Effective Dose Equivalent Research Articles

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.

Radiological hazards of TENORM contaminated soil at Oil and Gas Fields

The presence of large quantities of TENORM contaminated soil produced during the extraction and processing of oil at oil extraction sites higher than the radiological reference levels assigned by the international organizations (UNSCEAR 2000) may cause the exposure of workers at this sites to unusual radiation hazards. This is a great importance for assessing the dose to the workers at these sites, which plays a vital rule in exploring the radiation health risks due to radiation exposure. This study aims to assess the TENORM activity concentration of the contaminated soil in some oil and gas production fields at Egypt. The assessment of the radiological hazards for the workers by estimating the annual doses and the radiation hazard indices are also studied. The obtained data showed that the activity concentration of 238U, 232Th and 40K found to be ranged from166 to 42567 Bq/Kg, 88 to 8358 Bq/Kg and 52.22 to 440Bq/Kg respectively. The calculated absorbed dose rate ranged from 132.39 – 24732.67 nGy/h, the calculated Annual Effective Dose Equivalent ranged from0.16 – 30.33 mSv/y (depending on the activity concentration of NORM contamination). The radiation hazard indices is calculated and found to be much higher than the international values. From the obtained results, it has concluded that the remediation/decontamination of the contaminated soils at the production sites that have high activity concentration is highly recommended. In addition, Egyptian regulations must be coherent to force companies to decontaminate the NORM contamination in order to reduce as much as possible the radiation worker exposure.

Distribution of natural radionuclides and assessment of excess lifetime cancer risk along coastal areas of Varkala in Kerala

Some of the coastal parts of Kerala are well reported high background radiation areas (HBRA). Hence, the radiological protection of the population in this region is of great concern. In view of this, study has been undertaken to understand the distribution and enrichment of radionuclides concentration in sand samples from Varkala region, a known HBRA. The NaI(Tl) detector was used for the measurement of radionuclides concentration in sand samples. The values obtained from the present study indicate that, the activities in sand samples were high compared with the world average values. The radiological parameters viz. absorbed dose, annual effective dose and annual gonadal dose equivalent were also calculated. Further, the excess lifetime cancer risk (ELCR) due to the exposure of radiation prevailing in the region was estimated from the activities of radionuclides. The ELCR value obtained from the present study was much higher than the world average value for all the samples. The results from the present investigation clearly indicate that, the radioactivity prevailing in the region is adversely affecting the inhabitants of the region. The results of these systematic investigations are presented and discussed in the manuscript.

РАДИОЭКОЛОГИЧЕСКАЯ ОПАСНОСТЬ ДЛЯ НАСЕЛЕНИЯ В РАЙОНАХ РАСПРОСТРАНЕНИЯ ВЫСОКОРАДИОАКТИВНЫХ ГРАНИТОВ

Актуальность исследования обусловлена необходимостью объяснения высокой заболеваемости населения в районах распространения радиоактивных пород и почв. Исследование выполнено в рамках нового научного направления – медицинской геологии. Целью работы является изучение масштабов радоновыделений в районах выхода на поверхность высокорадиоактивных гранитов, оценка их радиоэкологической опасности и медико-биологических последствий. Объекты: геохимический и минералогический состав образцов гранитов, кор выветривания и почв, масштабы радоновыделений и частота заболеваемости в различных областях мира (г. Чжухай в китайской провинции Гуандун; г. Эшасьер во французском регионе Овернь) и Сибирского региона (г. Белокуриха Алтайского края; пгт. Колывань Новосибирской области). Методы. В рамках исследования применялся широкий комплекс методов, включающий инструментальный нейтронно-активационный, рентгенофазовый анализы, гамма-спектрометрию, осколочную радиографию, электронную микроскопию, экспрессное измерение объёмной активности радона, расчет потока плотности радона, эквивалентной эффективной дозы и частоты вновь выявленных заболеваний (incidence). Результаты. Проведено обобщение данных по воздействию ионизирующего излучения на организм человека. По результатам геохимических, минералогических, радиоэкологических и медико- статистических исследований выявлено, что в процессах коро- и почвообразования радионуклиды высвобождаются из структурных решеток акцессорных минералов и сорбируются на глинистых минералах. Данный процесс способствует повышению радоновыделений и радиационного фона. Дано объяснение возможных связей повышенных концентраций радионуклидов в подстилающих породах, почвах и высокой активности газа радона с показателями заболеваемости населения. При сопоставлении первичных показателей онкозаболеваемости у всех групп населения с общероссийскими и мировыми показателями отмечаются превышения уровня во всех исследуемых районах. К территориям «риска» по частоте заболеваемости раком легкого можно отнести Белокуриху в Алтайском крае и Колывань в Новосибирской области; раком носоглотки – провинцию Гуандун; раком кроветворной ткани – Колывань; анемиями – Гуандун; по врожденным порокам развития – Гуандун и Колывань.

