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This work presents a study of radioactivity in soil samples from oil well sites of Baba Gurgur dome of Kirkuk oil field using a high-purity germanium (HPGe) detector and spectroscopy system. The activity concentration (Bq kg−1) of 226Ra, 232Th, 40K and 137Cs varied between 26.4–98, 10.8–55.2, 239–729, and 2.40–7.20, respectively. The results have been compared with the average worldwide values. The hazard indices have also been calculated. The radium equivalent activity (Raeq) was 131.04 Bq kg−1, the absorbed gamma dose rate (D) was 62.04 nGy h−1, the annual effective dose rate (AEDE) outdoor and indoor were 0.08 mSv y−1 and 0.30 mSv y−1, respectively, the external hazard (Hex) was 0.35, the internal hazard (Hin) was 0.51, the Gamma radiation representative level Index (Iγ) was 0.96, and excess lifetime cancer risk was 0.30 × 10−3. Our results of some sites were found to be higher than the allowable worldwide values. Statistical data including: Mean, Median, Std. Deviation, kurtosis, skewness, box plot, frequency distribution, Quantile-quantile (Q-Q) plots, Pearson's correlation coefficient analysis, principal component analysis (PCA), and cluster analysis were calculated and carried out to explain our results. [ABSTRACT FROM AUTHOR]

Multiple building constructions necessitating a regular influx of different soils for building purposes within Federal College of Education (Technical) Akoka, in Lagos State, Nigeria spurred a radiological risk assessment of selected soil samples. Five (5) construction points were identified and ten (10) soil samples were collected. A gamma spectrometer was used to evaluate the natural radionuclides (226Ra, 232Th, and 40K) present in the soils. IAEA-certified standard materials of RGU-1, RGTh-1, and RGK-1 were used to determine the full peak efficiencies of gamma energies 609, 1120, and 1764 keV for 238U, 2614 keV for 232Th and 1460 keV for 40K. Activity concentration, absorbed dose, annual effective dose equivalent, hazard indices, and excess lifetime cancer risk (ELCR) were estimated to assess possible radiological risks in the building soil samples. Results from the analysis revealed the highest radioactivity among soil samples was 674.3 Bq/kg from 40K and the lowest was 18.5 Bq/kg from 226Ra. The absorbed dose (D) varies from 65.8 nGy/h to 215.3 nGy/h with an average value of 136.6 nGy/h, and the annual effective dose equivalent ranged from 0.081 mSv/y to 0.264 mSv/y with an average value 0.168 mSv/y. The internal and external hazard index ranged from 0.49 −1.46 and 0.39 − 1.32 respectively which is not completely below the hazard index threshold value ≤1 as recommended by UNSCEAR. The ELCR values ranging from 0.222 × 10-3 − 0.726 × 10- 3 with an average value of 0.461 × 10-3 predicted an insignificant carcinogenic risk with the probability of four persons in every 10,000 persons.

This study was undertaken to determine natural radioactivity and potential radiological hazards associated with cement. A NaI (Tl) gamma-ray spectrometer run with gamma vision software was used to analyze the samples. The average value of activity concentrations of 226Ra, 232Th, and 40K were 22.9 ± 7.7, 27.3 ± 8.3, and 336.5 ± 44.9 Bq/kg respectively. These values are well below the global average value for building materials. All the radiological hazard parameters are also lower than the recommended value for safe use. From a radiological point of view, they are therefore suitable for use as building materials. [ABSTRACT FROM AUTHOR]

Recent years have seen increased attention given to radon from two scientific directions. After neglecting radon as an earthquake precursor in the 1990s, it has become the subject of discussions in earthquake-forecast papers due to growing networks of radon monitoring in different countries, particularly the technologies of real-time radon measurements where gamma spectrometers are of great interest as sources of 222Rn identification. The second fast-developing direction involves radon in Lithosphere–Atmosphere–Ionosphere Coupling (LAIC) models as a source of boundary layer ionization. Here we address the second topic, which is not connected with the earthquake forecast problems, namely, the role of air ionization by radon as a source of the Global Electric Circuit (GEC) modification. In this publication, we try to unite all of these problems to present a more complex view of radon as an important element in our environment. Special attention is paid to the dependence of radon variability on environmental conditions. [ABSTRACT FROM AUTHOR]

This study assessed the concentration of radionuclides (Ra-266, Th-232, U-238, and K-40) in selected dumpsites within some Local Government Areas of Kaduna State. Radiological analysis was carried out using a gamma spectrometer (HPGE) located at the Energy Research Center, University of Ibadan, Nigeria. The results of the concentration of Ra-266, Th-232, U-238 and K-40 in the study area were as follows: 196.12 - 239.14 Bq/kg, 126.79 - 171.32 Bq/kg, 84.96 - 115.96 Bq/kg, and 317.11 - 521.77 Bq/kg respectively for Chikun LGA; 213.84 - 268.98 Bq/kg, 102.17 - 122.90 Bq/kg, 110.89 - 137.80 Bq/kg, 407.64 - 486.38 Bq/kg respectively for Igabi LGA; 187.15 - 364.50 Bq/kg, 166.04 - 387.00 Bq/kg, 97.35 - 180.57 Bq/kg, and 541.72 - 801.08 Bq/kg respectively for Kaduna North LGA; and 128.98 - 293.45 Bq/kg, 139.43 - 182.96 Bq/kg, 70.57 - 132.02 Bq/kg and 526.19 - 707.42 Bq/kg respectively for dumpsites in Kaduna South. The results revealed that K-40 had the highest concentration in all the study areas and was found to be above the UNSCEAR (2000) recommended limit of 300 bq/kg. Ra-266, Th-232, and U-238 were found to be 37, 31, and 51 Bq/kg above the UNSCEAR (2000) recommended limits of 35, 30, and 50 Bq/kg, respectively. The annual effective dose was in the range of 1.23-2.30 mSvy(-1) above the UNSCEAR (2000) recommended safety limit. The radioactivity level in the study areas was high; therefore, continuous exposure to these radionuclides and their progenies may pose a severe risk to public health. All the sampled radionuclides were found to be within the recommended standard of =1.0 WHO reference values. [ABSTRACT FROM AUTHOR]

