This study assesses the radiological risk to the whitemouth croaker (Micropogonias furnieri Desmarest, 1823) by calculating the dose to biota. Samples were collected, identified, and prepared for analysis from Sepetiba Bay, Rio de Janeiro, Brazil. The activity concentration (AC) results of 238U, 235U, 234U, 232Th, 230Th, 228Th, 228Ra, 226Ra, and 210Pb are expressed in Bq·kg-1. The study highlighted that biota radioprotection does not recommend dose limit concepts due to model boundary conditions, focusing instead on Derived Consideration Reference Levels (DCRL), which are used to screen for potential deleterious effects of ionizing radiation. The radionuclide-specific Dose Coefficient (DoCo) values for the analyzed radionuclides in saltwater fish are presented. The average dose rate found in M. furnieri was 7.72-2 μGy∙d-1. This average dose rate falls within the background range, suggesting no visible biological effects. The research emphasizes the need for radiological risk assessments in tropical regions, which are often underexplored compared to temperate regions. The study calls for broader studies using representative organisms to inform national legislation aimed at protecting biota from radiological risks, ensuring a comprehensive understanding of environmental safety and health.

Santa Quiteria, a city in northeastern Brazil, faces significant challenges in ensuring the availability of potable water due to its semi-arid climate and limited water resources. This study investigates the radiological quality of surface waters commonly used by the population for drinking and by animals for hydration. Water samples were collected from six different locations over a 25-month period, and the concentrations of naturally occurring radionuclides were measured using spectrophotometric analysis, total alpha, and gross beta counting. The mean activity concentrations of U nat , 226 Ra, 210 Pb, 232 Th, and 228 Ra were determined to be 9.89 center dot 10- 2 , 5.35 center dot 10- 2 , 5.86 center dot 10- 2 , 6.89 center dot 10- 3 , and 2.81 center dot 10- 3 Bq center dot L-1, respectively. Statistical methods, such as cluster and factor analysis, were applied to understand the distribution patterns of these radionuclides. The study also estimated dose rates from radionuclide intake, with a maximum value of 108.5 mu Sv center dot y-1, and compared the results against dose limits set by relevant organizations. Furthermore, the risks of morbidity and mortality from radionuclide intake were assessed, revealing the need for optimization at one sampling point where the health risks exceeded intervention thresholds.

Uranium mining can cause environmental impacts on non-human biota around mine sites. Because of this, the reduction in non-human biota exposure becomes an important issue. Environmental radioprotection results from the evolution of human radioprotection; it is based on dose rate to non-human biota and uses, as a biological target, and has harmful effects on populations. In the present study, a flooded impoundment created following dam construction in a uranium mine plant undergoing decommissioning was investigated. Internal dose rates due to activity concentration of natural uranium (Unat) and 232Th in omnivorous, phytophagous, and carnivorous fish species were estimated. Radionuclide activity concentrations were obtained by spectrophotometry with arsenazo III in the visible range. The dose rate contribution of 232Th was lower than that of Unat. There were no differences between the internal dose rates to studied fish species due to 232Th, but there were differences for Unat. A dose rate of 2.30·10–2 µGy∙d−1 was found due to the two studied radionuclides. Although this value falls below the benchmark for harmful effects, it is important to acknowledge that the assessment did not account for other critical radionuclides from uranium mining, which also contribute to the internal dose. Moreover, the study did not assess external doses. As a result, the possibility cannot be excluded that dose rates at the study area overcome the established benchmarks for harmful effects.

In Santa Quitéria City, part of the population uses surface water for potation. These waters do not undergo any treatment before consumption. As the region has a deposit of uranium, assessing water quality becomes important. In the present study, the uranium activity concentration (AC) in becquerels per liter was determined in water samples from six points. Univariate statistics showed differences between the soluble and the particulate fraction (soluble AC > particulate AC). The particulate fraction showed no variation in AC among the six points. On the other hand, the soluble fraction and the total fraction presented different ACs between them. The multivariate statistics allowed to separate the soluble from the particulate fraction of the points. The same tools applied to the total fraction made it possible to differentiate the sampling points, grouping them ((#1, #2); (#3, #4), and (#5, #6)). The maximum mean value of AC found was 0.177 Bq∙L−1, corresponding to 25

