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The radioactive concentrations of 40K, 232Th and 226Ra in 11 intertidal sediment cores in the Red River Delta were determined, and radiological hazard indices for environmental risk were assessed. The values of 40K, 232Th and 226Ra activity were 656 Bq/kg, 49.8 Bq/kg and 37.0 Bq/kg, respectively. The values of radiological hazard indices such as radium equivalent activity (Raeq), absorbed dose rate (ADR), equivalent annual effective dose (AEDE), representative gamma index (Iγr), index active use, external hazard index (Hex), annual gonadal equivalent dose (AGDE) were 158.7 Bq/kg, 74.5 nGy/h, 0.09 mSv/year, 1.18, 1.0, 0.40, and 496.4 µSv/year, respectively. The results obtained of this study showed that eleven sediment cores can be divided into two groups, of which the radioactive concentrations of 40K, 232Th and 226Ra in group 2 were higher than in group 1, and the concentration of radionuclides in sediments was higher than the global average, except for 226Ra in group 1. The ADR, AEDE, Iγr and AGDE indices were above UNSCEAR's recommended levels for both groups. The results of this study show that sediments have the potential to impact organisms in the intertidal zone and are safe for use as construction materials. [ABSTRACT FROM AUTHOR]

The natural radioactivity of 238U, 232Th and 40K was measured in water and sediment samples collected from Sidi Salem dam (Tunisia) and Aïn Dalia dam (Algeria) in the Tuniso-Algerian transboundary basin. The samples were measured using a TERRA detector of gamma, beta, and alpha rays, and atomic absorption and gamma-ray spectrometry were used to analyze the levels of radionuclides and toxic elements, respectively. Potentially toxic elements (Fe, Pb, Zn, Ni, Cr, Cu and Cd) and associated health risks in surface water and sediment of dams were investigated in this present study. The concentrations of Fe, Pb, Zn, Ni, Cr, Cu and Cd in surface water ranged from 5.430 to 9.700 mg·L−1, 0.022 to 0.168, 0.018 to 0.142, 0.065 to 0.366, BDL to 0.0351, BDL to 0.071 and BDL to 0.048 mg·L−1, respectively. In the sediments, the concentrations of Fe, Pb, Zn, Cu, Ni, Cd and Cr were of the order of 136.7, 3.41, 3.22, 0.213, 0.182, 0.15 mg·L−1 and BDL, respectively. The mean radioactivity rates in the water samples were 1.72, 0.068 and 94.6 Bq·L−1 for 238U, 232Th and 40K, respectively (Tunisia dam), and were 1.9, 0.09 and 131.43 Bq·L−1 for 238U, 232Th and 40K, respectively (Algeria dam). The mean 238U, 232Th and 40K radioactivity concentrations measured in the sediment samples were 2.67, 0.18 and 197.87 Bq·kg−1, respectively (Tunisian dam), and were 4.34, 0.27 and 287.61 Bq·kg−1, respectively (Algeria dam). The activity concentration of 40K was higher than that of 238U and 232Th for the water and sediment samples. The activity concentrations follow the order 40K > 238U > 232Th. The cumulative impact of these radio-geochemical elements can cause immediate serious problems in the ecosystem due to their high potential toxicity to the environment and human health in this study area and can be transposable to any other similar region. A good knowledge of monitoring quality and quantity for transboundary water resources and international collaborations are essential to safeguard human health (women's breast cancer, thyroid cancer, neurological impact) and avoid conflicts, especially during climatic upheavals of drought. [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]

We have proposed an empirical formula for one- and two-proton decays, including the angular momentum term. While investigating the first term in the Viola–Seaborg formula, we found a linear relationship between the logarithmic half-life and the expression (a Z + b) Q − 1 / 2 for each angular momentum state. Furthermore, we obtained a linear relationship between the slope and intercept as functions of the angular momentum (l). Using these relations, we proposed a generalized empirical formula for the half-lives of one- and two-proton radioactivity for all angular momentum states. We analyzed the accuracy of the formula predictions by computing the standard deviation between the predicted and experimental decay half-lives. For the decay of one proton, the standard deviation of the proposed formula is 0.389, while that of the generalized formula is 0.400. These values represent the lowest standard deviations compared to previous models and the empirical formula. In the case of two-proton decay, the standard deviation for the current formula is 1.31, and the generalized formula also exhibits a lower standard deviation of 1.32. This lowest standard deviation value indicates that the proposed formula is suitable for reproducing the experimental half-life. We extended the half-life predictions to another 207 nuclei for one-proton decay and 42 nuclei for two-proton decay cases, which are energetically possible. The estimated half-lives for both one- and two-proton decays agree well with other theoretical predictions. [ABSTRACT FROM AUTHOR]

The cluster radioactivity of 2 2 2 , 2 2 4 , 2 2 6 Ra, 2 2 3 , 2 2 5 Ac, 2 3 2 , 2 3 4 , 2 3 5 , 2 3 6 U, 2 3 6 , 2 3 8 Pu, 2 3 4 , 2 3 6 U, 2 3 2 , 2 3 3 , 2 3 4 , 2 3 5 , 2 3 6 U and 2 3 0 , 2 3 2 Th isotopes which emitted 1 4 C, 2 4 Ne, 2 8 Mg, 2 6 Ne, 2 8 Mg, 2 4 Ne, respectively, has been analyzed with the help of fractional calculus for investigating the connection between order of the fractional derivative and nuclear structure. When the neutron number of daughter nuclei is equal to magic number, order of the fractional derivative shows a maximum. It is shown that there is a relationship between the order of fractional derivative and shell effect. This order has a similar role to the preformation factor in cluster radioactivity. [ABSTRACT FROM AUTHOR]

The article focuses on the detailed pharmacopeial standards and analytical methods for fludeoxyglucose (18F) injection, commonly known as 18F-FDG. It comprehensively outlines its chemical composition, including identity tests such as radiochemical purity and chemical purity evaluations. It emphasizes on ensuring the sterility, pH value, and absence of residual solvents, with specific criteria set for bacterial endotoxins and other impurities like aminopolyether and tetrabutylammonium.