Integrating radon and thoron flux data with gamma radiation mapping in radon-prone areas. The case of volcanic outcrops in a highly-urbanized city (Roma, Italy)

An integration of laboratory radon and thoron exhalation data with gamma radiation mapping is applied to assess the geogenic radon and the exposure of people to natural radiation in a highly-urbanized city (Roma, Italy). The study area is a protected territory where ignimbrites from Colli Albani volcano and alluvial sediments largely crop out. A map of total gamma radiation, a gamma transect across Caffarella valley and 9 vertical gamma profiles have been carried out, showing that the main control of gamma levels is, of course, the lithological nature, without neglecting the simultaneous effect of other parameters such as slope morphology, erosion/weathering processes, occurrence of sinkholes or underground tunnels. The surveys allowed to distinguish the medians of ignimbrites (from 816 ± 16 cps to 936 ± 19 cps) from that of alluvial materials (611 ± 14) cps), but showed also that alluvial sediments with anomalously high radioactivity (769 ± 14 cps) can be locally recognized, providing valuable information on the interaction between sedimentation and erosion in fluvial valleys. Total gamma activity was converted into absorbed gamma dose rate ranging from 0.33 to 0.38 μSv/hr. Outdoor Annual Effective Dose Equivalents were also estimated between 0.58 and 0.67 mSv y−1.Laboratory radon and thoron exhalation rates of collected material are positively correlated with gamma radiation. Volcanic and alluvial sediments are well-discriminated. The correlation between the two variables is evident, but not robust because of the variable concentration of 40 K, which is not contributing to radon and thoron exhalation rates. Anomalous data of soil samples located at the foot of a slope can be interpreted as due to reworking and accumulation processes. Similar gamma radiation data documents analogous concentration of radon and thoron parent-nuclides, but coexisting different radon and thoron exhalation rates provides an additional information on different grain size distributions which can be considered as a proxy for soil gas permeability.The integration of gamma mapping and radon and thoron exhalation measurements is a very useful tool to assess people exposure to natural radiation, in terms of dose rates and potential indoor radon. Gamma mapping, which provides data on the radiation source (the bedrock) is fast and not expensive. It allows to obtain very detailed pictures of a study area, but it needs to be combined with laboratory determination of radon and thoron release in order to definitely and correctly interpret variations of gamma signal. Furthermore, laboratory determination of soil radon exhalation gives information on the release of radon and is a good proxy for soil gas permeability. It has the great advantage over in-situ measurements of gas flow not to be influenced by seasonal pedoclimatic parameters and is affected by lower analytical uncertainties. These data are thus reproducible and precise and can be used to estimate potential radon hazard, which is the main source of exposure and thus the most important parameter for human protection from environmental radioactivity.

Internal radiation dose assessment of radiopharmaceuticals prepared with cyclotron-produced 99m Tc.