An experimental complex was created at the NRC Kurchatov Institute for testing of structural materials developed for MSR. The complex makes it possible to implant helium and (or) hydrogen into material specimens at the U-150 cyclotron, simulating the result of long-term neutron exposure, to perform mechanical tests and microstructural studies before and after simulation exposure, and to test the compatibility of structural materials before and after exposure with fuel salt in non-isothermal dynamic conditions at temperatures up to 750°C with control of the melt redox potential. Preliminary tests with samples of nickel-molybdenum alloy KhN80MT demonstrated the efficiency of the proposed experimental technique. The concentration of helium nuclei in the alloy samples reaches ~150 ppm for approximately 10 h of irradiation. [ABSTRACT FROM AUTHOR]

We investigate the contribution of gamma radiation of natural radionuclides constituting the Earth crust, radioactive emanations, and their decay product in the ground to the rate of production of ion pairs in the atmosphere against the background of ionization of the atmosphere by radioactive gases exhaled to the atmosphere from the ground and propagating together with their short-lived daughter products. The radon flux density to the atmosphere is estimated by three methods: the reservoir method, the integration of altitude profiles of volume activity of radon, based on gamma spectroscopic observations and the diffusion model. The distribution of the gamma radiation dose from the earth radionuclides in the soil and the atmosphere is calculated using Gleant4 software. The propagation of the radon isotopes and their decay products in the atmosphere is calculated simulated using large eddy simulation supplemented with kinematic simulation of subgrid flux of a passive scalar. It is shown that depending on the specific activity of radionuclides in the ground, the soil parameters, and the turbulent regime of the atmosphere, the total contribution of gamma radiation to the ion pair production rate in the atmospheric boundary layer is approximately from 1 to 20% and increases upon a decrease in the penetrability of the upper ground layer for radioactive emanations. [ABSTRACT FROM AUTHOR]

In the current study, the level of naturally occurring radioactivity materials (NORM) in coralline sand samples collected from Minicoy and Kavaratti Islands in Lakshadweep is determined for the first time. The measurement findings will serve as a background natural radioactivity reference level for the Lakshadweep Islands. Using an HPGe (high-purity germanium) detector-based gamma spectrometer with 100% relative efficiency, analysis of the collected sand samples was carried out to determine 226Ra, 232Th, and 40K concentration. The average activity concentrations of 226Ra, 232Th, and 40K for Minicoy coralline sands were 1.81 ± 0.2, 1.35 ± 0.2, and 9.72 ± 1.3 Bq kg–1 and for Kavaratti 1.62 ± 0.2, 0.99 ± 0.2, and 14.33 ± 1.5 Bq kg−1, respectively. The radioactivity concentrations were much below the prescribed limit (226Ra, 33 Bq kg–1; 232Th, 45 Bq kg–1; and 40K, 420 Bq kg–1) by the global average. To calculate the dose received by the locals and visitors, various radiological hazard indices like radium equivalent activity (Raeq), external hazard index (Hex), total absorbed dose rate, and the annual effective dose equivalent (AEDE) were examined in these samples. According to the findings, all of the indices fell below the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) set worldwide average limit. As a result, the findings of the present study show that coralline beach sands from the Islands of Minicoy and Kavaratti of Lakshadweep do not have any harmful radiological effects on visitors and locals. [ABSTRACT FROM AUTHOR]

In this work, activity concentrations of 226Ra, 232Th, 40K and 137Cs in soil and plant samples in Vi Thanh City were analyzed by laboratory gamma spectrometer with HPGe detector based on the Full Spectrum Analysis (FSA) method. The analytical results showed that the radioactivity values of 226Ra, 232Th, 40K and 137Cs reach the highest values in the Gleysols. The radioactivity contents of 226Ra, 232Th and 137Cs in some soil samples exceeded the average value reported by UNSCEAR (Sources and effects of ionizing radiation. Report of the United Nations Scientific Committee on the Effects of Atomic Radiation to the General Assembly, United Nations Scientific Committee on the Effects of Atomic Radiation, New York, 2000). Among many considered soil properties, the pH, electrical conductivity, organic carbon content and cation absorbance are correlated with the radioactivity content in the soil samples. The analysis of soil-to-plant transfer factors showed the general absorption trend in plants with the orders of transfer factors 40K > 137Cs > 226Ra > 232Th. [ABSTRACT FROM AUTHOR]

SiPMs are generally coupled into whole columns in gamma energy spectrum measurement, but the relationship between the distribution of whole SiPM columns and the energy resolution of the measured energy spectra is rarely reported. In this work, ∅ 3 × 3 inch NaI scintillator is placed on an 8 × 8 SiPM array, and the energy resolution of the 137Cs peak at 662 keV corresponding to the γ-ray is selected as a reference. Each SiPM is switched to explore the influence of the number of SiPM arrays, distribution position, and reflective layer on the energy resolution of SiPMs. Results show that without coupling, the energy resolution is greatly improved when the number of SiPMs ranges from 4 to 32. However, after 32 slices (the area covered by SiPMs relative to the scintillator reaches 25.9%), the improvement in energy resolution and total pulse count is not obvious. In addition, the position of SiPMs relative to the scintillator does not exert much impact on the energy resolution. Results also indicate that by adding a reflective film (ESR), the energy resolution of the tested group increases by 10.38% on average. This work can provide a reference for the design and application of miniaturized SiPM gamma spectrometers.