Subtitled Library for Radioactive Afterlife, Susanne Kriemann's books P(ech) B(lende) (2016) and Ge(ssenwiese) K(anigsberg) (2020) are dedicated to the invisibility and after-effects of radioactivity. Produced by several authors, these books-as-library bring together multiple textual genres and forms of representation to explore the "radioactive afterlife", which not only indicates the horizon of survival after a nuclear catastrophe, but also the survival of images, given the impossibility of representing an invisible, immeasurable phenomenon. [ABSTRACT FROM AUTHOR]

Background: Nasolacrimal duct obstruction (NLDO) is an adverse effect of high dose radioactive iodine (RAI) therapy for thyroid carcinoma. There are currently no established preventive measures. This study assesses whether preservative free artificial tears (PFATs) can decrease the 131I sodium iodide (131I) activity in the tears of patients following RAI therapy for thyroid carcinoma, and potentially serve as a preventive measure for RAI-associated NLDO. Methods: This non-randomized prospective pilot clinical trial recruited contact-lens wearing patients undergoing RAI therapy for thyroid cancer to self-administer PFATs into the right eye for four days starting on the day of RAI ingestion. Left eyes were the controls. While wearing contacts, patients self-administered PFATs per the following—Day 1: every 15 minutes for 2 hours, then every 30 minutes until bedtime, day 2: every hour for at least 12 hours, day 3: four times a day, and day 4: two times a day. Contact lenses were changed daily, and all lenses were collected one week later. Levels of 131I activity were measured by a well counter, decay-corrected, and converted to units of becquerel. Statistical analyses were performed to compare the 131I activities of the experimental and control eyes. Results: Sixteen eyes of eight patients treated with an average of 145.7 mCi (range 108–159) of 131I for papillary thyroid cancer were included. On day 1, artificial tears decreased the geometric mean 131I activity by 26% in the experimental eyes (p = 0.008). Artificial tears also decreased the geometric mean area under the curve over four days by 23% (p = 0.002). Conclusions:131I is present in the tears following RAI therapy for thyroid carcinoma. Frequent PFATs starting on the day of RAI ingestion may decrease the level of 131I in the tears. This finding could have implications for lowering the risk of NLDO. Future multi-center clinical trials are needed to determine whether the use of artificial tears after RAI therapy may decrease the risk of NLDO. Clinical Trial Registration: NCT04327999 [ABSTRACT FROM AUTHOR]

The Cubic plus Yukawa plus Exponential (CYE) model has been used to study the different decay properties of Superheavy nuclei 298,310114, 306,318122, 308,310124, 310,322126 and compared them with the available theoretical and experimental values. Here, the half-lives of several clusters have been computed that have not yet been detected experimentally. Hopefully, this will assist future research in this area. As a result of comparing the three different decay modes (α-decay, cluster radioactivity and spontaneous fission), it was possible to predict the predominant decay modes of Superheavy nuclei. [ABSTRACT FROM AUTHOR]

The present investigation was set as a database study which estimated the bioaccumulation and potential human health risks of Uranium 238 (U- 238) when consuming Leiognathus sp. and Portunus sanguinolentus from the Madras Atomic Power Station (MAPS) zone, India. In the study, two hypothetical scenarios were applied about the consumption of those fish and crab, calculating the values of some important pollution and human risk assessment indices, such as enrichment factor, bioaccumulation factor, estimated daily intake, daily intake of radioactivity, committed effective dose, lifetime cancer risk hazard, and risk quotient. The results showed that the study area has a moderate enrichment of U-238 (2< EF <5) during all seasons; furthermore, Leiognathus sp. and P. sanguinolentus are a hyperaccumulator (BAF>10.0) from seawater. The finding of this study demonstrates that, in light of the hypothetical 1st and 2nd scenarios, the index values are below the limit set, hence there is no radiation/chemical risk from the consumption of Leiognathus sp. and P. sanguinolentus as a dominant diet from the study area. [ABSTRACT FROM AUTHOR]

This study aimed to analyze the perception of high school students about learning radioactivity content, taught by Chemistry residents, through the active Peer Instruction methodology. The qualitative research was planned and applied following the assumptions of this method. The data collected, coming from a questionnaire administered to students, was analyzed according to Bardin (2016). From the study carried out, it was noted that students had greater interest and motivation regarding radioactivity content, and it was proven that the Peer Instruction methodology helped in understanding concepts on the subject. [ABSTRACT FROM AUTHOR]

The aim of this study was to determine activity concentrations of Naturally Occuring Radioactive Materials (NORM) products and artificial radioisotopes in foods, and Brazil nut and Turkish hazelnut were selected from food products to be examined. The activity concentrations of 238U, 232Th, 40K, and 137Cs radioisotopes in Brazil nut and Turkish hazelnut products purchased from 4 different brands operating in the UK were determined by a high purity germanium detector (HPGe) that performs gamma-ray counting. Ethically; all brands were encoded as A, B, C, and D. Activity concentrations of 238U and 232Th in Brazil nut samples were found to lie in the range of 33.9 ± 0.4 ↔ 35.5 ± 0.4 Bq/kg and 19.0 ± 0.3 ↔ 31.3 ± 0.4 Bq/kg, respectively, whereas the activity concentrations of 238U and 232Th in Turkish hazelnut samples were below minimum detectable activity (MDA) values. In all samples, the most dominant sources of radioactivity were 40K in range of 220.0 ± 3.4 ↔ 242.0 ± 3.4 Bq/kg, and very low activity concentrations of 137Cs were detected only in Turkish hazelnut samples purchased from D and A brands as 1.1 ± 0.2 and 1.8 ± 0.1 Bq/kg, respectively. [ABSTRACT FROM AUTHOR]

The concentration of natural radionuclides in the soil around the world has become an environmental concern for international and national authorities because of the harmful effect of radiation exposure on human health. The samples of soil used for this study were collected from Foron and Heipang districts of Barkin Ladi Local Government Area of Plateau State. The samples were analyzed using Canberra Model 727/727R Lead Shield Gamma-ray Spectrometer with NaI(Ti) detector. The result shows that 40K ranges from 301.91 ± 0.24 Bq/kg to 124.97 ± 0.31 Bq/kg from the mining spot to 400 m away from the mining spots. 226Ra ranges from 105.43 ± 1.76 Bq/Kg to 43.10 ± 0.62 Bq/Kg from mining spots to 400 m away from the mining spots, and 232Th also ranges from 92.79 ± 0.26 Bq/kg to 26.97 ± 0.39 Bq/kg respectively. The absorbed dose rate in the air (Dr) has a mean value of 82.88 nGh-1. The annual effective dose rate (AEDR) mean value was 0.1mSvy-1, and the radium equivalent (Ra eq) mean value was 180.23 Bq/kg, Hex and Hin have mean values of 0.49 and 0.69 respectively. The calculated excess lifetime cancer risk (ELCR) ranges from 0.0003 to 0.00039 with a mean value of 0.00035 in the soil samples. Therefore, this result suggested that the area under study could be termed radiologically unsafe for people living around or close to the area. [ABSTRACT FROM AUTHOR]