Concern about radiation exposure to non-human biota and the environment has increased since the 1990s, resulting in several publications by UNSCEAR, IAEA, ICRP, among other agencies, which highlighted significant gaps in knowledge regarding non-human biota and resulted in the establishment of Reference Animals and Plants (RAPs). In Brazil, the Atlantic Forest biome has vast biodiversity, but there is a lack of information on the radiometric profile of plant species growing there. Thus, the objective of this study was to evaluate the radiometric profile of Ouratea miersii (Malpighiales), endemic to the Atlantic Rainforest, collected in the State of Rio de Janeiro, city of Niterói, at the Municipal Natural Park (PARNIT), which covers a region of protected Atlantic Rainforest. The specimen was completely collected (root, stem, leaf and soil including organic matter around the root), and each sample analyzed individually by gamma spectrometry using a HPGe detector (Canberra). The calculated activity concentrations (AC) indicated the presence of 40K, 226Ra and 228Ra, with significant AC of 40K in the soil (3901 Bq·kg-1). The 40K soil-plant transfer was 11.6%, being limited by some physiological mechanism and/or osmotic saturation, while the transfer factor for 226Ra was 45.3%. The dose rate in non-human biota due to AC's of 226Ra and 228Ra in soil was estimated by modeling with the ERICA Tool, which indicated the absence of adverse effect on non-human biota due to exposure. The radiological hazard index values (Raeq, ADR, AEDR, and ELCR) obtained from the soil AC collected at PARNIT were significantly higher than those from other locations in Brazil, and about three times the value reported by UNSCEAR (2000) due to a ⁴⁰K anomaly in the soil. For this reason, a more extensive environmental monitoring was necessary in the PARNIT region.

Fish from a Funil dam reservoir associated with a Nuclear Fuel Factory were sampled aiming to assess the radiological risk due to ingestion. Funil dam reservoir is a strategic site, once it receives effluent from the industrial complex that performs isotopic enrichment of uranium and conversion of UF6. The mean activity concentrations obtained for 40K, 226Ra, 228Ra and 228Th were 57.81, 0.41, 0.92 and 0.49 Bq·kg-1, respectively. Lifetime cancer risk was estimated in ∼10-5 and no action needs to be taken.

Uranium mining causes several radiological impacts on the surrounding environment, notably in the water bodies, mainly due to the release of long half-life radionuclides from the 238 U and 232 Th series. The Ore Treatment Unit, an old uranium mine undergoing decommissioning, has three points of liquid effluent release (#014, #025, and #076). For current study, 78 samples of water were collected at #014, 33 samples at #025, and 63 samples at #076. The radionuclides were analyzed by gross alpha count, gross beta count, and by arsenazo spectrophotometry. Analyses were carried out using the radiological water quality criterion established by World Health Organization and other organizations, together with the Brazilian legislation, to assess if the released effluents may be used unrestrictedly by the individuals of the public. At #014, the mean values of activity concentration (AC), in Bq·L −1 , were as follows: U nat = 0.107, 226 Ra = 0.035, 210 Pb = 0.031, 232 Th = 0.007, and 228 Ra = 0.049. At #025 the mean values of AC, in Bq·L −1 , were as follows: U nat = 0.086, 226 Ra = 0.015, 210 Pb = 0.028, 232 Th = 0.006, and 228 Ra = 0.032. Finally, at point #076, the mean AC values, in Bq·L −1 , were as follows: U nat = 3.624, 226 Ra = 0.074, 210 Pb = 0.054, 232 Th = 0.013, and 228 Ra = 0.069. The current study showed that natural radionuclides were not in secular equilibrium. Despite uranium presented its values outside the limits of guidance levels, it can be state that the unrestricted use of effluents released in the three water bodies is authorized from the radiological point of view. In terms of dose rate, the releases at three points were within the radiological limits of potability. On the other hand, in an additional analysis, #76 presented chemical toxicity above the authorized value, pointing the need of restricted use of water from the point of view of chemical toxicity.