The results of γ-spectroscopic research of the concentrations and vertical distributions of natural 226Ra, 232Th, 40K, technogenic 137Cs, and cosmogenic 7Be radionuclides in soils, the radon flux density in the surface air, and the radon concentration in waters in some regions of the Nurata, Karatepa, Chakilkalyan, and Gissar mountains of Uzbekistan are presented. The dependence of these values on the physiographic characteristics of areas, the intensity of natural and anthropogenic processes occurring on them, weather, and other factors was revealed. [ABSTRACT FROM AUTHOR]

This study assesses the activity concentrations of the radionuclides 238U, 232Th, and 40K in soil samples collected from Wolaita Sodo town, located in the Southern Nations, Nationalities, and Peoples' (SNNP) Region, Ethiopia. A gamma-ray spectrometer equipped with a NaI(Tl) detector was used for the measurements. The concentrations of 238U, 232Th, and 40K varied from 3.25 ± 1.5 to 13.84 ± 2.2 Bq.kg-1, 0.4 ± 0.9 to 85.12 ± 3.4 Bq.kg-1, and 34.43 ± 2.7 to 748.07 ± 5.9 Bq.kg-1, respectively. The average activity concentrations were 7.83 ± 1.9 Bq.kg-1, 40.74 ± 2.7 Bq.kg-1, and 161.63 ± 3.9 Bq.kg-1 for 238U, 232Th, and 40K, respectively. The average radium equivalent activity was 192.25 Bq.kg-1, well below the recommended safety limit of 370 Bq.kg-1. The average gamma dose rate, and annual effective dose rate were 35.68 nGy.h-1, and 0.18 mSv.y-1, respectively. The internal and external indexes are below the recommended limit set by UNSCEAR and ICRP. However, the estimated excess lifetime cancer risk and indoor radon concentrations are slightly higher. Despite this, the overall radiological impact on the environment and public health in the study area remains negligible. This study provides valuable baseline data for radiation protection and informs urban and environmental policy in the region., (© The Author(s) 2025. Published by Oxford University Press.)

Wheat is one of the world's most commonly consumed cereal grains. It originates from a type of grass (Triticum) that is grown in countless varieties worldwide. Bread wheat or common wheat is a primary species. Several other closely related species include durum, spelt, emmer, einkorn, and Khorasan wheat. In addition to being a major source of starch and energy, wheat also provides substantial amounts of a number of components which are essential or beneficial for health, notably proteins, vitamins (notably B vitamins), dietary fibres, and phytochemicals. Wheat is a basic food product of Macedonian population. This study is mainly focused on measuring the concentration of radioactivity due to natural radioactive nuclides (226Ra, 232Th, 40K) in wheat grain samples, as well as on determining the quality of wheat used in daily diet. In addition, in this study we calculated radiation hazard indices (radium equivalent activity and internal hazard index) in the wheat sample. Average activity concentrations of 226Ra, 232Th, and 40K in the wheat samples were 0.57±0.14; 0.39±0.11; 96.55±0.86 (Bq·kg-1 ), respectively. The radiation hazard indices were calculated for all samples in this study where mean values did not exceed safety limits, pointing out to negligible radiation hazard arising from terrestrial radionuclides that are naturally present in wheat. In terms of quality, we confirmed that all tested samples meet the requirements regarding quality in accordance with the laws in our country.

Copyright of Nuclear Safety is the property of Nuclear & Radiation Safety Center and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

Radiation measurement is vital in radiation physics as its possible hazardous effect on human health should be known. Although radiation may be measured using different kinds of detector types, the NaI(Tl) crystal is one of the most commonly used detector types. This is due to its advantages such as low cost, resistance to thermal effects, and weather conditions. In the use of a gamma spectrometer system, the performance of the detector system is very important in order to determine absolute radiation values as the variation of measurement may affect health due to the radiation. In this work, the performance of 3″ × 3″ NaI(Tl) detector has been determined by obtaining some parameters such as response function, resolution, energy spectrum, the figure of merit. Those parameters have been measured using 22Na, 137Cs, and 60Co radioactive sources. The system was also modeled by using FLUKA code. [ABSTRACT FROM AUTHOR]

Qualitative analysis of radionuclides requires the use of reliable gamma-ray detection system. The NaI(Tl) detector has been widely used and still one of the most used detectors today. It is therefore imperative to validate the reliability of the 5 × 5 cm2 NaI(Tl) gamma spectrometry system used in carrying out gamma-ray analysis of soil samples in the Radiation and Health Laboratory, Federal University of Agriculture Abeokuta, Nigeria. The gamma ray spectrometer is housed in a 5 cm thick cylindrical lead shield. Calibration was executed using standard materials produced under the auspices of the International Atomic Energy Agency (IAEA). Resolution and detection limit (LD) of the detector were determined using full width at half the maximum of the energy peak of 137Cs and background signal level of the reference materials respectively. Counting efficiencies of the detector was calculated using energies of 1460 keV, 1764 keV and 2615 keV for 40K, 226Ra and 232Th respectively. Secondary samples, RGMIX1 and RGMIX2 were formulated and counted to calculate activity concentrations using the NaI(Tl) detector. Resolution of the detector was calculated to be 7.8% of 137Cs, which is good for a NaI(Tl) detector. The counting efficiency of the detector is seen to depend on the gamma ray energy. The results from this work shows that the detector system is suitable gamma spectrometry and will give quality measurements when used for quantitative determination of radionuclides in environmental samples. The efficiency and resolution of the NaI(Tl) detector should also be determined using photon energies obtained from other radioactive sources.