In this study, we quantify specific activity of 238U, 232Th, and 40K, from soils, water, and vegetables around limestone mining sites because of the dense urban settlement with high agricultural activities around the area. Annual effective dose (AED) was evaluated and used to estimate radiological hazard impact. Mean values of internal radiation hazard index (Hin) for soils, water, and vegetation are calculated and compared with those from literatures. The estimated mean excess lifetime cancer risk (ELCR) was obtained, too. The values of ELCR are under the world average value as recommended by United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) one of the world regulatory bodies. For this reason, health related issues may occur at long time of living in this environment. [ABSTRACT FROM AUTHOR]

Nuclear grade aluminum capsules (AA-1070) was filled with 2 mg, 4 mg, 6 mg of target Sc2O3. The irradiation process of the capsule was performed in the Central Irradiation Position (CIP) G.A Siwabessy research reactor for 58.61 h. At the end of irradiation, 46Sc radioactivity was 26.67; 57.81; 85.48 mCi/capsule. The SS-316 capsule swab test, its was found that 46Sc radioactivity contamination was 2.198 Bq, 0.089 Bq and 0.218 Bq which were declared free of contamination. The gamma energy attenuation test for the thickness of the SS-304 plate, indicating that there is significant relationship between plate thickness and 46Sc gamma energy intensity. [ABSTRACT FROM AUTHOR]

Natural radioactivity (226Ra, 232Th, and 40K) concentrations were determined in sand samples collected from various beaches in Kadıköy-Istanbul (Turkey) at 12 sampling point for the evaluation of radiological parameters such as radiological equivalent activity and excess lifetime cancer risk. The activity concentrations of 226Ra, 232Th, and 40K were found to range between 21.08 and 49.19 Bqkg−1, 20.51–49.92 Bqkg−1, and 173.70–554.16 Bqkg−1, respectively. The selection of İstanbul as the study area is based on its high population density, indicating an increased vulnerability to potential negative effects of radiation exposure. [ABSTRACT FROM AUTHOR]

In radiation physics classes, point sources are typically used, for which it is relatively easy to describe the signal obtained by a radiation detector, such as the NaI(Tl) scintillation detector. The use of large extended radiation sources is generally avoided due to the mathematical complexity that their description may involve. However, the use of Monte Carlo simulation methods allows this limitation to be overcome. Potassium chloride, containing the 40K isotope, is an ideal candidate for carrying out this type of experiment. The source activity is obtained through the detection of the 1460.8 keV gamma-photon emitted in the 40K decay. In the first experiment, a cylindrical container is used, placing the NaI(Tl) detector in its center and filling the remaining space with potassium chloride. In a second, more complex case, a large radioactive source consisting of a container filled with a mixture of sand and potassium chloride, with the NaI(Tl) detector placed in the center of the mixture, is used. In this case, the mass of potassium chloride is approximately 1/5 of the sand mass. In both experiments, the detection efficiency is obtained by Monte Carlo simulation. A careful analysis of the experimental data allows to obtain a good agreement between the measured and calculated value of the activity. [ABSTRACT FROM AUTHOR]

In this article the evaluation of the radon content in drinking water samples from the province of Reggio Calabria (Calabria, Southern Italy), is reported. In particular, the 222Rn activity concentration was measured by using the Liquid Scintillation Counting (LSC) PerkinElmer Tricarb 4910 TR setup, and it was compared with the parameter value (100 Bq L-1) reported in the Italian Legislative Decree 28/2016. The annual effective dose for the population of the investigated areas, due to the ingestion of 222Rn dissolved in water, was then evaluated only in those cases in which the parameter value was exceeded. Noteworthy, results reported in this paper represent a main reference for the investigated areas and constitute a baseline for future investigations regarding background radioactivity levels. [ABSTRACT FROM AUTHOR]

Mining of mineral ore is considered one of the anthropogenic sources of elevating the activity concentrations of the natural radionuclides in the environment, which in turn causes an increased risk of human exposure via the food chain. In an attempt to evaluate the radiological burdens resulting from tin mining activities in Nigeria, farm soil and sixty-two samples of different food crops grown around tin mining areas were evaluated for the activity concentrations of 226Ra, 232Th, and 40K using a high-purity germanium detector. The mean activity concentrations of 226Ra, 232Th and 40K in soil were 64.6 ± 29.5, 72.03 ± 28.73 and 680.6 ± 324.3 Bq/kg, respectively. These values were found to be higher than their corresponding world average values. However, the mean activity concentrations of the measured radionuclides in plants were below their respective world average values, as reported by UNSCEAR. The overall average annual ingestion dose due to the consumption of the analysed plants was 151 µSv/y, which is below the reported world average value of 290 µSv/y. The results obtained show that the hazard indices were low enough to cause any immediate radiological health complications due to the ingestion of the crops grown in the studied areas. [ABSTRACT FROM AUTHOR]

This article analyses the historical geography of nuclear energy through the spatial lens of river basins. Approximately half of the world's nuclear power plants were built along one or the other river. There, they gave rise to both conflict and cooperation. Drawing on the theoretical notion of water interaction, which takes into account relations of both conflictual and cooperative nature, we distinguish between such relations in three dimensions: space, environment, and infrastructure. The spatial dimension gravitates around social and political processes where proximity and distance are at the heart, often linked to the search for suitable sites for nuclear construction. The environmental dimension refers to conflict and cooperation around the radioactive and thermal pollution of waterways. The infrastructural dimension, finally, highlights how nuclear power plant builders, when they arrived from the 1950s onwards, had to relate to pre-existing infrastructural features of the rivers, which sometimes led to clashes with other actors and sometimes to more cooperative forms of interaction. In empirical terms, we focus on three European river basins that came to play particularly important roles in European nuclear history: those of the Rhine, Danube, and Elbe. [ABSTRACT FROM AUTHOR]