Brown marine macroalga Padina gymnospora (Phaeophyceae, Ochrophyta) produces both secondary metabolites (phlorotannins) and precipitate calcium carbonate (CaCO3-aragonite) on its surface as potential defensive strategies against herbivory. Here, we have evaluated the effect of natural concentrations of organic extracts (dichloromethane-DI; ethyl acetate-EA and methanol-ME, and three isolated fractions) and mineralized tissues of P. gymnospora as chemical and physical resistance, respectively, against the sea urchin Lytechinus variegatus through experimental laboratory feeding bioassays. Fatty acids (FA), glycolipids (GLY), phlorotannins (PH) and hydrocarbons (HC) were also characterized and/or quantified in extracts and fractions from P. gymnospora using nuclear magnetic resonance (NMR) and gas chromatography (GC) coupled to mass spectrometry (CG/MS) or GC coupled to flame ionization detector (FID) and chemical analysis. Our results showed that chemicals from the EA extract of P. gymnospora were significantly important in reducing consumption by L. variegatus, but the CaCO3 did not act as a physical protection against consumption by this sea urchin. An enriched fraction containing 76% of the new hydrocarbon 5Z,8Z,11Z,14Z-heneicosatetraene exhibited a significant defensive property, while other chemicals found in minor amounts, such as GLY, PH, saturated and monounsaturated FAs and CaCO3 did not interfere with the susceptibility of P. gymnospora to L. variegatus consumption. We suggest that the unsaturation of the 5Z,8Z,11Z,14Z-heneicosatetraene from P. gymnospora is probably an important structural characteristic responsible for the defensive property verified against the sea urchin.

The Ore Treatment Unit was a uranium mining company that is currently being decommissioned. The local rainfall index makes it necessary to release effluents into the environment. After releasing, the wastewater is available for unrestricted use. Current study aims to use national and international recommendations to assess the radiological potability of released effluents at one of the three points of company’s interface with the environment. Twenty-four samples of water were collected and activity concentrations (AC) were obtained by gross alpha count, gross beta count, and for arsenazo spectrophotometry. Statistical analysis techniques were applied to the data with the purpose of understanding the results for the soluble, particulate, and total fractions. The mean AC for effluents were 3.580, 0.082, 0.103, 0.063, and 0.090 Bq L−1 for Unat, 226Ra, 210Pb, 232Th, and 228Ra, respectively, for the total fraction. The analysis of variance pointed to Unat as a critical radionuclide, since it presented more than 90% of the total AC released into the environment. Pearson’s R2 pointed to soluble fraction as a major contributor to the total AC released. The guidance level proposed by WHO was used to assess the radiological potability of the effluents. The results obtained indicated the need for trigger other analyses. Committed effective dose was estimated due to the unrestricted use of effluents and the value obtained, 0.23 mSv year−1, was below the maximum allowed limit. Finally, the radiotoxicity of the released effluent was evaluated and the value obtained was ~ 50% of the maximum allowed limit. In conclusion, the present study showed that the level of radioactivity released into the environment by the Ore Treatment Unit does not present a radiological risk to the surrounding population.

O Depósito Inicial de Resíduos Radioativos de Baixa Atividade - DIRBA é uma instalação auxiliar à Fábrica de Combustível Nuclear - FCN para o armazenamento inicial dos rejeitos radioativos de baixa geração gerado no ciclo do combustível nuclear sob responsabilidade da FCN. Atualmente são armazenados aproximadamente 460 tambores de 200 litros contendo resíduos Classe 2.3: Resíduos contendo Radionuclídeos Naturais (RBMN-RN). Como parte do licenciamento nuclear da instalação, um programa de monitoramento radiológico da área foi desenvolvido com monitoramento mensal de 17 pontos de exposição, 3 pontos de amostragem direta de longa distância com monitores CAM alfa-7, monitorados em janeiro e 9 pontos onde manchas de alfa emissores de meia-vida longa foram monitorados em janeiro.A taxa média de exposição entre os pontos foi de 0,5 μSv ∙ h -1 , com um máximo de 1,27 μSv ∙ h -1 variando, em média, entre 0,98 μSv ∙ h -1 no ponto P1 a 0 , 23 μSv ∙ h -1 no P11. A média mensal foi a mesma, 0,50 μSv ∙ h -1 , variando de 0,46 μSv ∙ h -1 (novembro) a 0,57 μSv ∙ h -1 (agosto). Como a alfa de meia-vida de longa duração estava todas abaixo do MDA, bem como os 9 esfregaços. Em relação às exigências das áreas monitoradas, o depósito deve ser considerado como área supervisionada, do ponto de vista da radioproteção.A possibilidade de tombamento dos tambores ou outros acidentes com derramamento de material neles contido fez com que, de forma proativa, uma área considerada considerada área controlada.

