Radioactivity levels of 238U and 232Th decay series and related dose rates in the surroundings of a coal power plant using high resolution g-spectrometry

Gamma radiations measurements were carried out in the vicinity of a coal-fired power plant located in the southwest coastline of Portugal. Two different gamma detectors were used to assess the environmental radiation within a circular area of 20 km centred in the coal plant: a scintillometer (SPP2 NF, Saphymo) and a high purity germanium detector (HPGe, Canberra). Fifty urban and suburban measurements locations were established within the defined area and two measurements campaigns were carried out. The results of the total gamma radiation ranged from 20.83 to 98.33 counts per second (c.p.s.) for both measurement campaigns and outdoor doses rates ranged from 77.65 to 366.51 Gy/h. Natural emitting nuclides from the U-238 and Th-232 decay series were identified as well as the natural emitting nuclide K-40. The radionuclide concentration from the uranium and thorium series determined by gamma spectrometry ranged from 0.93 to 73.68 Bq/kg, while for K-40 the concentration ranged from 84.14 to 904.38 Bq/kg. The obtained results were used primarily to define the variability in measured environmental radiation and to determine the coal plant’s influence in the measured radiation levels. The highest values were measured at two locations near the power plant and at locations between the distance of 6 and 20 km away from the stacks, mainly in the prevailing wind direction. The results showed an increase or at least an influence from the coal-fired plant operations, both qualitatively and quantitatively.

Radioactivity studies in Porto urban area: gamma radiation of Paranhos sector

A set of radiation measurements were carried out in several public and private institutions. These were selected with basis on the people affluence and passage to these sites. These measurements were registration formed either indoor, outdoor or underground and were compiled in three Case Studies. Radiation doses measurements were also made, surface and underground locations, and compiled in other two Case Studies. There were sampled, at the same time, humidity, temperature, atmospheric pressure and relevant construction materials at sampling locations. They were collected and registration formed to analyse if there is any relation or contribution for the measured value in each specific place. Geostatistical models were used to elaborate maps of the results both for radiation values and for doses. Preliminary relations were established among the measured parameters.

Inventories and concentration profiles of 137Cs in undisturbed soils in the northeast of Buenos Aires Province, Argentina

Inventories and vertical distribution of (137)Cs were determined in La Plata region undisturbed soils, Argentina. A mean inventory value of 891 ± 220 Bq/m(2) was established, which is compatible with the values expected from atmospheric weapon tests fallout. The study was complemented with pH, organic carbon fraction, texture and mineralogical soil analyses. Putting together Southern Hemisphere (137)Cs inventory data, it is possible to correlate these data with the mean annual precipitations. The large differences in (137)Cs concentration profiles were attributed to soil properties, especially the clay content and the pH values. A convection-dispersion model with irreversible retention was used to fit the activity concentration profiles. The obtained effective diffusion coefficient and effective convection velocity parameters values were in the range from 0.2 cm(2)/y to 0.4 cm(2)/y and from 0.23 cm/y to 0.43 cm/y, respectively. These data are in agreement with values reported in literature. In general, with the growth of clay content in the soil, there was an increase in the transfer rate from free to bound state. Finally, the highest transfer rate from free to bound state was obtained for soil pH value equal to 8.

Modelling the Contribution of 40K, 232Th and 226Ra to Radiation Dose and Risk from Airborne Discharges of Coal-Fired Power Plants