Extraction and processing of the phosphate rocks has produced a massive amount of waste and posed a significant environmental concern. The majority of wastes generated in the fertiliser industry are overburden or waste rocks from mining, and phosphate tailings (PTs) or phosphogyp-sum from the beneficiation process. Phosphate rock mining and beneficiation expose heavy metals and radionuclides into the environment, which are harmful to living things. The purpose of this study was to determine the concentration levels of heavy metals and radionuclides activity in the phosphate tailings at Minjingu mines in northen of Tanzania. Heavy metals content and radionu-clide activity concentration were determined using energy dispersive X-ray fluoresence spectroscopy (ED-XRF) and high pure garmin energy detector (HPGe), respectively. The concentra-tion of heavy metals investigated ranges: Cu - 12.9-27.3 mg·kg-1, Fe - 7944.2-19052.2) mg·kg-1, Mn - 410.9-474) mg·kg-1, Ni - 1.9-13.2) mg·kg-1, Al - 3597-13129.2) mg·kg-1, Zn - 195.2-281.7) mg·kg-1, Pb - 0.7-4.5) mg·kg-1 and As - 2.7-11.3) mg·kg-1. The result revealed that, the concentration level of heavy metals (Cu, Fe, Ni, As, and Pb) are below the permissible level while concentration level for Zn has high concentration compared to permissible level limit. However, the activity concentration of radionuclides 226Ra, 232Th and 40K were ranging from 311 to 7,606 Bqkg-1, 207 to 654 Bqkg-1 and 131 to 762 Bqkg-1, respectively. The reported results of activity concentration of radionuclides are found to be higher compared to the recommended world value. The study results will be used as a guide for decision making in addressing problems observed in phosphate tailings, including radiation safety standards for workers and environmental systems in phosphate mines. [ABSTRACT FROM AUTHOR]

In this contribution, the distribution of naturally occurring radionuclides in the area around Main Karakoram Thrust (MKT) in Karakoram Range, North Pakistan is documented. Three natural radionuclides (226Ra, 232Th, and 40K) and one anthropogenic radionuclide (137Cs) were studied for their specific activities in 30 samples. The measurements were made by high resolution gamma-ray spectrometry. The sampling area is located in Gilgit Baltistan province of Pakistan at an altitude of 1838 m/6030 ft above sea level. MKT separates the Karakoram plate from the Kohistan-Ladakh Terranes and Indian Plate to the south. The specific activity varied as 4.5–56.5 Bq kg−1, 18.2–61.4 Bq kg−1, 1.4–19.6 Bq kg−1 and 51–1640 Bq kg−1 for 226Ra, 232Th, 137Cs and 40K, respectively. The average radium equivalent activity was 127.8 ± 45.9 Bq kg−1. The external hazard index was <1 for all samples and representative level index was <1 for majority of the samples. The average air absorbed dose rate was 60.9 ± 23.2 nGy h−1 corresponding to the outdoor effective dose rate of 73.7 ± 28.0 μSv y−1. These values were slightly higher than the world average values for air absorbed dose rate (51 nGy h−1) and outdoor annual effective dose rate (70 μSv y−1). The data revealed significant positive correlation between 226Ra and 40K. Principal component analysis revealed distribution patterns within the samples and identified three distinct groups. Data was also evaluated for the concentrations of uranium, thorium and potassium and their ratios. [ABSTRACT FROM AUTHOR]

The main focus of this research is to determine the extent of analyzes performed for the presence of radionuclides in food, their dynamics, which radionuclides are present in food, and how much their radioactivity was in the period 2019-2023. The research covers the period from January 01, 2019. until December 31, 2023. The data we used to conduct this research were obtained from the Public Health Institute of R. N. Macedonia. The tests were carried out with accredited methods and by the Regulation on the maximum allowed amounts of radionuclides in food, water, air, land, products, and raw materials of animal and plant origin and objects for general use. Relative numbers and trends are used as statistical methods of work. According to the results, in the period 2019-2023, radionuclides were analyzed in 6065 samples (2711 samples from imports, and 3354 samples from domestic production). The largest amount of radioactivity analyzes were performed in the group of mushrooms (51%) and the group of grain and flour (44%). The scope of analyzes performed for the presence of radionuclide residues in food in R.N. Macedonia shows a downward trend. In the analyzed products, no radioactivity above the limit values was detected (except in 2020 when only in 1 product from the mushroom group - dry morel) detected a value for Cs-137 = 662.8 Bq/kg, and the maximum allowed value is 600 Bq/kg). It can be concluded from the study that food is safe in terms of the presence of radionuclide residues, but work should be done to increase the volume of analyzes performed for the presence of radionuclides in food, as well as to increase the coverage of different groups of products (fruit, vegetables, coffee, tea, etc.) in which such analyzes would be performed. [ABSTRACT FROM AUTHOR]

Copyright of EU-topías: A Journal on Interculturality, Communication & European Studies is the property of Universite de Geneve, Global Studies Intitute 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.)

Copyright of Basrah Journal of Science / Magallat Al-Barat Li-L-ulum is the property of Republic of Iraq Ministry of Higher Education & Scientific Research (MOHESR) 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.)

The results of assessing the dose of external and internal irradiation of the tree tier of pine stands growing on the northern trace of the Belarusian sector of the 30-kilometer zone around the Chernobyl nuclear power plant at the present stage are presented. It was found that, in the most polluted experimental sites, the total dose of external and internal irradiation of the stand can reach 160 mGy/year. It is also shown that internal irradiation is formed by beta radiation of radionuclides accumulated by aboveground phytomass, its contribution to the total dose can be 80%. The external irradiation of the stand is determined by the γ-radiation of 137Cs located in the soil. The results obtained are important for understanding the processes of formation of radiation-induced effects and assessing the effects of irradiation of living organisms. [ABSTRACT FROM AUTHOR]