Radionuclides from uranium and thorium series were analyzed to evaluate the radiological quality of the released wastewater from a uranium mine under decommissioning process. The results based on Pearson's R 2 analysis showed that the activity concentration of radionuclides in soluble and particulate fractions were statistically independent. The wastewater poses no radiological impacts to surrounding waters, generating maximum dose rates of 65 µSv·y −1 . Cancer risk was analyzed, and the value found is below that suggested to undertake some actions. Among the radionuclides studied, 210 Pb and 228 Ra were the major contributors to both dose rate and cancer risk.

Activity concentration (AC) in foods produced and commonly consumed in a High Background Radiation Area (HBRA) was analyzed. The AC were obtained by spectrophotometry and by the radiochemical separation method. The AC were up to 104 times higher than the AC for both UNSCEAR suggested values and non-HBRA. It was noted that the lifetime cancer risk was increased in 4 decimal places, taking the risk from the "statistically negligible range" (<10-6) to "middle range" (between 10-4 and 10-6).

Introdução: A radioproteção tem como foco a proteção dos seres humanos e seus descendentes e a proteção do meio ambiente. A proteção ambiental sempre foi feita de forma indireta por meio da proteção do ser humano no meio ambiente. Essa abordagem antropocêntrica tem várias deficiências. Em sua recomendação de 2007, a Comissão Internacional de Proteção Radiológica - ICRP aponta para a necessidade de uma radioproteção ser feita no meio ambiente. Conclusão: Os valores de concentração de atividade estiveram dentro das variações para emissores alfa na literatura e, com as taxas de estimativa de dose, nenhum efeito biológico relevante era esperado.

A mine in an area of naturally occurring radioactive materials (NORM), characterized by acid mine drainage, generates effluents with natural radionuclide concentrations, usually above the limits authorized by the regulator. The plant exploiting NORM controls the water quality and discharges it into the aquatic environment after meeting technical requirements. Downstream, water usage is unrestricted. In order to reach activity concentrations in the released effluents below the authorized values, the facility applies a chemical treatment to the effluent. Then, to ensure the effectiveness of the treatment, the facility performs sampling of treated effluent and determines the activity concentration of natural radionuclides (Unat, 226Ra, and 210Pb from the uranium series and 232Th and 228Ra from the thorium series). In the current study, the proportion and distribution of these radionuclides between the soluble and particulate fractions were determined. The measured activity concentrations were compared with the values proposed by the World Health Organization and Brazilian legislation, as well as other authorities, as regards the potable use from the radioprotection point of view. It was observed that the radionuclides are not in secular equilibrium. The fractions contribute differently to the total release of radionuclide, and there is no linear relationship between the fractions. The average activity concentrations did not result in radiological restrictions to water use, and the committed effective dose due to ingestion was estimated at 0.06 mSv y−1. Therefore, there is no radiological restriction to water use, since the dose which was found was below the constraint value for the public.