Technetium-99m (99m Tc) is the radioisotope most widely used in diagnostic nuclear medicine. It is readily available from 99 Mo/99m Tc generators as the β- decay product of the 99 Mo (T½ =66h) parent nuclide. This latter is obtained as a fission product in nuclear reactors by neutron-induced reactions on highly enriched uranium. Alternative production routes, such as direct reactions using proton beams on specific target materials [100 Mo(p,2n)99m Tc], have the potential to be both reliable and relatively cost-effective. However, results showed that the 99m Tc extracted from proton-bombarded 100 Mo-enriched targets contains small quantities of several Tc radioisotopes (93m Tc, 93 Tc, 94 Tc, 94m Tc, 95 Tc, 95m Tc, 96 Tc, and 97m Tc). The aim of this work was to estimate the dose increase (DI) due to the contribution of Tc radioisotopes generated as impurities, after the intravenous injection of four radiopharmaceuticals prepared with cyclotron-produced 99m Tc (CP-99m Tc) using 99.05% 100 Mo-enriched metallic targets. Four 99m Tc radiopharmaceuticals (pertechnetate, sestamibi (MIBI), hexamethylpropylene-amine oxime (HMPAO) and disodium etidronate (HEDP)) were considered in this study. The biokinetic models reported by the International Commission on Radiological Protection (ICRP) for each radiopharmaceutical were used to define the main source organs and to calculate the number of disintegrations per MBq that occurred in each source organ (Nsource ) for each Tc radioisotope present in the CP-99m Tc solution. Then, target organ equivalent doses and effective dose were calculated for each Tc radioisotope with the OLINDA/EXM software versions 1.1 and 2.0, using the calculated Nsource values and the adult male phantom as program inputs. Total effective dose produced by all Tc isotopes impurities present in the CP-99m Tc solution was calculated using the fraction of total activity corresponding to each radioisotope and compared with the effective dose delivered by the generator-produced 99m Tc. In all cases, the total effective DI of CP-99m Tc radiopharmaceuticals calculated with either versions of the OLINDA software was less than 10% from 6 up to 12h after EOB. 94m Tc and 93m Tc are the Tc radioisotopes with the highest concentration in the CP-99m Tc solution at EOB. However, their contribution to DI 6h after EOB is minimal, due to their short half-lives. The radioisotopes with the largest contribution to the effective DI are 96 Tc, followed by 95 Tc and 94 Tc. This is due to the types of their emissions and relatively long half-lives, although their concentration in the CP-99m Tc solution is five times lower than that of 94m Tc and 93m Tc at the EOB. The increase in the radiation dose caused by other Tc radioisotopes contained in CP-99m Tc produced as described here is quite low. Even though the concentrations of the 94 Tc and 95 Tc radioisotopes in the CP-99m Tc solution exceed the limits established by the European Pharmacopoeia, CP-99m Tc radiopharmaceuticals could be used in routine nuclear medicine diagnostic studies if administered from 6 to 12h after the EOB, thus maintaining the effective DI within the 10% limit.

Risks assessment for the retrieval of radioactive waste from the old Russian cemetery Al -Tuwaitha site

In this work the radioactive wastes in the Old RussianCemetery Al -Tuwaitha site were classified according to risks forworkers who are involved in the retrieval process. The exposureassessment results expressed as estimates of radionuclide intakes byinhalation and ingestion, exposure rates and duration for externalexposure pathways, and committed effective dose equivalents toindividuals from all relevant radionuclides and pathways. Resultsshowed the presence of natural radionuclides Ra-226, Th-234 and K-40, as well as the produced radionuclide Cs-137 and Eu-152 in thecemetery wells. The absorbed doses from the waste were classified totwo categories; exempt waste and low level waste according toabsorbed dose value. This studied site does not pose a radiologicalhazard for the workers.