A dynamic mathematical model of the accumulation of radionuclides in the marine biota of Stepovoi Bay was carried out for the scenario of a hypothetical accident with a spontaneous chain reaction with a submerged K-27 submarine. The dynamic model MARINA II was used to calculate the transfer of radionuclides with water masses and the transition to the bottom sediments of the bay. The modeling results were applied to calculate the dynamics of the radiation dose rate for the marine biota of Stepovoi Bay and to assess the environmental risk for the hypothetical accident scenario considered. The predicted radioactive contamination of water is determined mainly by 137Cs and 90Sr, and contamination of bottom sediments, by 137Cs, 90Sr, and 151Sm. The averaged contamination of sediments by 137Cs in this scenario is predicted at a level that is significantly lower than the criterion for attribution to solid radioactive waste. Model assessments have shown that the maximum levels of accidental 137Cs and 90Sr in the fish of Stepovoi Bay was reached one year after a single release, and it does not exceed the established hygienic standards. The highest risk index in the accident scenario considered was estimated for a marine mammal (provided that the animal is permanently located in the bay) and amounted to 0.07. Negative radiation effects are not expected to occur for the ecosystem of StepovoI Bay at this level of environmental risk. The obtained value of the generalized indicator of radioecological safety indicates a weak radiation effect on the ecosystem of the bay for a marine mammal in Stepovoi Bay. [ABSTRACT FROM AUTHOR]

The new coronavirus pandemic (2019-nCoV) arrived in Brazil in February 2020, where the worsening led to social isolation. The population started to remain entirely in their homes, mainly the elderly, children, and adolescents. The study aimed to determine the impact of radioecological dosimetry within the residences located in the municipality from Espinharas, Paraíba, Brazil, where one of the main uranium deposits in Brazil occurs. A scintillator-type gamma spectrometer with a combined NaI (Tl) and BGO probe, at 1.0 m from the soil surface, was used. A total occupation factor for the pandemic period was considered. The dose-response for the three months ranged from 0.55 to 1.70 mSv, with an average of 0.68 mSv, which characterises an increase of 25% when compared to the same period of the retrospective study in 2014. In the period of one year, the dosimetric response can vary between 2.22 and 6.80 mSv/y, with an average of 2.73 mSv/y. The work portrays the importance of a database for future affirmative actions and the determination of different radiometric conditions in an environment already considered to have a high level of natural radioactivity. The study also provides definitions of extreme exposure conditions and correlations with public health parameters. [ABSTRACT FROM AUTHOR]

Nuclear power components contain radioactivity on their surfaces after long-term service, which can be harmful to personnel and the environment during maintenance, dismantling, and decommissioning. In this experiment, laser decontamination technology is utilized to remove radioactivity from their surfaces. In order to meet the actual needs, a laser decontamination process without spot overlapping has been studied. Under the same equipment conditions, the decontamination efficiency of the non-spot overlapping process is 10 times higher than that of the spot overlapping process. Alloy 690 is used as the test substrate, and non-radioactive specimens are prepared by simulating primary-circuit hydrochemical conditions. The surface morphology, elemental composition, and phase composition of the specimens before and after laser decontamination are investigated with SEM and XRD using the single-pulse experiment and power single-factor experiment methods, and the laser decontamination effect was evaluated. The results show that the decontamination efficiency reached 10.8 m2/h under the conditions of a pulse width of 500 ns, a laser repetition frequency of 40 kHz, a scanning speed of 15,000 mm/s, and a line spacing of 0.2 mm, according to which the removal effect was achieved when the laser power was 160 W and the oxygen content on the surface was 6.29%; additionally, there were no oxide phases in the XRD spectra after decontamination. Therefore, the laser cleaning process without spot overlap can provide reference for future practical operations to achieve efficient removal of radioactivity from nuclear power components. [ABSTRACT FROM AUTHOR]

At present, domestic and international studies on the Xinjiang River basin are limited to the study of sediment heavy metal and nuclide pollution characteristics, and there are few studies on the treatment of heavy metals in sediments of dredged bottom sediments in the Xinjiang River basin. Therefore, taking the sediment sediment of the Xinjiang River (Yingtan section) as the research object, three stabilizers were used to solidify / stabilize the heavy metal polluted sediment with Portland cement, and a heavy metal solidification / stabilization technology of river sediment was studied, which can be used for the restoration and treatment of heavy metal in river sediment. The optimal ratio of cement and three stabilizers was determined by conducting an indoor unconfined compressive strength test and leaching toxicity, and the solid phase morphological characteristics, mineral composition, and changes of heavy metal speciation before and after the treatment were combined to investigate the solidification and stabilization mechanisms of heavy metals Pb and U in the bottom sediments. The results show that the optimal formulation is 30% cement, 1∶ 1 potassium dihydrogen phosphate (Molar ratio of phosphorus to heavy metals), 5% bentonite, and 5% fly ash, under this experimental condition. The ratio of two heavy metals Pb and U active states in the substrate is reduced by about 30% after treatment with the compound reagent, and the method effectively limited the migration of heavy metals Pb and U in the substrate. SEM( scanning electron microscope) and XRD(X-ray diffraction) analysis show that the main hydration products in the cured body are hydrated calcium silicate (C-S-H), calcium alumina (Aft), and bentonite agglomerates, which can increase the strength of the curing body through the cementation. The hydration products can also adsorb and encapsulate heavy metals in the sediments. Result elucidate the mechanism of heavy metal solidification / stabilization technology for river sediment and find that the technology also has a better stabilization effect on radionuclides, which can provide a reference basis and technical support for the dredged sediment project in the Xinjiang River basin and its surrounding site soil treatment. [ABSTRACT FROM AUTHOR]

This study examined the radioactivity levels of soil samples within selected solid mining sites in Nigeria using high-purity germanium (HpGe) detector. Sixty soil samples in all were collected from the 10 solid mineral mining sites investigated and six samples were collected as control samples from non-mining environment for analyses. The results of the activity concentration values obtained for 40K, 226Ra and 232Th are 100.22 Bq kg−1, 33.15 Bq kg−1 and 77.31 Bq kg−1, respectively. The 226Ra and 40K activities were found to be within the United Nation Scientific Committee on the Effects of Atomic Radiation acceptable permissible limit, but the 232Th mean value was above the permissible limit of 30 Bq kg−1 for the public. In comparison, 40K, 226Ra and 232Th soil samples mean activity concentrations were higher than the control soil samples values by 48.6%, 43.7% and 62.3%, respectively. The results of estimated radiation hazard indices indicate average values of 150.72 Bq kg−1, 68.40 nGyh−1 n G y h − 1 , 83.65 µSvy−1 and 454.70 µSvy−1 for the Radium Equivalent (Raeq R a e q ), Absorbed Dose Rate (D), Dose Equivalent (AEDE) and Annual Gonadal Equivalent Dose (AGED), respectively. The mean values for External Hazard Indices (Hex, Hin), Representative Gamma index ( I γ ) and Excess Life Cancer Risk (ELCR) were 0.41, 0.50, 1.06 and 0.29 × 10−3, respectively. The statistical analysis shows positive skewness. [ABSTRACT FROM AUTHOR]