The Ore Treatment Unit is a deactivated uranium mine and milling situated in Caldas, MG, BR. Although disabled, there are still areas considered controlled and supervised from the radiological point of view. In these areas, it is necessary to keep an occupational monitoring program to ensure the workers' safety and to prevent the dispersion of radioactive material. For area monitoring, the dose rate, in µSv∙h-1, was measured with Geiger Müller (GM) area monitors or personal electronic monitors type GM and thermoluminescence dosimetry (TLD), in mSv∙month-1, along the years 2013 to 2016. For area monitoring, 577 samples were recorded; for personal dosimeters monitoring, 2,656; and for TLD monitoring type, 5,657. The area monitoring showed a mean dose rate of 6.42 µSv∙h-1 associated to a standard deviation of 48 µSv∙h-1 with a maximum recorded value of 685 µSv∙h-1. 96 % of the samples were below the derived limit per hour for workers (10 µSv∙h-1). For the personal electronic monitoring, the average of the data sampled was 15.86 µSv∙h-1, associated to a standard deviation of 61.74 µSv∙h-1. 80 % of the samples were below the derived limit and the maximum recorded was 1,220 µSv∙h-1. Finally, the TLD showed a mean of 0.01 mSv∙h-1 (TLD detection limit is 0.2 mSv∙month-1 equivalent to 0.28 µSv∙h-1), associated to a standard deviation of 0.08 mSv∙h-1. 98% of the registered values were below 0.2 mSv∙month-1 and less than 2 % of the measurements had values above the limit of detection. The samples show areas with low risk of external exposure, as can be seen by the TLD evaluation. Specific areas with greater risk of contamination have already been identified, as well as operations at higher risks. In these cases, the use of the individual electronic dosimeter is justified for a more effective monitoring. Radioprotection identified all risks and was able to extend individual electronic monitoring to all risk operations, even with the use of the TLD.

During its operation, the Nuclear Fuel Factory of the Nuclear Industries of Brazil (FCN/INB) may generate and disseminate particulate material. Therefor, aiming occupational control, a system of air exhaustion is installed equipped with a system of automatic detection of release of radionuclides into the environment. The present work aims to evaluate the radionuclides released by FCN, in terms of total release and activity concentration (AC). Along 2016, the amount of 4.14∙106 Bq was released, which means a mean of 3.45∙105 Bq.month-1. The largest mean for AC was 4.03 mBq∙m-3. The release data was almost an order of magnitude lower than the annual release limit established by the regulatory agency, fixed at 1.2∙107 Bq.y-1, proving the adequacy of the atmospheric effluents to the licensing requirements. The largest magnitudes of the two variables (AC and release) were observed in August while the smallest ones, in January.

As a part of our continuing search for insect and arthropod development regulators from Brazilian restinga vegetation of the Rio de Janeiro State, crude extracts, purified fractions and essential oils were submitted to screening tests seeking for biological activities on the development of the insects Rhodnius prolixus, Dysdercus peruvianus, Oncopeltus fasciatus and Rhipicephalus (Boophilus) microplus. Up to now, 102 secondary metabolites have been detected in the fractions, among them monoterpenes, sesquiterpenes and two triterpenes which were obtained from the species, Eugenia sulcata, Pilocarpus spicatus, Manilkara subsericea, Myrciaria floribunda and Zanthoxylum caribaeum. These secondary plant metabolites are considered of interest for the use of studies related to arthropod endocrinology, vector-parasite interaction system, and population control of vector insect and agricultural pest. The observed biological activities were surprisingly high, involving increased mortality, molting and metamorphosis inhibition, paralysis, corporeal deformities, apparition of permanent nymphs, of adultoids and juvenoids, partial or total inhibition of oviposition and egg hatching. These compounds are now being studied further to determine if they may or may not be useful in controlling insect populations and/or interfere with the life cycle and vector transmission of parasites to animal and human populations.

Ionizing radiation can expose individuals, and this exposure may cause deleterious biological effects. Protection against these effects, called radioprotection is accomplished through actions at the source, on the exposure routes and on the individual. It is assumed a proportional relationship between increased exposure and increased risk of stochastic effects of exposure. This approach allows dividing the network events and exposure situations and evaluating steps which are important for radioprotection. The aim of this study is to evaluate the state of the art radiation protection recommendations published by the International Commission on Radiological Protection (ICRP). For operational reasons, the radioprotection needs to perform simplifications in the relations between sources and biological effects. The last simplification was made in 2007, dividing the relations according to the sources and individuals. The principles of radioprotection (justification, dose limitation and optimization) were maintained and strengthened. The ratio depending on the source allowed the inclusion in the sources of regulatory framework previously not included and definitions of dose constraint concepts and reference levels. All this, when used with the principle of optimization of radiation protection can restrict individual doses. The maintenance of the three radiation protection principles demonstrates the robustness of these principles, as well as the maintenance of the dose limits demonstrates the confidence of the radioprotection community in the safety of these limits. Brazilian radioprotection did not reach yet the state of the art described here and is still based on ICRP previous recommendation edited in 1990, but being the legal regulations for Brazil they must be obeyed. All legislation based on ICRP No 60 and subsequent recommendations are able to protect quite adequately the environment and workers, although they are not in the state of the art as defined by the ICRP No 103 and subsequent recommendations.