Coal contains trace elements and naturally occurring radionuclides such as 40K, 232Th, 238U. When coal is burned, minerals, including most of the radionuclides, do not burn and concentrate in the ash several times in comparison with their content in coal. Usually, a small fraction of the fly ash produced (2-5%) is released into the atmosphere. The activities released depend on many factors (concentration in coal, ash content and inorganic matter of the coal, combustion temperature, ratio between bottom and fly ash, filtering system). Therefore, marked differences should be expected between the by-products produced and the amount of activity discharged (per unit of energy produced) from different coal-fired power plants. In fact, the effects of these releases on the environment due to ground deposition have been received some attention but the results from these studies are not unanimous and cannot be understood as a generic conclusion for all coal-fired power plants. In this study, the dispersion modelling of natural radionuclides was carried out to assess the impact of continuous atmospheric releases from a selected coal plant. The natural radioactivity of the coal and the fly ash were measured and the dispersion was modelled by a Gaussian plume estimating the activity concentration at different heights up to a distance of 20 km in several wind directions. External and internal doses (inhalation and ingestion) and the resulting risk were calculated for the population living within 20 km from the coal plant. In average, the effective dose is lower than the ICRP’s limit and the risk is lower than the U.S. EPA’s limit. Therefore, in this situation, the considered exposure does not pose any risk. However, when considering the dispersion in the prevailing wind direction, these values are significant due to an increase of 232Th and 226Ra concentrations in 75% and 44%, respectively.

Optimização e Validação da Produção de [13n]-Nh3 para Estudos Clínicos de Tomografia por Emissão de Positrões na Avaliação da Perfusão Miocárdica

A par das patologias oncológicas, as doenças do foro cardíaco, em particular a doença arterial coronária, são uma das principais causas de morte nos países industrializados, devido sobretudo, à grande incidência de enfartes do miocárdio. Uma das formas de diagnóstico e avaliação desta condição passa pela obtenção de imagens de perfusão miocárdica com radionuclídeos, realizada por Tomografia por Emissão de Positrões (PET). As soluções injectáveis de [15O]-H2O, [82Rb] e [13N]-NH3 são as mais utilizadas neste tipo de exame clínico. No Instituto de Ciências Nucleares Aplicadas à Saúde (ICNAS), a existência de um ciclotrão tem permitido a produção de uma variedade de radiofármacos, com aplicações em neurologia, oncologia e cardiologia. Recentemente, surgiu a oportunidade de iniciar exames clínicos com [13N]-NH3 para avaliação da perfusão miocárdica. É neste âmbito que surge a oportunidade do presente trabalho, pois antes da sua utilização clínica é necessário realizar a optimização da produção e a validação de todo o processo segundo as normas de Boas Práticas Radiofarmacêuticas. Após uma fase de optimização do processo, procedeu-se à avaliação dos parâmetros físico-químicos e biológicos da preparação de [13N]-NH3, de acordo com as indicações da Farmacopeia Europeia (Ph. Eur.) 8.2. De acordo com as normas farmacêuticas, foram realizados 3 lotes de produção consecutivos para validação da produção de [13N]-NH3. Os resultados mostraram um produto final límpido e ausente de cor, com valores de pH dentro do limite especificado, isto é, entre 4,5 e 8,5. A pureza química das amostras foi verificada, uma vez que relativamente ao teste colorimétrico, a tonalidade da cor da solução de [13N]-NH3 não era mais intensa que a solução de referência. As preparações foram identificadas como sendo [13N]-NH3, através dos resultados obtidos por cromatografia iónica, espectrometria de radiação gama e tempo de semi-vida. Por examinação do cromatograma obtido com a solução a ser testada, observou-se que o pico principal possuia um tempo de retenção aproximadamente igual ao pico do cromatograma obtido para a solução de referência. Além disso, o espectro de radiação gama mostrou um pico de energia 0,511 MeV e um outro adicional de 1,022 MeV para os fotões gama, característico de radionuclídeos emissores de positrões. O tempo de semi-vida manteve-se dentro do intervalo indicado, entre 9 e 11 minutos. Verificou-se, igualmente, a pureza radioquímica das amostras, correspondendo um mínimo de 99% da radioactividade total ao [13N], bem como a pureza radionuclídica, observando-se uma percentagem de impurezas inferiores a 1%, 2h após o fim da síntese. Os testes realizados para verificação da esterilidade e determinação da presença de endotoxinas bacterianas nas preparações de [13N]-NH3 apresentaram-se negativos.Os resultados obtidos contribuem, assim, para a validação do método para a produção de [13N]-NH3, uma vez que cumprem os requisitos especificados nas normas europeias, indicando a obtenção de um produto seguro e com a qualidade necessária para ser administrado em pacientes para avaliação da perfusão cardíaca por PET.