Solok Selatan is one of the areas in West Sumatra that has geothermal potential, contains much higher levels of radioactive substances in the soil in the form of Radium (Ra-226), Thorium (Th-232), and Potassium (K-40). This study aimed to measure the concentration of Ra-226. Th-232, and K-40 contained in the soil in the Solok Selatan which was then reviewed based on PERKA BAPETEN No. 9 of 2009 and UNSCEAR 2000, also evaluates the average radium equivalent activity (Raeq), representative level index (Iyr), external hazard index (Hex). Soil samples were collected from seven different locations. The radionuclide activity concentration was measured by using a gamma spectrometer in the PTKMR BATAN laboratory, with the results of the average radionuclide measurement Ra-226 being 28.58 Bq/kg, Th-232 was 44.74 Bq/kg and K-40 at 323.29 Bq/kg. For the average value of Raeq is 118,051 Bq/kg, Iyr is 0.853 and Hex is 0.335. Based on BAPETEN PERKA No. 9 of 2009 and UNSCEAR 2000, the radionuclide activity concentration was found still within safe limits. It does not pose a health hazard to the people living in the area.

Because radioactive 177Lu has a wide range of possible applications in radiopharmaceuticals, its removal from medical wastewater is particularly important. Montmorillonite clay was employed as an adsorbent in this study. Radioactive solutions were prepared with dilutions of the solution containing 177Lu at various concentrations, in which it was present as Lu3+. ULEGe detector in gamma spectrometer was used to measure 177Lu gamma rays emitted from the radioactive aqueous solutions. The results obtained showed that it is possible to remove 177Lu with a high yield of approximately 90% and it is effective in a period of 90 min under acidic conditions. From the findings, it can be argued that Montmorillonite clay, as an abundant and sustainable adsorbent, may also be suitable for the disposal of different radioactive medical wastes such as 131I and 99mTc, and also the technique based on gamma ray spectroscopy can be used for fast and practical measurements of radioactive material amounts. • 177Lu could be removed from aqueous systems in a relatively short time, with an efficiency of about 90%, by Montmorillonite. • The adsorption mechanism is predominantly ion exchange and ion coupling, and the interactions between Lu3+ ions. • The adsorption of Lu3+ is in agreement with the pseudo-second-order kinetic model and the Freundlich isotherm equation. [ABSTRACT FROM AUTHOR]

Uptake of natural radionuclides by vegetables cultivated on contaminated soil may contribute significantly to the radiation exposure of a population. This study evaluated the activity concentrations of 226Ra, 232Th, and 40K in 27 soil and 27 irrigation water samples from different farms in Lagos using Hyper Pure Germanium (HPGe) detector. Activity concentrations of 226Ra, 232Th, and 40K from soil samples were used to estimate some radiological hazard indices. The mean values of the activity concentrations for 226Ra, 232Th, and 40K in irrigation water were 2.29 ± 0.28, 0.38 ± 0.03, and 2.17 ± 0.51 Bq/l, respectively. The values for 232Th and 226Ra were 62% lower and 129% higher than their respective reference values while the value for 40K was within the values reported by similar studies. The mean specific activity for 226Ra, 232Th, and 40K in soil samples were 10.99 ± 3.75, 11.20 ± 5.36, and 19.38 ± 15.81 Bq/kg. These were 70, 75, and 81% lower than their respective world's average values. The values of the hazard indices, radium equivalent, representative level index (RLI), mean absorbed dose, outdoor annual effective dose, internal hazard index, external hazard index, and excess lifetime cancer risks (ELCRs) were 28.50 Bq/kg, 0.20, 12.50 nGy/h, 15.35 μSv/yr, 0.11, 0.08, and 0.05 × 10−3, respectively. These values were 92, 80, 72.27, 78.07, 89, 92, and 82.76% below their respective world's average values and safe limits. The soils in the study area do not present any potential radiological effects. The use of surface water for irrigation, however, poses radiological risks to consumers of vegetables. Irrigation water is, therefore, a potential source of elevated concentrations of 226Ra in vegetables cultivated in Lagos metropolis. [ABSTRACT FROM AUTHOR]

In the present study, activity concentrations of 226Ra, 232Th and 40K in soil and uranium concentration in groundwater samples collected from Sikar, Rajasthan were estimated for dosimetric purposes. Uranium content in 48 groundwater samples measured using LED fluorimeter, ranged from 0.50 µg L−1 to 93.41 µg L−1. Uranium concentration in 27% groundwater samples exceeded the safe limit (30 µg L−1) advocated by WHO and USEPA. Radio- toxicity quantified as 'Excess Cancer Risk' and chemo-toxicity as 'Lifetime Annual Daily Dose' and 'Hazard Quotient' exhibited minor concerns. The mean activity concentration of 226Ra, 232Th and 40K content in soil samples determined using NaI(Tl) gamma spectrometer were 50.28 Bq kg−1, 34.16 Bq kg−1 and 587.45 Bq kg−1, respectively. Health risk assessment due to radiation exposure form soil was carried out considering indoor/outdoor environmental conditions and age groups. [ABSTRACT FROM AUTHOR]

Chemical fertilizers, phosphate ore treatments, and phosphogypsum wastes contribute to enhanced levels of natural radionuclides in the environment. A total of 27 soil samples were collected from nine uncultivated sites around a Lebanese fertilizer plant in order to analyze the gamma emitter radionuclides (238U,232Th,226Ra,210Pb,137Cs, and40K) and to assess the radiological impact on the surrounding environment, through the calculation of different radiological index parameters. In addition, a total of 27 Dittrichia viscosa plant samples were gathered including roots, leaves, and stems, and the radionuclide transfer factors were determined. Measurements were conducted using a gamma spectrometer with high-purity germanium detectors. The highest values measured in soil samples were 77 ± 9 Bq/kg, 102 ± 10 Bq/kg, and 143 ± 5 Bq/kg for238U,226Ra, and210Pb, respectively.40K levels were comparable to other Lebanese provinces and about 50% less than the worldwide average value. The results showed the absence of radionuclide transfer between soil and plants, except for40K. The average values of the total absorbed dose rate and the annual effective dose were comparable to the worldwide average values. Therefore, the external exposure index and Radium equivalent were found to be below the international recommended values.

