Devolução de doses unitárias: análise de uma prática diária

A Distribuição Individual Diária em Dose Unitária deve assegurar o maior rigor no Processo de Distribuição de Medicamentos, o que nem sempre se verificou no Hospital Pedro Hispano, dado que as Doses Unitárias devolvidas pelos Serviços de Internamento, nem sempre seguiam os Parâmetros de Qualidade. Assim, desenvolveu-se um estudo quasi-experimental, longitudinal, prospetivo e analítico, entre 1 de Março a 30 de Junho de 2012, no qual se analisaram as Doses Unitárias, devolvidas pelos Serviços de Internamento da Unidade Local de Saúde de Matosinhos a funcionam com Distribuição Individual Diária em Dose Unitária, tendo-se recolhido as não conformes relativamente aos Parâmetros de Qualidade instituídos. Na 1.ª fase do estudo (Recolha de amostras), foram contabilizadas 337 amostras, correspondentes a uma perda de 471 €. Na 2.ª fase do estudo (Implementação de acções correctivas às amostras previamente recolhidas), foram rejeitadas definitivamente 129 amostras, correspondentes a uma perda de 198 €. Na 4.ª fase do estudo (Segunda recolha de amostras), foram contabilizadas 228 amostras, correspondentes a uma perda de 199 €. A 3.ª fase do estudo incluiu a divulgação dos resultados às enfermeiras chefes dos serviços envolvidos no estudo e a 5.ª fase a comparação dos resultados obtidos na 1.ª, 2.ª e 4.ª fase do estudo. As amostras foram recolhidas em 16 serviços de internamento, sendo os valores monetários mais relevantes associados ao Espessante para alimentos líquidos e ao Imipeno + Cilastatina. A prática observada e sujeita a estudo aumenta os riscos associados ao consumo do medicamento e os custos relativos ao Processo, sendo de eliminar. A sua monitorização deve constituir uma rotina, uma vez que houve mudança de comportamentos. A redução/eliminação desta prática não conforme conduz à integração de novas tarefas com valor acrescentado, com aumento da fiabilidade do Processo.

Assessment of direct radiological risk and indirect associated toxic risks originated by Coal-Fired Power Plants

Over the past few decades there has been some discussion concerning the increase of the natural background radiation originated by coal-fired power plants, due to the uranium and thorium content present in combustion ashes. The radioactive decay products of uranium and thorium, such as radium, radon, polonium, bismuth and lead, are also released in addition to a significant amount of 40K. Since the measurement of radioactive elements released by the gaseous emissions of coal power plants is not compulsory, there is a gap of information concerning this situation. Consequently, the prediction of dispersion and mobility of these elements in the environment, after their release, is based on limited data and the radiological impact from the exposure to these radioactive elements is unknown. This paper describes the methodology that is being developed to assess the radiological impact due to the raise in the natural background radiation level originated by the release and dispersion of the emitted radionuclides. 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 2013. Data from preliminary stages are already available and possible of interpretation.

Radiological impact associated to Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM) from coal-fired power plants emissions

Certain materials used and produced in a wide range of non-nuclear industries contain enhanced activity concentrations of natural radionuclides. In particular, electricity production from coal is one of the major sources of increased human exposure to naturally occurring radioactive materials. A methodology was developed to assess the radiological impact due to natural radiation background. The developed research was applied to a specific case study, the Sines coal-fired power plant, located in the southwest coastline of Portugal. Gamma radiation measurements were carried out with two different instruments: a sodium iodide scintillation detector counter (SPP2 NF, Saphymo) and a gamma ray spectrometer with energy discrimination (Falcon 5000, Canberra). Two circular survey areas were defined within 20 km of the power plant. Forty relevant measurements points were established within the sampling area: 15 urban and 25 suburban locations. Additionally, ten more measurements points were defined, mostly at the 20-km area. The registered gamma radiation varies from 20 to 98.33 counts per seconds (c.p.s.) corresponding to an external gamma exposure rate variable between 87.70 and 431.19 nGy/h. The highest values were measured at locations near the power plant and those located in an area within the 6 and 20 km from the stacks. In situ gamma radiation measurements with energy discrimination identified natural emitting nuclides as well as their decay products (Pb-212, Pb-2142, Ra-226, Th-232, Ac-228, Th-234, Pa-234, U- 235, etc.). According to the results, an influence from the stacks emissions has been identified both qualitatively and quantitatively. The developed methodology accomplished the lack of data in what concerns to radiation rate in the vicinity of Sines coal-fired power plant and consequently the resulting exposure to the nearby population.