Abstract Karnataka state is the fourth largest tobacco-growing state in India and Mysore district has large tobacco cultivation. The fertilizers contain the primary nutrients NPK (Nitrogen, Phosphorus and Potassium). This is also responsible for enhancing the gamma radiation level in rural areas of cultivated land of tobacco growing places, in addition to the natural gamma radiation. The aim and objectives of the present study consist of the measurement of the natural ambient gamma radiation dose level, and dose to the public. The natural ambient gamma radiation levels in some tobacco growing places of the Karnataka state were measured by a scintillation survey meter. The ambient gamma absorbed dose rate in cultivated and non-cultivated land varies from 34.8±0.3 nGyh-1 to 226.2±5 nGyh-1, with a mean value of 84.77±1.9 nGyh-1, and 26.1±0.3 nGyh-1 to 182.7±4 nGyh-1, with a mean value 58.82±1.2 nGyh-1 respectively. The indoor and outdoor gamma absorbed dose rate of the villages of the study area varies from 52.2±0.4 nGyh-1 to 234.9±4.5 nGyh-1, with a mean value of 100.89±2.3 nGyh-1, and 30.45±0.5 nGyh-1 to 165.3±3.5 nGyh-1, with a mean value of 63.19±1.3 nGyh-1 respectively. The annual effective equivalent dose rate of the study area varies from 0.293mSvy-1 to 1.344mSvy-1, with a mean value of 0.572mSvy-1. The indoor, tobacco leaves stored houses and the cultivated land shows higher gamma radiation dose rates than the outdoor atmosphere of the villages and non-cultivated land. The present study was able to establish a baseline data of Annual Effective Dose (AED) and assess gamma radiation dose rate of the study area. The results were presented and analyzed systematically from the radiation protection point of view.

Gamma-emitting radionuclides in therapeutic muds of the Euganean Thermal District (Padua, Italy)

Mud therapy is a therapeutic tool which uses natural materials available in the environment for healing purposes (clays and thermal water). The use of natural remedies increases the compliance to the cure, and their success is increasing in the last decades, all over the world. As natural matters, also muds have a wide range of composition, so, their use for healing requires appropriate knowledge.One of the most important world reference area for mud therapy has been accessed for sampling in different thermal centers (28) and also the exploiting site of raw clay has been studied. High resolution gamma spectrometry measurements have been acquired, compared with previous published data and discussed considering other compositional parameters.A clear increase of radionuclides of the 238U series characterize therapeutic muds respect to raw materials, 226Ra in particular. The scavenging of Ra from thermal waters is considered to occur after the precipitation of sulfate minerals (gypsum, barite) into the mud matrix, and several lines of evidence suggest that the repeated contact with thermal water (mud recycling) enhance the enrichment of Ra. A different scenario can be drawn for workers and for patients, as their contact with the mud is different for type and time. The dose arising from working in the area of therapeutic muds preparation and the dose to the skin of patients have been calculated.Even if Euganean therapeutic muds are richer in 226Ra respect to other similar materials, no radiological hazards emerged for workers who manage the preparation area, even in the most cautionary scenario. Also for patients, the contribution of Euganean mud therapy to the annual equivalent dose to skin is negligible, according to the cautionary elaboration done. Also considering literature data on the transcutaneous passage of chemical elements with geochemical affinity with Ra, no radiological hazard is detectable.

Evaluation of outdoor background ionizing radiation level around radiological sections in Federal Teaching Hospital Gombe, Gombe State Nigeria

This study presents the results of ambient radioactive radiation, radiation health hazard indices and excess lifetime cancer risk estimation around radiological sections in Federal Teaching Hospital Gombe, Gombe State, Nigeria using a well calibrated Rados-200 meters and a Global Positioning System (Garmin 765). The mean annual outdoor equivalent dose of 0.078 mSv/y. was measured. Mean annual outdoor effective doses of 0.1358 mSv/y. and 0.0950 mSv/y. were computed respectively, that were less than 1 mSv/y. maximum recommended limit for general public. The mean outdoor ELCR values of 0.3330 x10-3 was also estimated. The results though below the world’s average, are comparable with those of some other locations similar to the study area.