Under the comprehensive nuclear-test-ban treaty a State Party may request an on-site inspection to establish whether a nuclear explosion has taken place. The on-site inspection may include high- and low-resolution gamma spectroscopy surveys as well as environmental sampling and analysis. Aerial radiometric survey in particular has been demonstrated to provide efficient coverage of large areas. We have developed the Advanced Radiation Detector for Unmanned Aerial Vehicle (UAV) Operations (ARDUO) and are investigating its possible contribution to aerial radiometric survey in on-site inspection. This gamma spectrometer is direction-capable; it can point out the direction toward a source of radioactivity while in flight. We have collected data with the ARDUO flown over one and two point radiation sources in a grid survey covering 5,000 m 2 . With this data we demonstrate how directional techniques can be implemented in mobile aerial surveys to improve the spatial precision of the resulting radioactivity map. In particular, in an on-site inspection, an Inspected State Party may declare up to 50 km 2 of restricted-access sites, each of area up to 4 km 2 . We show how perimeter survey outside of a restricted-access site of area 920 m 2 with the direction-capable ARDUO permits a reconstruction of the distribution of radioactivity within the no-fly zone. [ABSTRACT FROM AUTHOR]

Natural radionuclides, such as potassium-40 (40K), radium-226 (226Ra), and thorium-232 (232Th) originating from the earth's crust can enter the human body through foods grown in the soil, which can cause internal irradiation. Information on radioactivity concentrations in foods allows us to assess the amount of exposure to radiation through the diet. K, a vitally important mineral for human health, is found in nature as a mixture of three isotopes 39K, 40K, and 41K and of these, only 40K is radioactive and constitutes 0.0117% of natural K. Because natural K is abundant in the soil, the biggest contribution among natural radionuclides that are taken into the body through food comes from 40K, and beta and gamma radiation emitted from 40K can increase the level of radiation exposure through internal irradiation. In the present study, the concentrations of radionuclides found naturally in some grains and legumes (e.g., pumpkin seeds, cowpeas, bulgur, sunflower seeds, rice, broad beans, chickpeas, beans, lentils, wheat, rye, com, barley, and oats) were measured using a spectrometer, and the annual effective radiation dose resulting from these radionuclides was evaluated. Accordingly, we found that the activity concentrations of 40K, 226Ra, and 232Th radionuclides contained in food samples had values varying between 33.27 ±5.17 and 370.4 ± 16.73, 1.19 ±0.18 and 3.55 ± 0.34, and 0.98 ± 0.06 and 3.65 ± 0.37 Bq kg"1, respectively. We determined that the annual effective dose resulting from these radionuclides varied between 0.09 and 49.98 qSvy'1. The results obtained were compared with those from other studies. The present study also aimed to develop an alternate method, which is much easier and more sensitive, using 40K concentrations to determine the K content in foods. Using this method, we observed that the amount of K in the food samples varied between 1.2 and 11.93 gkg-1. [ABSTRACT FROM AUTHOR]

Copyright of Journal Of Sichuan University (Natural Sciences Division) / Sichuan Daxue Xuebao-Ziran Kexueban is the property of Editorial Department of Journal of Sichuan University Natural Science Edition and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

A high-resolution gamma-ray spectrometer was applied to measure the activity concentration of natural and artificial radionuclides 226Ra, 232Th, 40K, and 137Cs in 14 brands of infants powdered milk consumed in Egypt. The average activity concentrations were 0.91 ± 0.20, 0.60 ± 0.11, 477 ± 25 and 0.42 ± 0.11 Bq kg−1 for 226Ra, 232Th, 40K, and 137Cs, respectively. The total annual effective dose for different infant's age groups is estimated and also the total risk has been assessed. The results indicate that the consumption of the studied powdered milk would not pose any significant radiological impact to the infants. [ABSTRACT FROM AUTHOR]

Chemical fertilizers, phosphate ore treatments, and phosphogypsum wastes contribute to enhanced levels of natural radionuclides in the environment. A total of 27 soil samples were collected from nine uncultivated sites around a Lebanese fertilizer plant in order to analyze the gamma emitter radionuclides (238U,232Th,226Ra,210Pb,137Cs, and40K) and to assess the radiological impact on the surrounding environment, through the calculation of different radiological index parameters. In addition, a total of 27 Dittrichia viscosa plant samples were gathered including roots, leaves, and stems, and the radionuclide transfer factors were determined. Measurements were conducted using a gamma spectrometer with high-purity germanium detectors. The highest values measured in soil samples were 77 ± 9 Bq/kg, 102 ± 10 Bq/kg, and 143 ± 5 Bq/kg for238U,226Ra, and210Pb, respectively.40K levels were comparable to other Lebanese provinces and about 50% less than the worldwide average value. The results showed the absence of radionuclide transfer between soil and plants, except for40K. The average values of the total absorbed dose rate and the annual effective dose were comparable to the worldwide average values. Therefore, the external exposure index and Radium equivalent were found to be below the international recommended values. [ABSTRACT FROM AUTHOR]

Based on the platform of MATLAB GUI, the experimental platform of the digital gamma spectrometer is designed, and the implementation methods of current algorithms in the process of digital nuclear pulse generator, filter shaping, baseline recovery, amplitude extraction and energy spectrum counting and display are presented. The platform can not only arbitrarily modify the key parameters in each process, but also output the results of each process in order to judge the reliability of the parameters. It can also be used for the analysis of measured nuclear pulses, providing a reference for the hardware implementation of digital nuclear energy spectrometer. [ABSTRACT FROM AUTHOR]