Assessment of Equivalent Radium Activity and Annual Effective Dose Due to Building Materials in Côte D’Ivoire by Gamma Spectrometry: Cases of Cement

Radioactivity is a natural phenomenon present in the universe. So, because of human life solidarity with a habitat, we are permanently in contact, especially through building materials. The objective of this work is the determination of the used cement radioactivity level in the buildings in Cote d'Ivoire. Thus, samples of grey and white cement currently used on Ivorian territory were taken. In order to determine the radioactivity level of this cement, samples were analyzed by using gamma spectrometry chain which contains a NaI (Tl) scintillation detector designed by the German manufacturer LD-DIDACTIC, coupled to a multichannel analyzer (AMC) using a Cassy Lab software. Thus, the specific activity of the primordial radionuclides 226Ra, 232Th and 40K, was able to be determined. The average values obtained are 29.66 Bq/kg, 34.88 Bq/kg and 178.424 Bq/kg respectively for 226Ra, 232Th and 40K. All average values are below the limit values recommended by UNSCEAR. However, we evaluated the radiological parameters such as the equivalent radium activity and the annual effective dose in order to translate the specific activity in terms of harmfulness. Values obtained for these parameters are below those recommended by ICRP and UNSCEAR. These results show that the risk incurred by the use of these different brands of cement is low.

Radiological consequences assessment of a hypothetical accident during transportation of spent nuclear fuel

During the transportation of spent nuclear fuels, the potential release of the radioactive materials into the atmosphere in the case of an accident becomes a serious threat to public health and the environment. In China, a commercial reprocessing plant is planned to be commissioned around 2025 based on the China nuclear roadmap. After being cooled on site the spent nuclear fuels are transported to the reprocessing plant by train or truck. This requires the assessment of radiological consequences of such accidents during transportation, therefore dose calculations under hypothetical accident conditions have been presented in this paper. The total effective dose equivalent and ground deposition are calculated using the HotSpot health physics computer code with site-specific meteorological conditions. The results indicate that the total effective dose equivalent and ground deposition are both decreased with the increase of the downwind distance. The maximum of the total effective dose equivalent is about 1.4?101 Sv, which is larger than the regulation limit for the public. The TEDE counter plot shows that the inner regions marked with dose contours of 1.0?10?3 Sv are higher than the regulation limits for the public, however this needs no intervention but any unnecessary trip to this area should be avoided.

Measurement of radon (222Rn) and thoron (220Rn) concentration of plants (Vegetables) in different locations in Sulaimania City using CR-39 detector

Introduction: Radon is a radioactive gas released from the normaldecay of uranium in rocks and soil depending on local geology. Radioactive decay of uranium through radium produces radon. Materials and Methods: In the present work, seventeen plant (vegetables) samples collected from Sulaimania Governorate. The plants have been analyzed and examined to measure the level of radon (222Rn) and thoron (220Rn) using plastic track detector (CR-39) for evaluation of radon and thoron concentration in this region. Results and Discussion: The results indicated that the higher andlower radon concentration have been found in Halabjay-con, and inSulaimani-center, to be (119.72 Bq.m-3, 3.236 pCi/L), (54.36 Bq.m-3,1.469 pCi/L), respectively, and the higher and lower thoron concentration have been found in Qaladza and in Sulaimani-center, to be (733.66 Bq.m-3, 19.828 pCi/L), (227.33 Bq.m-3, 9.117 pCi/L), respectively. Radiation level compared with the standard level known by the EPA (4 pCi/L) and190 Bqm-3. The concentration of radon in all sample plants is less than international standard level 4(pCi/L)and190 (Bqm-3), therefore the human in safety. The average effective dose equivalent (EDE) of radon from plants determined was (7.2) μSv.y-1 for all the samples. This is lower than the normal value of (1.3) mSv.y-1 given by EPA. Conclusions: This study showed that the contamination in the plant (vegetables) is normal and is not considered a great radial dose for plants and consequently for humans.

Estimation of Natural Radionuclides and Exhalation Rate in Surface Soils of Four Districts of Haryana, India

A comprehensive study is conducted to determine the elemental concentrations of 238U, 232Th and 40K in surface soil samples collected from four well-populated districts of central part of Haryana, India. NaI(Tl) gamma ray spectrometer is used for measurement of 238U, 232Th and 40K in soil samples and SMART RnDuo is used for estimation of exhalation rate in soil samples. Average values of activity concentrations of 238U, 232Th and 40K are 27.9 ± 6.0 Bqkg-1, 34.0 ± 6.6 Bqkg-1 and 306.9 ± 15.9 Bqkg-1, respectively. Radium equivalent activity is lower than the recommended limits with an average value of 97.98 Bqkg-1. Absorbed dose rates in air outdoors, effective dose rates for indoor and outdoor, internal and external hazard index, radium equivalent activities and annual effective dose are measured in soil sample of the study area. A weak positive correlation is observed between radionuclides and exhalation rate.