Evaluation of Lens Doses among Medical Staff Involved in Nuclear Medicine: Current Eye Radiation Exposure among Nuclear-Medicine Staff

The International Commission on Radiological Protection has lowered the annual equivalent eye-lens dose to 20 mSv. Although occupational exposure can be high in nuclear medicine (NM) departments, few studies have been conducted regarding eye-lens exposure among NM staff. This study aimed to estimate the annual lens doses of staff in an NM department and identify factors contributing to lens exposure. Four nurses and six radiographers performing positron emission tomography (PET) examinations and four radiographers performing radioisotope (RI) examinations (excluding PET) were recruited for this study. A lens dosimeter was attached near the left eye to measure the 3-mm-dose equivalent; a personal dosimeter was attached to the left side of the neck to measure the 1-cm- and 70-µm-dose equivalents. Measurements were acquired over six months, and the cumulative lens dose was doubled to derive the annual dose. Correlations between the lens and personal-dosimeter doses, between the lens dose and the numbers of procedures, and between the lens dose and the amounts of PET drugs (radiopharmaceuticals) injected were examined. Wilcoxon’s signed-rank test was used to compare lens and personal-dosimeter doses. The estimated annual doses were 0.93 ± 0.13 mSv for PET nurses, 0.71 ± 0.41 mSv for PET radiographers, and 1.10 ± 0.53 mSv for RI radiographers. For PET nurses, but not for PET or RI radiographers, there was a positive correlation between the numbers of procedures and lens doses and between amounts injected and lens doses. There was a significant difference between the lens and personal-dosimeter doses of PET nurses. The use of protective measures, such as shielding, should prevent NM staff from receiving lens doses &gt; 20 mSv/year. However, depending on the height of the protective shield, PET nurses may be unable to assess the lens dose accurately using personal dosimeters.

Assessment and evaluation of residents’ excess lifetime cancer risk of federal university of Kashere, Gombe State, Nigeria

A Study of indoor and outdoor radiation dose rate level measurements for male and female hostels at the Federal University of Kashere Hostels, Gombe State, Nigeria, has been carried out with the radiation alert smart 4 to ascertain the radiation level. The measured radiation dose rates were used to calculate the excess lifetime cancer risk and assess radiological health risks. The mean annual outdoor and indoor equivalent doses were 0.025 mSv/y. and 0.370 mSv/y. were recorded, with less than 1 mSv/y. maximum recommended limit for the general public. The mean annual outdoor and indoor effective doses were 0.017 mSv/y. and 0.086 mSv/y. respectively with a total of 0.103 mSv/yr. respectively. were computed. Mean outdoor and indoor ELCR values of 0.061X10-3and 0.302X10-3 respectively, with a mean total of 0.363X10-3 were also computed.

Problems of personnel irradiation in modern medical technologies

BACKGROUND: The widespread use of radiation sources in medical practice (cardio-endovascular surgery, endoscopy, traumatology, urology, neurosurgery, dentistry, and radioisotope diagnostics departments) leads to irradiation of the lens of the eye and the skin of the hands. The introduction of new recommendations by the IAEA to reduce the limit of the annual equivalent dose to the lens (20 mSv) has led to an inaccurate dose assessment based on the effective dose.&#x0D; AIM: To analyze approaches and assess equivalent doses of irradiation of the lens of the eye and skin of the hands of medical personnel during various diagnostic studies under the influence of X-rays and radiopharmaceuticals studies and to compare the results obtained with previously published data.&#x0D; MATERIALS AND METHODS: Thermo-luminescent dosimetry was used. Dose assessment was performed by cardio-endovascular surgery, endoscopy, isotope diagnostics, dentistry, and urology personnel.&#x0D; RESULTS: The estimated annual equivalent doses to the lens of the eye for doctors of cardio-endovascular surgery departments, in most cases, ranging 3590 mSv, 619 mSv for the average medical staff (in some cases, the doctor [225 mSv] and the nurse [180 mSv]) and 4.59 mSv for the staff of the department of radioisotope diagnostics. The annual calculated equivalent doses to the skin of the hands for cardio-endovascular surgery personnel were 17100 and 24220 mSv for the staff working with radiopharmaceuticals. It is shown that the use of an estimate of the average dose per operation by cardio-endovascular surgery doctors, as a rule, inevitably leads to an excess of the equivalent dose to the lens of the eye after a certain number of operations.&#x0D; CONCLUSION: When a certain number of operations are exceeded (100200), equivalent doses to the eyes lens in cardio-endovascular surgery doctors above 20 mSv per year can be formed. At current radiation levels, a lesion of the eyes lens was found in a cardio-endovascular surgery doctor. The results indicate the need for further dosimetric measurements and epidemiological studies, based on which recommendations for radiation protection of the eyes lens and the skin of the hands of medical personnel working in low-intensity, scattered, gamma X-ray radiation can be developed.