The effects of residual radiation from atomic bombs have been considered to be minimal because of its low levels of external radioactivity. However, studies involving atomic bomb survivors exposed to only residual radiation in Hiroshima and Nagasaki have indicated possible adverse health effects. Thus, we investigated the biological effects of radioactive dust of manganese dioxide 56 (56MnO2), a major radioisotope formed in soil by neutron beams from a bomb. Previously, we investigated C57BL mice exposed to 56MnO2 and found pulmonary gene expression changes despite low radiation doses. In this study, we examined the effects in a radiation-sensitive strain of mice, BALB/c, and compared them with those in C57BL mice. The animals were exposed to 56MnO2 particles at two radioactivity levels and examined 3 and 65 days after exposure. The mRNA expression of pulmonary pathophysiology markers, including Aqp1, Aqp5, and Smad7, and radiation-sensitive genes, including Bax, Phlda3, and Faim3, was determined in the lungs. The radiation doses absorbed in the lungs ranged from 110 to 380 mGy; no significant difference was observed between the two strains. No exposure-related pathological changes were observed in the lungs of any group. However, the mRNA expression of Aqp1 was significantly elevated in C57BL mice but not in BALB/c mice 65 days after exposure, whereas no changes were observed in external γ-rays (2 Gy) in either strain. In contrast, Faim3, a radiation-dependently downregulated gene, was reduced by 56MnO2 exposure in BALB/c mice but not in C57BL mice. These data demonstrate that inhalation exposure to 56MnO2 affected the expression of pulmonary genes at doses <380 mGy, which is comparable to 2 Gy of external γ-irradiation, whereas the responses differed between the two mouse strains. [ABSTRACT FROM AUTHOR]

In the present work, we investigate the concentration of radon and its alpha-emitting progeny at the archaeological site of Huaca 20 in Lima, Peru. The site holds significant cultural and historical importance as an ancient pre-Inca ruin, providing valuable insights into the lives and rituals of its former inhabitants. We quantified the radon levels accurately with passive CR-39TM detectors deployed within specially designed chambers at the site for 28 days. In a controlled laboratory environment, we processed the detectors afterward, examining and analyzing the resulting tracks using advanced microscopy and the ImageJ analysis software. The ground-level concentration of radon and its alpha-emitting progeny was determined, revealing elevated levels ranging from 2.4 ± 0.6 to 8.9 ± 0.9 (kBq/m³). These findings underscore the unique presence of radon at Huaca 20 and highlight the potential impact on microorganisms at ground level. Likewise, these results can contribute to studies on the radiological risks faced by visitors, excavators and archaeologists. Finally, we show the spatial distribution of radon concentrations within the site by creating an iso-concentration map. The iso-concentration map reveals a relation between areas with elevated radon levels and the good preservation of funerary contexts. [ABSTRACT FROM AUTHOR]

The Karnaphuli and Halda rivers play a significant role in the ecological and commercial arena of Bangladesh, but no detailed study on radioactivity in these two rivers sediments is reported elsewhere. The present study measures the concentrations of terrestrial radionuclides in the sediment samples collected from these two rivers by using high-purity germanium (HPGe) γ-ray spectrometry. The concentrations (Bqkg−1) of 226Ra, 232Th and 40K show in the range of 17.63 ± 1.47–38.90 ± 2.50, 27.86 ± 1.76–48.80 ± 2.70 and 324.28 ± 26.83–640.70 ± 42.70, respectively, which is similar to the literature data and world mean value except for four sampling locations (Kalamiabazar, Natun bridge, Rajakhali and Chaktai khal) that shows higher concentrations of primordial radionuclides. These four sampling points are located adjacent to the industrial wastes discharge channels into the Karnaphuli river. In fact, among the thousands of industries located on the bank of the Karnaphuli river, about 200 units were identified as the sources of environmental pollution. To assess human health hazards due to natural radiation, several indicators such as radium equivalent activity (Raeq), external hazard index (Hex) and outdoor annual effective dose equivalent were calculated and compared with the recommended limits. The present results serve as an input to prepare the baseline radioactivity in commercially important river sediments prior to the operation of the first nuclear power plant in the country. [ABSTRACT FROM AUTHOR]

Evaluated data are presented for 11 known A = 222 nuclides (Bi, Po, At, Rn, Fr, Ra, Ac, Th, Pa, U, and Np), and relevant J π and T 1/2 data for A = 226 nuclei decaying by α -decay to A = 222 nuclei. For 222Bi, only the isotopic identification is established with no measurement of its half-life. For 222Po, 222At, 222Fr, 222U, and 222Np, data are available only for the ground states, with static magnetic dipole and electric quadrupole moments, and charge radius measurements for the 222Fr ground state. For 222Ac and 222Pa, two low-lying levels are known from 226Pa α decay, and 226Np decay, respectively, but with no information about J π assignments and γ decays of these levels. For 222Pa, a long-lived isomeric state is known, decaying dominantly by α decay. 222Rn, 222Ra, and 222Th have been investigated in detail, the low-spin states by α decay and the high-spin studies of ground-state and octupole bands by in-beam γ -ray studies for all the three nuclei, as well as by Coulomb excitation for 222Rn and 222Ra. Low-spin levels in 222Ra have been investigated also through the β − decay of 222Fr. Half-lives of the excited states are known for 7 levels in 222Rn, 12 levels in 222Ra, and 3 levels in 222Th. Octupole deformations, with the presence of alternating-parity bands up to (16+) and (21 −) in 222Rn, (20+) and (19 −) in 222Ra, and (26+) and (25 −) in 222Th, and with interband E1 transitions, have been established in these three nuclei. The present evaluation supersedes the previous A = 222 ENSDF evaluations: (2011Si24), (1996El01), (1987El06) and (1977To14). [ABSTRACT FROM AUTHOR]