Determination of Indoor Radon Concentration and Effective Dose Equivalent at Workplaces of Afyonkarahisar Province

It is commonly known that people are exposed to radon and its progenies since they spend about 35% of daytime at workplaces. This exposure has been reported to be more than 50% of the natural radiation. Therefore, determination of indoor radon concentration has been widely conducted by the scientists. This work presents indoor radon measurements and the associated annual dose equivalentsobtained in 28 public buildings of the Afyonkarahisar province. The survey was conducted using passive nuclear track detectors and repeated quarterly during a year.The investigation focused on the seasonal and regional effects in indoor radon concentration anomalies. The measured values ranged from 13 Bq.m-3to 1932 Bq.m-3, whereas the calculated average values were in the range of 21,75 Bq.m-3and 1032,50Bq.m-3. Moreover, the mean indoor radon concentration and the corresponding annual dose equivalent valueswere obtained as 158,83±13,16Bq.m-3and 1,25±0,10mSv.y-1, respectively.

Thrombolytic and Anticoagulant Therapy for Pulmonary Embolism with High and Intermendiate Risk of Early Death. Part 3. An Effect on Pulmonary Perfusion with High and Intermediate Risk of Early Death

Background The advantage of thrombolytic therapy (TLT) over anticoagulant therapy(ACT) in patients with a high risk of early death (hemodynamic disorders) in acute pulmonary embolism is considered proven. But the advantage of thrombolytic therapy over anticoagulant therapy remains uncertain in patients with an intermediate risk. Perfusion lung scintigraphy helps provide a quantitative comparison of changes in pulmonary blood flow with the use of different treatment methods in subgroups of high and intermediate risk of an adverse outcome.The aim of study is to compare the effectiveness of thrombolytic and anticoagulant therapy in the treatment of acute pulmonary embolism in patients with a high and intermediate risk of early death in terms of the dynamics of pulmonary perfusion disorders.Study design: a prospective non-randomized study. The introduction of a thrombolytic was cosidered as intervention. The comparison group consisted of patients who received an anticoagulant. Thrombolysis in patients with intermediate risk was indicated in the absence of a potential threat of hemorrhagic complications, a deficit of pulmonary perfusion above 40%, a high level of pulmonary hypertension and a high probability of cardiac decompensation. The method of comparison was the quantitative result of pulmonary perfusion deficiency.Description of the method Radionuclide and CT studies were carried out using a hybrid system SPECT/CT Discovery NM/CT 670 (GE, USA): the perfusion was evaluated with 80–120 MBq of 99mTc macrotech radiopharmaceutical (RP) (effective equivalent dose of 0.8–1.3 mSv), CT angiography was performed with 70–100 ml of radiopaque substance Visipaque (effective equivalent dose of irradiation 9.4–10.3 mSv). The accumulation deficit of an area equal to a segment was counted as a perfusion deficiency of 5% (subsegmental 2.5%), inferior lobe — 25%, an area equal to the right lung — 55%, the left lung — 45%.Characteristics of the sample In a sample of 503 patients who received treatment at the Intensive Care Unit for Surgical Patients of the N.V. Sklifosovsky Institute for Emergency Medicine from 2011 to 2016, the overall mortality rate was 14.7% (95% CI 11.7; 18.1) (74/503); anticoagulation therapy — 17.8% (95% CI 13.5; 22.8) (50/281); thrombolytic therapy — 10.8% (95% CI 7.1; 15.6) (24/222); p=0.031, Fisher’s test, P=0.60. At a high risk of death, the mortality rate in the thrombolytic therapy group was 30.2% (19/63) versus 47.1% (32/68) in the anticoagulant therapy group; p=0.051, the Fisher’s test; P=0.51. At an intermediate risk, it was 3.2% (5/158) and 