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The Uruguayan east coast has several mineral resources, which include black sand ores in the Barra de Valizas-Aguas Dulces area. Cancer in Uruguay shows non-homogeneous geographical distribution, with the highest standardized mortality ratio (SMR) in the northeast and east region, which includes the aforementioned area and the town of Barra de Valizas. The activity concentration of natural radionuclides (226Ra, 232Th and 40 K) in Barra de Valizas´soil was determined by gamma spectrometry in order to evaluate the radiological hazard for inhabitants and tourists. The outdoor annual effective dose (AEDE), excess lifetime cancer risk (ELCR), and annual gonadal dose equivalent (AGDE) were evaluated for inhabitants with a life expectancy of 77.7 years, a 0.2 and 0.5 occupancy factor, and using the conversion coefficients recommended by United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). The annual effective dose was also evaluated for both summer and fortnight tourists. The radiological hazard indices for Barra de Valizas inhabitants are higher than the worldwide mean and recommended values. This may contribute to Rocha's higher SRM value, although a direct correlation cannot be assured with the epidemiological information currently available. Social, medical and anthropological studies will be carried out in future to provide data and verify this correlation.

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The exploration of unconventional hydrocarbons may be very effective in promoting economic development and confronting energy crisis around the world. However, the environmental risks associated with this practice might be an impediment if not adequately dimensioned. In this context, naturally occurring radioactive materials and ionizing radiation are sensitive aspects in the unconventional gas industry that may compromise the environmental sustainability of gas production and they should be properly monitored. This paper provides a radioecological assessment of the São Francisco Basin (Brazil) as part of an environmental baseline evaluation regarding the Brazilian potential for exploring its unconventional gas reserves. Eleven and thirteen samples of surface waters and groundwater were analyzed for gross alpha and beta using a gas flow proportional counter. A radiological background range was proposed using the ± 2 Median Absolute Deviation method. Using geoprocessing tools, the annual equivalent doses and lifetime cancer risk indexes were spatialized. Gross alpha and beta background thresholds in surface water ranged from 0.04-0.40 Bq L-1 to 0.17-0.46 Bq L-, respectively. Groundwater radiological background varies from 0.006-0.81 Bq L-1 to 0.06-0.72 Bq L-1 for gross alpha and beta, respectively. All environmental indexes are relatively higher in the south of the basin, probably a direct response to the local volcanic formations. Traçadal fault and local gas seepages might also influence the gross alpha and beta distribution. All samples have radiological indexes below the environmental thresholds, and should remain at acceptable levels with the development of the unconventional gas industry in Brazil.

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The oil and gas industries are the largest producers of NORM wastes that are continuously generated during production and extraction activities. In addition, an increasing trend is observed in waste production worldwide due to the decommissioning of oil platforms. The problem is that most of these wastes are in activity concentration levels above the exemption and the clearance limits and are being accumulated in storage sites because no repositories exist in Brazil for NORM wastes generated by oil industries. There are regulations for radioactive wastes and for the licensing of repositories for managing wastes with low and intermediate levels of radiation but the current regulations apply only to packaged wastes. Therefore an initial radiological assessment was carried out with the RESRAD-OFFSITE code to show that bulk NORM wastes (not packaged wastes) could be disposed of in repositories near the surface without causing additional risk to the public above the criteria used. The results can also support decision-making by the Regulatory Authority to change the current regulations and allow for the disposal of wastes in bulk form.

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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.

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Introducción: La aplicación del método de la matriz de riesgo para la evaluación del riesgo radiológico en la medicina permite identificar de manera proactiva debilidades en las etapas del proceso y hacer un plan de acciones de mejora para la seguridad y calidad. Objetivo: Evaluar los riesgos radiológicos de la radiosinoviortesis y el tratamiento mielosupresor con Fósforo-32 de la policitemia vera. Método: Se utilizó el método de matriz de riesgo y se realizó el análisis y tratamiento de los riesgos radiológicos por medio del código cubano SECURE-MR-FMEA 3.0. Resultados: El 17 por ciento del riesgo alto se eliminó con las medidas adicionales adoptadas; predominaron las consecuencias medias para los trabajadores y el público, 30 por ciento y el 14 por ciento, respectivamente. Las defensas más importantes fueron: levantamiento radiológico inicial de las áreas del departamento; revisión independiente del proyecto con las regulaciones de seguridad aplicables; inspección de trabajos de construcción civil y montaje de equipos antes de iniciar la operación del departamento; capacitación de los médicos nucleares en los tratamientos; existencia de protocolos de tratamiento; análisis de lecciones aprendidas de incidentes radiológicos; levantamiento radiológico periódico de las áreas del servicio y procedimiento de emergencia para reducir la dosis en órganos críticos en caso de administración errónea de radiofármacos. Se creó una base de datos de incidentes utilizada como referencia para el modelo utilizado. El factor humano fue la causa mayor de los sucesos radiológicos analizados (88 por ciento). Conclusiones: Estos resultados facilitan la toma de decisiones para el mejor desempeño de la radiosinoviortesis y el tratamiento de la policitemia vera con Fósforo-32 en Cuba. Se sugiere elaborar el plan de mejora de la seguridad con especial atención a las operaciones de administración del radiofármaco en ambos casos.(AU)

Introduction: The application of risk matrix for ionizing radiation medicine allow identify in proactive way the weakness of the process' step, which implies in the design of safety and quality improvement plan for this. Method: Risk matrix method applied for radiosynoviorthesis and the myelosupressor treatment with Phosphorus-32 of polycythemia vera. The Cuban code SECURE-MR-FMEA 3.0 is used. Results: It was eliminated the 17 percent of the high risk with additional measures, and the medium consequences for workers and public are 30 percent and 14 percent, respectively. The most important identified safety measures were the initial radiological monitoring from different nuclear medicine department areas; the project revision based on the applicable safety regulations; a survey of civil construction works and equipment assembly before work began; training of nuclear medicine doctors in related aspects of nuclear medicine treatments; existence of treatment protocols; the analysis of learned lessons from radiological incidents; the periodical radiological monitoring from different services areas and the emergency procedure for the cases of mistake in the radiopharmaceuticals administration. Human factor was the major cause in analyzed radiological events (88 percent). Conclusions: These results facilitate taking decisions for the best performance of radiosynoviorthesis and the myelosupressor treatment with Phosphorus-32 of polycythemia vera in Cuba. It is recommended to elaborate the safety improvement plan from these and focussing in the radiopharmaceutical administration operations in both cases.(AU)

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