This letter discusses the Chinese Consensus of Nuclear Medicine (CTA) in relation to the guidelines provided by the American Thyroid Association (ATA) and European Thyroid Association (ETA) for the management of pediatric differentiated thyroid cancer (DTC). The Chinese Consensus aims to implement standardized management practices, particularly regarding 131I treatment. However, there is a lack of evidence-based clinical data on factors such as patient age, preparation for treatment, 131I radioactivity, subsequent treatments, and follow-up. The letter compares various aspects of the CTA consensus with the ATA and ETA guidelines, including age recommendations, indications for 131I treatment, preparation for treatment, 131I radioactivity, efficacy of treatment, successive treatments, TSH inhibition therapy, and follow-up. The goal is to improve clinical outcomes for pediatric DTC patients in China by aligning with international guidelines. [Extracted from the article]

The adsorption of actinide ions (Am(III) and U(VI)) from aqueous solutions using pristine and oxidized carbon fabrics was investigated by means of batch experiments at different pH values (pH 4, 7 and 9) and temperatures (25, 35 and 45 °C) under ambient atmospheric conditions. The experimental results indicated that both the pH and the fabric texture affected the adsorption rate and the relative removal efficiency, which was 70% and 100% for Am(III) and U(VI), respectively. The Kd (L/kg) values for U(VI) were generally found to be higher (2 < log10(Kd)< 3) than the corresponding values for Am(III) adsorption (1.5 < log10(Kd) < 2). The data obtained from the experiments regarding the temperature effect implied that the relative adsorption for both actinides increases with temperature and that adsorption is an endothermic and entropy-driven reaction. The application of the fabrics to remove the two actinides from contaminated seawater samples showed that both the relative removal efficiency and the Kd values decreased significantly due to the presence of competitive cations (e.g., Ca2+ and Fe3+) and complexing anions (CO32−) in the respective waters. Nevertheless, the removal efficiency was still remarkable (50% and 90% for Am(III) and U(VI), respectively), demonstrating that these materials could be attractive candidates for the treatment of radionuclide/actinide-contaminated waters. [ABSTRACT FROM AUTHOR]

The monitoring of marine ecosystems is crucial due to the growing threat posed by nuclear power plants and other nuclear anthropogenic emissions. In our work, we used a straightforward and low-cost biomonitoring technique called fluctuation asymmetry (FA) to examine the variation between the left and right sides (developmental instability) of organisms' traits that were influenced by genetic and environmental variables in the early stages of ontogenesis. The specimens of fish (Leiognathus sp.) and crabs (Portunus sanguinolentus) were collected seasonally and used as bioindicators to determine the effects of Uranium-238 (U-238) radioactivity around a nuclear power plant. The obtained results revealed that FA values were not considered typical values (FA = 0) in all seasons. Moreover, FA values of Leiognathus sp. exhibited insignificant fluctuation for a particular characteristic through the different seasons, while a significant fluctuation occurred amongst the characteristics themselves throughout the same season. Inversely, FA values of the four characteristics in Portunus sanguinolentus displayed seasonal variation amongst them all. Statistically, there was a strong positive correlation (r = 0.5, p < 0.05) between U-238 radioactivity in the flesh of both organisms and the fluctuation asymmetry of different traits but it is not a sign that any radioactive pollution exists. [ABSTRACT FROM AUTHOR]

Daprodustat is an oral small molecule hypoxia‐inducible factor (HIF) prolyl hydroxylase inhibitor (PHI) approved in Japan and the United States for the treatment of anemia associated with chronic kidney disease. This phase 1, nonrandomized, 2‐period, crossover study in 6 healthy men characterized and quantified the metabolites generated after a microtracer IV infusion of 50 μg (125 nCi) [14C]‐daprodustat administered concomitantly with a nonradiolabeled therapeutic dose of a 6‐mg daprodustat tablet, followed by a single oral solution dose of 25 mg (62.5 μCi) [14C]‐daprodustat. High‐performance liquid chromatography (HPLC) coupled with radioactivity detection (TopCount or AMS) and HPLC‐tandem mass spectrometry (HPLC‐MSn) were used for quantitative measurement and structural identification of radioactive metabolites in plasma, urine, feces, and bile. Following oral administration of [14C]‐daprodustat, unchanged daprodustat was the principal circulating drug‐related component, accounting for 40% of plasma radioactivity. Predominant oxidative metabolites M2, M3, M4, and M13 individually represented 6–8% of the plasma radioactivity and together accounted for the majority of radioactivity in urine and feces (53% in both matrices; 12% and 41% of dose, respectively). Unchanged daprodustat was not detected in urine and was only 0.7% of total radioactivity in feces (<0.5% of dose), with the remainder of the dose accounted for by oxidative metabolites. The radio‐metabolic profile of duodenal bile following IV infusion of [14C]‐daprodustat was similar to that observed in feces after oral administration. The data suggested that oral daprodustat was extensively absorbed, cleared exclusively by oxidative metabolism, and eliminated via hepatobiliary (primary) and urinary (secondary) excretion. [ABSTRACT FROM AUTHOR]

This article provides a historical overview of the use of radium in the treatment of localized cancers. It mentions the discovery of radium and its application in medicine in the early 20th century, with Alexander Graham Bell proposing its use in treating deep-seated cancers. The contributions of Marie and Pierre Curie in the study of radioactivity and the isolation of radium are also highlighted. The article notes that radium was mistakenly believed to have universal therapeutic properties and was added to various products. However, as the harmful effects of radiation became better understood, the use of radium in medicine declined, and it is now prohibited by law in France. [Extracted from the article]

The objective of the study was to estimate the effective dose rates of external population exposure based on measurements of average specific activity of natural radionuclides (226Ra, 232Th and 40K) in building materials of existing buildings. The measurements were performed using new developed non-destructive technique in 100 apartments in 9 Russian cities. The effective dose rate is 34 nSv h–1 in average and varies from 10 to 102 nSv h–1 between cities. Specific factors of conversion from specific activity to effective dose rate were obtained taking into account the real room geometries. [ABSTRACT FROM AUTHOR]

Eorae mountain which is located in the Ogcheon metamorphic zone, was reported high radioactivity rock character. Therefore, 68 groundwaters around Eorae mountain area were sampled according to the geological radioactivity data and radioactive element such as uranium and radon (222Rn) were analyzed to understand radioactive element distribution. U and 222Rn contents distribution was different around Gongju fault line. The U content ranged from < 0.07 to 84.7 μg/L and 222Rn content ranged from 1.01 to 428 Bq/L. The average U and 222Rn content of northern and eastern part were high, which place was close to Eorae mountain. [ABSTRACT FROM AUTHOR]