8.4% (8/214); p=0.049, the Fisher’s test, P=0.54. Changes in pulmonary perfusion deficiency as a result of treatment were performed in 169 patients who promptly underwent a primary and repeated dynamic scintigraphic study: 127 patients after thrombolysis (of which 38 patients had a high risk and 88 had an intermediate risk) and 42 patients who were treated with an anticoagulant (5 — high risk, 37 — intermediate risk). The groups did not differ in age and gender composition: the mean age was 59±16; Me 61 (49; 71) and 57±14 years; Me 58 (43; 67), respectively; p=0.50 (Mann–Whitney test); men/women: 50/77 and 12/30; p=0.27, the Fisher’s test. The groups differed in the presence of cancer: in the ACT group, the proportion of patients with cancer was 21.4% (9/42), and in the TLT group it was 4.7% (6/127), p=0.003, the Fisher’s test, P=0.85.Results Patients of high and intermediate risk, who received thrombolysis, were in a significantly more serious condition in terms of baseline characteristics. Both methods of treatment were effective. In high-risk patients, perfusion deficiency regressed: from 57±10% (Me 60 (50; 65)) to 31±15% (Me 30 (20; 40)), p<0.00001 (Wilcoxon test), Es=2.08, P=1.00 after TLT; from 38±9% (Me 40 (35; 40)) to 14±8% (Me 10 (10; 20)), p=0.043 (Wilcoxon test), Es=2.72, P=0.93 after ACT. In patients with intermediate risk, perfusion deficiency regressed: from 48±9% (Me 50 (40, 55)) to 24±13% (Me 20 (15; 30)), p<0.00001 (Wilcoxon test) after TLT; from 38±11% (Me 40 (30; 45)) to 24±15% (Me 15 (15; 30)), p=0.00003 (Wilcoxon test) after ACT. The effect size for TLT was Es=2.16, for ACT Es=1.13. The power of the study was P=1.00 and P=0.99.Conclusion Thrombolytic therapy was more effective in restoring pulmonary perfusion compared to anticoagulants in patients with an intermediate risk of early death: the effect of thrombolysis was greater than that of anticoagulant therapy (Es=2.16 and Es=1.13). The absence of the effect of restoring pulmonary perfusion during thrombolysis was noted less frequently compared to the results of anticoagulant therapy: in 5.5% (95% CI 2.2–11.0) vs. 19.0% (95% CI 8.6–34.1).

Biodistribution and Internal Radiation Dosimetry of 99mTc-IDA-D-[c(RGDfK)]2 (BIK-505), a Novel SPECT Radiotracer for the Imaging of Integrin αvβ3 Expression.

Background: Integrin αvβ3 is a molecular marker for the estimation of tumor angiogenesis. 99mTc-IDA-D-[c(RGDfK)]2 (also known as BIK-505) is a recently developed radiotracer for single-photon emission computed tomography, with good affinity for integrin αvβ3. In this study, the authors investigated the whole-body distribution and internal radiation dosimetry of 99mTc-IDA-D-[c(RGDfK)]2 in elderly human participants.Materials and Methods: Six healthy volunteers underwent whole-body simultaneous anterior and posterior scans, preceded by transmission scans using cobalt-57 flood source, with a dual head gamma camera system, at 0, 1, 2, 4, 8, and 24 h postinjection of 99mTc-IDA-D-[c(RGDfK)]2 (injected radioactivity [mean ± SD] = 388.7 ± 29.3 MBq). Anterior and posterior images were geometrically averaged and attenuation corrected to delineate the regions of interest in the liver, gallbladder, kidneys, urinary bladder, spleen, brain, and large intestine. Radiation dose for each organ and the effective doses (EDs) were estimated using OLINDA/EXM 1.1 software.Results: High radiation doses of renal and biliary excretion tracks such as the urinary bladder wall, upper large intestine, kidneys, liver, and gallbladder wall (19.15 ± 6.84, 19.28 ± 4.78, 15.67 ± 0.90, 9.13 ± 1.71, and 9.09 ± 2.03 μGy/MBq, respectively) were observed. The ED and effective dose equivalent were 5.08 ± 0.53 and 7.11 ± 0.58 μSv/MBq, respectively.Conclusions: Dosimetry results were comparable to other radiolabeled peptides and were considered safe and efficient for clinical usage.