Aims: To report the activity concentrations (AC) of 210 Pb in surface waters in a semi-arid region, aiming to record these concentrations before the beginning of a Naturally Occurring Radioactive Material (NORM) mining operation, facilitating subsequent comparisons with the operational phase besides verifying the radioecological characteristics of this radionuclide and the potability of the water used for human consumption by the local population. Original Research Article Pereira et al.; AIR, 9(6): 1-8, 2017; Article no.AIR.33213 2 Study Design: The water samples were collected in a six points grid associated to places of human consumption, aiming to verify their radioecological characteristics and radiological potability. Place and Duration of Study: The study site was a semi-arid region associated to a NORM phosphate deposit, between October 2009 and December 2011. No collection occurred in January and February 2010, accounting for 25 collections and 50 analyzes (soluble and particulate) per point. Methodology: 1 L of water, per point, was collected acidulated and filtered. The filtrate was considered as the soluble fraction and the retained part as the particulate fraction. The Pb was separated by coprecipitation and analyzed by total beta counts. Data were analyzed by univariate and multivariate statistical methods and the values found were compared with international potability standards. Results: The values found were within the international recommendations of ingestion of 210 Pb in water (mean value of 0.05 Bq∙l < recommended of 0.1 Bq∙l). Radionuclide radioecology proved to be complex. The total AC of 210 Pb (sum of the soluble and particulate fractions) showed no difference between points, ranging from 0.05 Bq∙l -1 at point 01SQ to 0.10 Bq∙l -1 at point 04SQ. But when the AC of the fractions were analyzed, it could be verified that the AC of the particulate fraction were systematically higher than that of the soluble fraction. Conclusion: The analyzed water, in relation to the activity concentration of Pb, is considered potable and the particulate fraction has higher AC than the soluble fraction. The characterization of the water must be complemented when entering the operation of the phosphate mine to verify the radiological environmental impact assessment of the enterprise.

The Ore Treatment Unit (in Portuguese Unidade de Tratamento de Minerios - UTM) located in Caldas, MG, Brazil is a disabled uranium mine. Environmental conditions generate acid drainage leaching metals and radionuclides from the waste rock pile. This drainage is treated to remove the heavy metals and radionuclides, before allowing the release of the effluent to the environment. To validate the treatment, samples of the released effluents were collected at the interface of the installation with the environment. Sampling was carried out from 2010 to 2015, and the activity concentration (AC, in Bq.l(-1)) of uranium in the liquid effluent was analyzed by arzenazo UV-Vis spectrophotometry of the soluble and particulate fractions, and of the sum of both fractions. Descriptive statistics, Z test and Pearson R-2 correlation among the fractions were performed. Then, the data were organized by year and both ANOVA and Tulcey test were carried out to group the means by magnitude of AC. The annual mean ranged from 0.02 Bq.l(-1) in 2015 to 0.11 Bq.l(-1) in 2010. The soluble fraction showed a higher AC mean when compared to the mean of the particulate fraction and no correlation of the data could be observed. Concerning the magnitude of the release, the ANOVA associated with the Tukey test, identified three groups of annual means (AC(2010) > AC(2011) AC(2012) = AC(2013) = AC(2014) > AC(2015)). The mean values of uranium release at the interface installation-environment checking point (point 014) were within the Authorized Annual Limit (AAL) set by the regulator (0.2 Bq.l(-1)) indicating compliance of treatment with the licensing established for the unit. Finally, the data showed a decreasing tendency of U release.