Bentonite is a soft, porous, easily shaped, and absorbent material rich in aluminum, sodium, and potassium. Bentonite is a mineral widely utilized as drilling mud, ore pelletizing, absorbent/adsorbent, bleaching agent, water impedance, coating, and raw material in various industries. In this study, radiometric measurements of 90 bentonite samples collected from 21 quarries in Turkey were performed using gamma-ray spectrometry. The radiological hazards caused by indoor exposure to adults due to the utilization of bentonites as raw materials in the construction industry and outdoor external exposures to quarry workers were evaluated by estimating the activity concentration index, annual effective doses, and lifetime cancer risk. The average activity concentrations of 226Ra, 232Th and 40K measured in bentonite samples were found as (50 ± 5) Bq/kg, (76 ± 4) Bq/kg and (373 ± 19) Bq/kg, respectively. The evaluation results reveal that the bentonites examined could be safely utilized as raw materials. [ABSTRACT FROM AUTHOR]

Radionuclides 226Ra, 232Th, and 40K can be found in various concentrations in the surface soil. High concentrations of radionuclides in the surface soil may cause radiological risks. This study investigated natural radioactivity levels and artificial radionuclide (137Cs) levels in the Istanbul University-Cerrahpasa, Avcilar region, Istanbul, Turkey. Radioactivity concentrations were analyzed using the gamma-ray spectrometer. The mean activity concentration of 226Ra, 232Th, 40K, and 137Cs is 28.55, 29.57, 385.72, and 3.09 Bq kg−1, respectively. Radiological parameters radium equivalent activity, absorbed dose rate, annual effective dose equivalent, external hazard index, and excess lifetime cancer risk were calculated using activity concentrations. The radiological parameters values were lower than UNSCEAR values, except for the annual gonadal dose equivalent (approximately 10% higher). There is a strong correlation between radiological parameters and radionuclides. Generally, the activities of radionuclides in the region fall within the recommended limits, thus Istanbul-Avcilar region can be considered safe for settlement. [ABSTRACT FROM AUTHOR]

The concentration of natural and anthropogenic radionuclides, emanation fraction (EF), and mass (χM) and area (χA) exhalation rate of 222Rn in urban soil samples collected from dwelling areas in Nevşehir city located in a region known as the central Anatolian volcanic province of Turkey were determined using gamma-ray spectroscopy. The average activity concentrations of 226Ra, 228Ra, 40K and 137Cs were measured as 60.2 ± 3.8, 50.1 ± 2.8, 631.0 ± 29.7 and 5.5 ± 0.4 Bq/kg, respectively. The average concentration of 222Rn in soil and air was estimated as 27 kBq/m3 and 84 Bq/m3, respectively. The average values of EF, χM and χA were found as 20%, 25.4 μBq/kg⋅s and 20.2 mBq/m2⋅s, respectively. The average values of outdoor absorbed gamma dose rate, external and internal annual effective dose and lifetime cancer risk estimated for radiological assessment were found as 85 nGy/h, 104 µSv/y, 797 µSv/y and 4.1 × 10−4, respectively. [ABSTRACT FROM AUTHOR]

Samples have been collected from two sources of water: drinking water and well water, for various depths for the Al-Bayaa region in Baghdad using a gamma spectrometer with the Germanium HPGe detector. The results of the analysis show that the average activity concentrations were 1.19±0.5 for 238U, 0.96±0.2 for 232Th, and 10.5±0.5 0.5Bq/L for 40K in drinking water samples, and1.77±0.5 for 238U, 1.03±0.2 for 232Th, and 12.6± 0.5Bq/L for 40K in well water samples, respectively. The results were less than their recommended. The study also calculated the radiation hazards represented by the radium equivalent activity, Gamma index, Hazard Index, Absorbed gamma dose rate, Annual effective dose equivalent, and Lifetime cancer risk. All the radiological parameters in water drinking and well samples were within the range of the global limit; thus the water drinking and well water was Safe and free from radioactive contamination in that area. [ABSTRACT FROM AUTHOR]

The impact of radioactivity on the environment and health is very overwhelming, until today these continuous radiations affect local populations by differential cancers, eye diseases, genetic malformations and other rare diseases. Fatal radiation carried by sand, water and poisoned air affects local populations directly or indirectly. The Analysis of spatial phenomena is effective by the use of techniques of geomatics, and that is when the geographical problems are quantitative and qualitative, can be easily applied in identifying and explaining phenomena. In our case how to make knowledge, despite the enormous number of cancer patients, there has been practically no geographical discussion on the aggravating factors linked to radioactive risks, we have not even spatialized radioactive territories in Algeria. The aim of this study is to identify carcinogenic sites by the spatialization of radioactivity due to nuclear tests in Algeria. [ABSTRACT FROM AUTHOR]

A new ultra-low background high-purity germanium (HPGe) detector has been installed at the Kamioka underground experimental site. The background count rate in the energy range from 40 keV to 2700 keV is about 25% lower than that of the first HPGe detector installed in 2016, which has the same detector specification and similar shielding geometry. This paper describes the shielding configuration, including the cleaning of the material surface, the comparison of calibration data and simulation, the time variation of the background spectra, the sample measurement procedure, and some results of the radioactivity in the selected samples. [ABSTRACT FROM AUTHOR]

The aim of this study was to examine the effect of the Common Knowledge Construction Model (CKCM) on the conceptual understanding of science teacher students about Radioactivity. CKCM was used. In order for the students to adapt the radioactivity subject, which they see as difficult and abstract, to daily life by knowledge structuring. This study was carried out with 48 students studying in the second year of science education at a public university in the western region. The research employed pretest-posttest control group random design. The Radioactivity Concept Test (RCT) with 2 phases consisting 23 multiple-choice items were used as data collection tools in the research. After the tests were applied as a pilot study to 124 students, it was used with the participants of the study after the necessary validity and reliability studies were carried out. The KR20 reliability coefficient obtained from the sample data was calculated as 0.74. In the study, experimental and control groups were formed by random assignment. While the traditional lecture method was applied to the control group, the CKCM was applied to the experimental group. When the concept test data were analyzed with the SPSS 24 package program, it was determined that the experimental group were more successful than the control group. determined that the increase in correct answers in the post-test of the experimental group was higher than that of the control group. [ABSTRACT FROM AUTHOR]