Radiometric and Radiogenic Heat Evaluation of Natural Radioactivity in Soil Around Solid Minerals Mining Environment in South-Eastern Nigeria

Radionuclides activity concentrations in soil around ten solid mineral mining sites have been investigated using sodium iodide [Na(TI)] gamma spectroscopy. Four soil samples and a control sample were collected from each of the selected sites for analyses. The obtained results showed mean concentration values of 33.2 Bq kg−1 for 226Ra, 100.7 Bq kg−1 for 40K and 77.7 Bq kg−1 for 232Th. The estimated radiological risk parameter results have shown average values of 67.5 ηGy h−1 for the Absorbed Dose Rate (DR), 82.8 μSv y−1 for the Annual Effective Dose Equivalent (AEDE), 151.4 Bq kg−1 for the Radium Equivalent (Raeq) and 457.1 mSv y−1 for the Annual Gonadal Equivalent Dose (AGED) which is highly comparable to the allowable WHO value of 300 mSv y−1 and the control value of 177.7 mSv y−1. The average Excess Life Cancer Risk (ELCR) value obtained was 289.6 × 10−6 and the control value 112.9 × 10−6. The average External Hazard Index (Hex), Internal Hazard Index (Hin), Representative Gamma index ( Iγ), and Activity Utilization Index (AUI) obtained were 0.4, 0.5, 1.1 and 1.3, respectively. The Radiogenic Heat produced Q ranged from 248.4 pW kg−1 in Awkuke (ironstone mine) to 608.5 pW kg−1 in Ama-Echi (Silica mine) with an average heat value of 415.8 pW kg−1. The obtained result for lithology [clay] identification showed a mixed clay lithology type. The overall results were found to be higher when compared to previously reported values from similar mineral mining areas, which indicates radiological contamination.

Assessment of the Specific Activity of Alpha- and Beta-emitting Radionuclides in Groundwater, Anka, Nigeria

Introduction: After the lead poisoning outbreak came to light in Zamfara State, Nigeria, people living near gold mines were worried about environmental safety, especially drinking water quality. This study examined the gross alpha and gross beta activity concentrations in groundwater in different locations of Anka, Zamfara State, Nigeria, to measure the possible radiation dose and potential health effects. Material and Methods: In this study, 32 water samples were collected from hand dug wells and boreholes in Anka, Nigeria, through stratified random sampling method. The ISO 9696 and ISO 9697 methods were adapted using Eurysis system-multiple-channel-gas-filled proportional counter to measure gross alpha and gross beta activity concentration. Results: The ranges of alpha and beta activity concentration in groundwater of the area were 0.114 to 3.698 Bq/l and 0.071 to 4.823 Bq/l with the geometric means of 0.961 Bq/l and 2.134 Bq/l, respectively. These amounts were higher than the reference limits of 0.5 Bq/l and 1 Bq/l for gross alpha and beta activity concentrations, respectively. Additionally, the total annual effective dose equivalent was more than that (0.1 mSv/y) of recommended by World Health Organization (WHO). Conclusion: The mean concentrations of alpha and beta activities in the samples were above the limits recommended by WHO. These excessive radiations might negatively affect the environment and inhabitants.