Feldspar, which constitutes 60% of the earth's crust, is one of the most important mineral groups. Feldspar zones and deposits are formed by cooling and crystallization of these minerals in different shapes in different parts of magma. Feldspar reserves in many sectors of an important raw material in especiaaly ceramic, porcelain and glass industries including about 14% are in Turkey. In this sense, Turkey, is located in the rich world feldspar category in terms of reserves and has a significant share of exports. Although the evaluation of reserve resources is a priority issue of mining in the country, it is very important to know the radioactivity levels of 226Ra, 232Th, 40K and 137Cs isotopes contained in the raw material used in the construction of residential and business buildings. To this end, Turkey's most important zones (Aydın, Muğla, Manisa and Kırşehir) of feldspar mine using samples obtained from the bed where radioactivity analyzes were performed. As a result of the analyzes using gamma spectrometric method, the mean activity concentrations of 226Ra, 232Th, 40K and 137Cs radioisotopes were 11.94 ± 3.8, 4.28 ± 1.7, 879.26 ± 56.3 and 1.9 ± 0.7 Bqkg-1, respectively. And than Radiological risk analysis was performed. [ABSTRACT FROM AUTHOR]

Abstract Perlite mineral contains relatively high water and in general hydrated obsidian forms the perlite which is mainly an amorphous volcanic glass. Photon attenuation properties for different concrete types including natural perlite mineral and B 4 C have been experimentally investigated by using different radioactive point sources at 81, 276, 303, 356, 384, 662, 1173, 1275 and 1333 keV. SEM and EDAX analyses were carried out to control the crystal structure of the selected concrete types. In this work, HPGe detector based on gamma spectrometer was employed for all experiments. The results revealed that among the prepared concrete samples, the P6 concrete sample has the lowest HVL and MFP values and thus, having best ability to attenuate gamma rays in comparison to the other prepared concretes. [ABSTRACT FROM AUTHOR]

BackgroundAs one of the most important issues in the field of gamma spectrum analysis, the main function of spectrum stabilization is to suppress the "spectral line drift" caused by environmental changes. Portable LaBr3(Ce) gamma spectrometer is mainly used to analyze and process the gamma spectra of radionuclides and obtain qualitative and quantitative information about radionuclides. It often works in the field complex environment where the spectrum drift is inevitable, hence must have the function of spectrum stabilization.PurposeThis study aims to improve the performance of spectrum stabilization technique for a portable LaBr3(Ce) gamma spectrometer.MethodsThe intrinsic characteristic peak of LaBr3(Ce) detector and the peak of 40K in the natural background were made of as the reference peaks. Then, the concept of "spectrum similarity" was defined to calculate the similarity between the measured spectrum and the standard background spectrum. Finally, a new spectrum stabilization method using standard reference peak and "spectrum similarity" was proposed to measure and correct the deviation. Experiments were carried out verify the performance of this new method.ResultsExperimental results show that the technology can effectively stabilize spectrum in the temperature range of -30 ℃ to 50 ℃ without calibration of the relationship curve between the reference peak and the temperature, and the peak drift of the reference peak is stable within ±1 channel even if the temperature changes more than 50 ℃∙h-1.ConclusionsThis technology effectively improves the application range of portable LaBr3(Ce) spectrometers.

In this work, it was aimed to determine the potential bacterial strains that can be bioremediated of the radioactive uranium. The experimental analysis was made in gamma spectrometry. Uranyl acetate (CH 3 COO) 2 UO 2.2H 2 O was used as the radioactive material. The radioactive solutions containing bacterial strains (P. chlororaphis (3N17-10); B. licheniformis (1N17-3); L. casei (NM-25); L. plantarum (NM-10); L. brevis (NM-26); L. lactis (NM-41); L. curvatus (NM-1); L. pentosus (NM-38); L. coryniformis (NM-22) and B. subtilis (N-28)) were prepared. A high purity germanium detector with a resolution of 490 eV at 122 keV was used to measure the photon intensities emitted from the radioactive solutions. The removal percentage and adsorbed amount of the investigated samples were determined. The results showed that P. chlororaphis have got an excellent sorption capacity for uranium removal. • Uranium could be removed from aqueous systems with an efficiency of about 95%, by adsorption using bacterial strains. • The adsorption mechanism of radioactive uranium for the bacterial strains is predominantly ion exchange and ion coupling. • P. chlororaphis have got an excellent sorption capacity for uranium removal. [ABSTRACT FROM AUTHOR]

The natural radionuclides namely 238U, 232Th and 40K for soil samples collected from locations of Alexandria and Musayyib electrical stations were measured. In addition, the radiological effects were calculated for all samples chosen in this study. The technique used in this study was gamma-ray spectrometry to estimate the natural radioactivity of twenty samples at the study area of the above-mentioned electrical stations. The results show that the specific activity of Alexandria samples of 238U were varied as 13.3 - 17.2 Bq/kg with an average of 15.4 ± 0.5 Bq/kg, 232Th were varied as 5.0 - 9.6 Bq/kg with an average of 6.2 ± 0.4 Bq/kg, and 40K were varied as 244.3 - 330.5 Bq/kg with an average of 293.0 ± 8.4 Bq/kg. But in Musayyib, the results of 238U, 232Th and 40K were varied as 10.0 - 18.7 Bq/kg with an average of 13.9 ± 0.9 Bq/kg, as 4.8 - 7.4 Bq/kg with an average of 6.0 ± 0.3 Bq/kg and as 207.5 - 294.2 Bq/kg with an average of 269.5 ± 8.6 Bq/kg, respectively. Also, it is found that the average of radiological effects like the radium equivalent (Raeq), the absorbed dose rate (Dr), external hazard index (Hex), internal hazard index (Hin), representative gamma hazard index (Iγ), the total annual effective dose equivalent (AEDE) and the excess lifetime cancer risk (ELCR) due to natural radioactivity in soil samples of Alexandria stations were 46.82 ± 2.10 Bq/kg, 23.27 ± 0.673 nGy/h, 0.126 ± 0.005, 0.167 ± 0.004, 0.359 ± 0.01, 0.142 ± 0.005 mSv/y and 0.499 ± 0.018 ⋅ 10-3, respectively, while for Musayyib were 43.29 ± 2.51 Bq/kg, 21.52 ± 0.719 nGy/h, 0.116 ± 0.004, 0.154 ± 0.006, 0.332 ± 0.011, 0.132 ± 0.005 mSv/y and 0.462 ± 0.019 ⋅ 10-3, respectively. When comparing the results in the study area with the world mean values specified by the UNSCEAR, OECD and ICRP, it can be concluded that no health risk may threaten the workers in the center of these locations due to these radionuclides in the soil of the study area.

