Radiation dose rates and exposure associated to Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM) at locations of a Portuguese coal-fired power plant

Coal contains trace quantities of natural radionuclides such as Th-232, U-235, U-238, as well as their radioactive decay products and 40K. These radionuclides can be released as fly ash in atmospheric emissions from coal-fired power plants, dispersed into the environment and deposited on the surrounding top soils. Therefore, the natural radiation background level is enhanced and consequently increase the total dose for the nearby population. A radiation monitoring programme was used to assess the external dose contribution to the natural radiation background, potentially resulting from the dispersion of coal ash in past atmospheric emissions. Radiation measurements were carried out by gamma spectrometry in the vicinity of a Portuguese coal-fired power plant. The radiation monitoring was achieved both on and off site, being the boundary delimited by a 20 km circle centered in the stacks of the coal plant. The measured radionuclides concentrations for the uranium and thorium series ranged from 7.7 to 41.3 Bq/kg for Ra-226 and from 4.7 to 71.6 Bq/kg for Th-232, while K-40 concentrations ranged from 62.3 to 795.1 Bq/kg. The highest values were registered near the power plant and at distances between 6 and 20 km from the stacks, mainly in the prevailing wind direction. The absorbed dose rates were calculated for each sampling location: 13.97-84.00 ηGy/h, while measurements from previous studies carried out in 1993 registered values in the range of 16.6-77.6 ηGy/h. The highest values were registered at locations in the prevailing wind direction (NW-SE). This study has been primarily done to assess the radiation dose rates and exposure to the nearby population in the surroundings of a coal-fired power plant. The results suggest an enhancement or at least an influence in the background radiation due to the coal plant past activities.

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.

Dosimetria das exposições em imagiologia clínica

A importância da radiação ionizante na prática médica, nãoo só como diagnóstico mas também como terapia, ganhou, no último meio século, uma importância fulcral. Devido aos efeitos secundários da radiação ao ser humano, torna-se fundamental definir regras para aumentar a segurança de todos os seus utilizadores, surgindo assim a radioprotecção. Nesse sentido a Comunidade Europeia da Energia Atómica (EURATOM) define directrizes para os países membros da Comunidade Europeia de forma a poder orientá-los nesse processo. Torna-se assim importante registar e monitorizar os valores de dose de radiação num exame radiológico para o aumento de segurança dos pacientes e técnicos. O presente trabalho desenvolvido no âmbito da disciplina anual Dissertação/Projecto/ Estágio Profissional do Mestrado em Computação e Instrumentação Médica teve como objectivo registar esses valores através da comunicação com medidores de doses. A luz do dia-a-dia da Dr. Campos Costa - Consultório de Tomogra a Computarizada S.A, é apresentada nesta tese uma aplicação computacional capaz de obter os valores de dose de um estudo radiológico a um paciente e guardá-los numa base de dados projectada exclusivamente para esse fim. Os resultados obtidos são animadores uma vez que provam ser possível automatizar a monitorização desses valores através de aplicações com ferramentas capazes de auxiliar os responsáveis por essa monitorização em qualquer centro clínico.

A reconstrução tomográfica em SPECT com utilização dos novos métodos iterativos “WBR”: comparação com métodos analíticos

Os métodos utilizados pela Medicina moderna no âmbito da Imagem Molecular e na sua capacidade de diagnosticar a partir da “Função do Orgão” em vez da “Morfologia do Orgão”, vieram trazer á componente fundamental desta modalidade da Imagiologia Médica – A Medicina Nuclear – uma importância acrescida, que se tem traduzido num aumento significativo no recurso á sua utilização nas diferentes formas das suas aplicações clínicas. Para além dos aspectos meramente clínicos, que só por si seriam suficientes para ocupar várias dissertações como a presente; a própria natureza desta técnica de imagem, com a sua inerente baixa resolução e tempos longos de aquisição, vieram trazer preocupações acrescidas quanto ás questões relacionadas com a produtividade (nº de estudos a realizar por unidade de tempo); com a qualidade (aumento da resolução da imagem obtida) e, com os níveis de actividade radioactiva injectada nos pacientes (dose de radiação efectiva sobre as populações). Conhecidas que são então as limitações tecnológicas associadas ao desenho dos equipamentos destinados á aquisição de dados em Medicina Nuclear, que apesar dos avanços introduzidos, mantêm mais ou menos inalteráveis os conceitos base de funcionamento de uma Câmara Gama, imaginou-se a alteração significativa dos parâmetros de aquisição (tempo, resolução, actividade), actuando não ao nível das condições técnico-mecânicas dessa aquisição, mas essencialmente ao nível do pós-processamento dos dados adquiridos segundo os métodos tradicionais e que ainda constituem o estado da arte desta modalidade. Este trabalho tem então como objectivo explicar por um lado, com algum pormenor, as bases tecnológicas que desde sempre têm suportado o funcionamento dos sistemas destinados á realização de exames de Medicina Nuclear, mas sobretudo, apresentar as diferenças com os inovadores métodos, que aplicando essencialmente conhecimento (software), permitiram responder ás questões acima levantadas.

Assessment of the environmental radiation by in situ gamma ray spectrometry

Naturally occurring radioactive materials (NORM) under certain conditions can reach hazardous radiological levels contributing to an additional exposure dose to ionizing radiation. Most environmental concerns are associated with uranium mining and milling sites, but the same concerns should be addressed to natural near surface occurrences of uranium as well as man-made sources such as technologically enhanced naturally occurring radioactive materials (TENORM) resulting from phosphates industry, ceramic industry and energy production activities, in particular from coal-fired power plants which is one of the major sources of increased exposure to man from enhanced naturally occurring materials. This work describes the methodology developed to assess the environmental radiation by in situ gamma spectrometry in the vicinity of a Portuguese coal fired power plant. The current investigation is part of a research project that is undergoing in the vicinity of Sines Coal-Fired Power Plant (south of Portugal) until the end of 2013.

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.