Assessment of Annual Effective Dose Equivalent and Excess Lifetime Cancer Risk Due to Radionuclide Present in Water obtained from Oloru, Kwara State, Nigeria

Assessment of Annual Effective Dose Equivalent and Excess Lifetime Cancer Risk Due to Radionuclide Present in Water obtained from Oloru, Kwara State, Nigeria

Estimation of radiation-induced cataract and cancer risks during routine CT head procedures

Eye lenses lie within the radiation field during computed tomography (CT) procedures of the brain. Therefore, patients are at risk of forming eye lens opacity when exposures exceed the threshold for such onset. The purpose of this study was to estimate the eye lens equivalent and radiation effective doses during CT procedures of the brain, facial bones, and paranasal sinuses. A total of 85 patients were examined using a 16-detector CT machine. The organ and surface dose received by specific radiosensitive organs was carried out using software from the National Radiological Protection Board (NRPB). The overall mean patient doses were as follows: CTDIvol, 45.7 ± 15.6 mGy for brain; and 7.6 mSv for the eye lens. The mean eye lens equivalent dose per CT procedure was 11.5 mSv, 4.5 mSv, and 6.7 mSv for the brain, paranasal sinuses, and facial bones, respectively. The radiation risk per procedure equates to 1 cancer case per 11 × 10−3 procedures. The study shows there to be great need for improving the imaging protocol and for continuous training of staff. Dose reduction techniques in brain CT are required, eye lens irradiations potentially generating lens opacities.

Outdoor radioactivity and health risk assessment for capital city Ankara, Turkey

The aim of this study is to determine the soil radioactivity levels and assess the possible relevant health hazards for the inhabitants of Ankara province. Total of 341 samples were collected from predetermined locations and outdoor gamma dose rate measurements were carried out. The mean activity of 40K, 226Ra, 232Th, and 137Cs with the ranges were determined as 454 (23–1355), 27 (6–186), 33 (2–181) and 3.3 (0.5–20.9) Bq kg−1, respectively. The average annual effective dose equivalent was found to be 71.8 µSv y−1 for public exposure and the average excess lifetime cancer risk value was calculated as 2.69E−04.

Natural Radioactivity Levels in Soil Samples of AL- Sadr and AL-Forat AL-Aosat Hospitals in Najaf

This work was undertaken with the purpose of measuring natural radioactivity, due to 238U, 232Th and 40K in 30 soil samples collected from two hospitals in the governorate of (AL-Najaf), in Iraq. The samples were distributed (15) samples per hospital, and Radiation risks were also calculated for all soil samples. The natural radioactivity was measured using NaI (Tl) detector, the results of the specific activity at the Al Sadr Hospital were 238U ranged from (5.89±0.36 to 21.38±0.69) (Bq/kg) with average value 12.60±0.51 (Bq/kg). 232Th from (0.44±0.06 to 14.67±0.37) (Bq/kg) with average value (4.46±0.19) (Bq/kg), and 40K from (252.14±2.54 to 478.24±3.50) (Bq/kg) with average value (346.95±289) (Bq/kg). AL-Forat AL-Aosat hospital results were 238U ranged from (0.69±0.12 to 27.63±0.74) (Bq/kg) with average value (12.84±0.51) (Bq/kg), 232Th from (1.47±0.11 to 9.3±0.31 (Bq/kg) with average value 6.19±0.24 (Bq/kg), and 40K from (192.88±2.27 to 338.52±3.08) (Bq/kg) with average value (254.29±2.54) (Bq/kg). The radiation risks calculated, Radium Equivalent (Raeq), external Hazard index (Hex), absorbed dose rate (ADr), total Annual Effective Dose Equivalent (AEDE), and the Excess Life Cancer Risk (ELCR). The results were for Al Sadr Hospital (45.7063(Bq/kg), 0.1234, 23.0648(nGy/h), 0.0283(mSV/y), 1.247439702×10-3) respectively. For AL-Forat AL-Aosat hospital were (41.2655 (Bq/kg), 0.111, 20.3772 (nGy/h), 0.0250(mSV/y)`, 1.102083688×10-3) respectively. The results in the two hospitals were compared with the global allowable values ratio within the permissible ranges specified by UNSCER, OCDE, and ICRP; we concluded that all the sites in this study are safe.