This paper deals with correlation analysis of gamma dose rate measured in the test field with the five distinctive soil samples from a few minefields in Federation of Bosnia and Herzegovina. The measurements of ambient dose equivalent rate, due to radionuclides present in each of the soil samples, were performed by the RADIAGEMTM 2000 portable survey meter, placed on the ground and 1m above the ground. The gamma spectrometric analysis of the same soil samples was carried out by GAMMA-RAD5 spectrometer. This study showed that there is a high correlation between the absorbed dose rate evaluated from soil radioactivity and the corresponding results obtained by the survey meter placed on the ground. Correlation analysis indicated that the survey meter, due to its narrow energy range, is not suitable for the examination of cosmic radiation contribution.

The minimum detectable activity (MDA) is the activity that a system can detect with a given confidence level and good discrimination against the background radiation. When low levels of activities are counted, the MDA of gamma spectrometer must be comparable to the number of sample counts. In this research, the MDA of AT1315 spectrometer has been experimentally determined and a theoretical correlation between the MDA and experimental parameters such as the sample mass and counting time has been established. Using the correlation, the frequent and cumbersome MDA measurements can be avoided. A quantitative comparison of the theoretical and experimental MDA approaches has been performed.

Gamma ray measurement is an important issue in nuclear technology, since it is widely used in industry, medicine, agriculture, education research, and some military applications. Gamma ray is also needed to build radiation protection, which is very useful for human health. When gamma radiation penetrates through shielding material, it generates two radiation components within or beyond the shield, namely: the uncollided and the collided photons. Therefore, the buildup factor is an important parameter for gamma ray measurement. Buildup factor is defined as the ratio of the total number of particles at a given point to the number of uncollided particles, at that same point. In this work, we evaluate the gamma-ray buildup factors for copper (Cu-29), as a function of energy, for 0.511, 0.662, 1.275 MeV, by using cesium and sodium radioactive sources. The results show that the value of energy buildup factor decreases with increasing gamma energy, and increases with increasing thickness. Moreover, it was found that at high energies (1.275 MeV), the absorption buildup factor is at minimum when the energy is at high level. The results also reveal that there is no contribution from the scattering photons to the value of buildup factor, in general, at low intensity levels, when the geometry structure is built well. While for bad geometry, the detector measures intensity, which is greater than that described by the main linear attenuation coefficient, because the scattered photons will be detected as well. All in all, in order to get rational results, a well geometry should be used for the future applications. [ABSTRACT FROM AUTHOR]

Now-a-days several standard and well calibrated radioactive sources are available for gamma spectrometer efficiency calibration but at some situations, like lack of standard calibrators, in need of verification of standards or preparation a standard with the same properties with the interested sample, 40 K is a cheap and easily available radioisotope that could be used. In this study, eighteen different inorganic potassium compounds that have different potassium abundances, types of elements, densities and particle sizes were studied as efficiency verification sources. Gamma spectrometric measurements were performed and it was dawn on the compounds which have low density, low molecular weight and high potassium abundance showed higher 40 K activity concentration. It was also indicated that potassium abundance of the compound was the dominant property in these parameters. The activity concentrations were also calculated theoretically and results were in good agreement with the experimental results. Thus it was reported that the 40 K compounds with these properties are much suitable for to use as verifying sources or gamma calibrators. [ABSTRACT FROM AUTHOR]

The radiation shielding properties of some ceramic materials have been measured and obtained results were compared with the simulation. Gamma rays with energy of 662, 1173, and 1332 keV produced from 137Cs and 60Co radioactive sources were utilized in the experimental part of this work to measure linear attenuation coefficients (LAC). A gamma spectrometer with a 3″ × 3″ NaI(Tl) detector, high-voltage electrical components, a preamplifier, an amplifier, and 16384-channel Multi-Channel Analyses (MCA). For simulation the Monte Carlo method to compute and evaluate the linear attenuation coefficients of ceramic materials employed in the human body as synthetic or natural materials. In the simulations conducted with the Gamos 6.2 software, a mono-energetic point photon source geometry between 1 keV and 15 MeV was employed in the computational phase of the investigation by focusing a parallel photon beam toward the absorber material. • The radiation shielding properties of some ceramic materials have been measured and compared with the simulation. • Gamma rays with energy of 662, 1173, and 1332 keV were used for experiment. • A gamma spectrometer system with a 3″ × 3″ NaI(Tl) detector was used for experiment. • For simulation the Gamos Monte Carlo code was used to obtain the linear attenuation coefficients. • In the simulations, a mono-energetic point gamma source geometry between 1 keV and 15 MeV. [ABSTRACT FROM AUTHOR]

This work studies the activity concentration of natural radioactivity in 20 different types of rice, including imported rice and that produced locally. The rice samples were collected from markets and farms in Iraq, and then a natural radioactivity investigation was done in the environmental laboratory of the Kufa University, using gamma-ray spectrometer systems. The research focused on measuring the activity concentration of natural radioactivity (238U, 232Th, and 40K) to determine the level of the radium equivalent activity, internal hazard indices, and annual effective dose. The results show that all these parameters are within the permissible limits and that radioactivity is present in almost all foodstuffs at levels ranging from 40 to 600 Bq/kg of food. Radioactivity in foodstuffs is attributed to a natural source, potassium-40, and to artificial sources, which include industrial radioactivity, weapons testing, and accidents involving radioactivity. In this article, radionuclides have been identified for most of the common species of rice available in Iraqi markets; in addition, radium equivalent activity, internal hazard indices, and annual effective dose were calculated and compared with the permissible dose to estimate the risk of radioactive isotopes in the rice crop. [ABSTRACT FROM AUTHOR]

The natural radionuclides namely 238U, 232Th and 40K for soil samples collected from locations of Alexandria and Musayyib electrical stations were measured. In addition, the radiological effects were calculated for all samples chosen in this study. The technique used in this study was gamma-ray spectrometry to estimate the natural radioactivity of twenty samples at the study area of the above-mentioned electrical stations. The results show that the specific activity of Alexandria samples of 238U were varied from 13.3 - 17.2 Bq/kg with an average of 15.4 ± 0.5 Bq/kg, 232Th were varied from 5.0 - 9.6 Bq/kg with an average of 6.2 ± 0.4 Bq/kg and 40K were varied from 244.3 - 330.5 Bq/kg with an average of 293.0 ± 8.4 Bq/kg. But in Musayyib, the results of 238U, 232Th and 40K were varied from 10.0 - 18.7 Bq/kg with an average of 13.9 ± 0.9 Bq/kg, from 4.8 - 7.4 Bq/kg with an average of 6.0 ± 0.3 Bq/kg and from 207.5 - 294.2 Bq/kg with an average of 269.5 ± 8.6 Bq/kg respectively. Also, it is found that the average of radiological effects like the radium equivalent (Raeq), the absorbed dose Rate (Dr), external hazard index (Hex), internal hazard index (Hin), representative gamma hazard index (Iy), the total annual effective dose equivalent (AEDE) and the excess lifetime cancer risk (ELCR) due to natural radioactivity in soil samples of Alexandria stations were 46.82 ± 2.10 Bq/kg, 23.27 ± ± 0.673 nGy/h, 0.126 ± 0.005, 0.167 ± 0.004, 0.359 ± 0.01, 0.142 ± 0.005 mSv/y and 0.499 ± 0.018 • 10-3 respectively, while for Musayyib were 43.29 ± 2.51 Bq/kg, 21.52 ± 0.719 nGy/h, 0.116 ± 0.004, 0.154 ± 0.006, 0.332 ± 0.011, 0.132 ± 0.005 mSv/y and 0.462 ± 0.019 • 10-3 respectively. When comparing the results in the study area with the world mean values specified by the UNSCEAR, OECD and ICRP, it can be concluded that no health risk may threaten the workers in the center of these locations due to these radionuclides in the soil of the study area. [ABSTRACT FROM AUTHOR]

A high-resolution gamma-ray spectrometer based on a hyper-pure germanium detector has been used to determine the amounts of depleted uranium in ground features subjected to military operations during the Gulf War of 1991 and in beach sediment samples collected from the northern side of the Arabian Gulf. The determination of 235 U/ 238 U was evaluated using spiked samples with a series of depleted uranium solutions. According to this method, the levels of depleted uranium were found to exceed 6.5% of the total natural uranium required to achieve reasonable levels for detection. Soil results indicated that the average of the total radioactivity of 238 U is 50.59 Bq/kg, with approximately 41.41% of this being represented by depleted uranium. For on-site and off-site individuals in an area of 10000 m 2 , the RESRAD computer code was applied to calculate the annual radiological dose, which determined a level of 0.0031 mSv of total U; the code was also used to estimate the cancer risk, the level of which was determined to be 4.75 × 10 −6 and 1.9 × 10 −6 due to the total U and DU, respectively. [ABSTRACT FROM AUTHOR]

Problem statement Sn–Zn solders are candidate alternatives to Sn–Pb-based solder alloys. With the increasing requirement for lead-free solders, the reliability of successor solders in microelectronics assemblies is in high demand. The elimination of radionuclides, heavy metals, and other poisonous elements in lead-free Sn–6.5Zn solders in the microelectronics industry is a worldwide goal. As a result, it is useful to identify the natural concentrations of radioactive nuclides, heavy metals and other poisonous trace elements (both macro- and micro-element contents), such as Au-196, Th-227, Ag-110M, Fe-59, Zn-65, Rb-89, Rh-106M, Bi-207, Cs-137, Eu-154, Sb-126, Eu-152, Co-56, Co-58, Co-60 and K-40. If this lead-free solder contains high concentrations of natural radioactive nuclides, then workers handling it might be exposed to significant levels of radiation. Therefore, it is important to determine the levels of radioactive nuclides in this solder to protect workers; these levels provide background for the safety rules and precautions that should be applied for those working in this field. Approach The levels of natural radionuclides ( 238 U, 232 Th, and 40 K) and their daughter products contained in Sn–6.5Zn solders have been estimated via gamma-ray spectrometry using a 100% Hyper-Pure Germanium (HPGe) detector. Results The mean activities due to radionuclides, heavy metals, and other poisonous elements were measured, and the results are summarised in tables. Conclusion The results of this assessment obtained by gamma-ray spectroscopic analysis indicated the presence of high levels of natural radioactivity, heavy metals and other poisonous elements. This result implies that a comprehensive study should be conducted to protect workers from high doses of hazardous substances. [ABSTRACT FROM AUTHOR]