999 resultados para DD nuclear fusion


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Formaldehyde (FA), also known as formalin, formal and methyl aldehydes, is a colorless, flammable, strong-smelling gas. It has an important application in embalming tissues and that result in exposures for workers in the pathology anatomy laboratories and mortuaries. Occupational exposure to FA has been shown to induce nasopharyngeal cancer and has been classified as carcinogenic to humans (group 1) on the basis of sufficient evidence in humans and sufficient evidence in experimental animals. Manifold in vitro studies clearly indicated that FA is genotoxic. FA induced various genotoxic effects in proliferating cultured mammalian cells. The cytokinesis-block micronucleus (CBMN) assay was originally developped as an ideal system form easuring micronucleus (MN), however it can also be used to measure nucleoplasmic bridges (NBP) and nuclear buds (NBUD). Over the past decade another unique mechanism of micronucleus formation, known as nuclear budding has emerged. NBUDS is considered as a marker of gene amplification and/or altered gene dosage because the nuclear budding process is the mechanism by which cells removed amplified and/excess DNA.

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A new circuit topology is proposed to replace the actual pulse transformer and thyratron based resonant modulator that supplies the 60 kV target potential for the ion acceleration of the On-Line Isotope Mass Separator accelerator, the stability of which is critical for the mass resolution downstream separator, at the European Organization for Nuclear Research. The improved modulator uses two solid-state switches working together, each one based on the Marx generator concept, operating as series and parallel switches, reducing the stress on the series stacked semiconductors, and also as auxiliary pulse generator in order to fulfill the target requirements. Preliminary results of a 10 kV prototype, using 1200 V insulated gate bipolar transistors and capacitors in the solid-state Marx circuits, ten stages each, with an electrical equivalent circuit of the target, are presented, demonstrating both the improved voltage stability and pulse flexibility potential wanted for this new modulator.

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Formaldehyde (FA) is ubiquitous in the environment and is a chemical agent that possesses high reactivity. Occupational exposure to FA has been shown to induce nasopharyngeal cancer and has been classified as carcinogenic to humans (group 1) on the basis of sufficient evidence in humans and sufficient evidence in experimental animals. The exposure to this substance is epidemiologically linked to cancer and nuclear changes detected by the cytokinesis-block micronucleus test (CBMN). This method is extensively used in molecular epidemiology, since it determines several biomarkers of genotoxicity, such as micronucleus (biomarkers of chromosomes breakage or loss), nucleoplasmic bridges (biomarker of chromosome rearrangement, poor repair and / or telomeres fusion) and nuclear buds (biomarker of elimination of amplified DNA). The gene X-ray repair cross-complementing group 3 (XRCC3) is involved in homologous recombination repair of cross-links and chromosomal double-strand breaks and at least one polymorphism has been reported in codon 241, a substitution of a methionine for a threonine.

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The increase of mortality from cancer brought urgency in identification and validation of predictive markers of risk and therefore early diagnosis. There is evidence that cytogenetic biomarkers are positively correlated with risk of cancer, and this is validated by studies of cohort and case-control. Cytokinesis-blocked micronucleus (CBMN) assay is used extensively in molecular epidemiology, and can be considered as a “cytome” assay covering cell proliferation, apoptosis, necrosis and chromosomal changes. The chromosomal alterations most reported and studied by the CBMN are: micronucleus (MN), nucleoplasmic bridges (NPB) and nuclear buds (NBUDS). The use of the MN assay in biomonitoring studies had a large increase in the last 15 years and international projects such as the HUMN have helped to increase the applicability and reliability of these tests.

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Objectivo do estudo - Demonstrar o contributo, essencial, que a Medicina Nuclear apresenta no diagnóstico dos Tumores Gastroenteropancreáticos e demonstrar a importância da precocidade diagnóstica recorrendo, maioritariamente, aos exames de medicina nuclear.

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Introdução – A monitorização da exposição ocupacional a doses de radiação ionizante pode ser complementada por dosímetros eletrónicos individuais que permitem uma leitura direta da dose de radiação recebida. Dada a dependência energética e de débito de dose já reportada para estes dosímetros, este trabalho pretende determinar a linearidade da resposta de um dosímetro eletrónico individual e estudar o comportamento da sua resposta em função da energia de radiação e do débito de dose. Metodologia – Para estudar a dependência da energia da radiação do dosímetro eletrónico pessoal Vertec Bleeper Sv procedeu‑se à sua irradiação com um equivalente de dose individual, Hp(10), de 500 μSv de radiação gama do Cobalto – 60 (60C) e Césio – 137 (137Cs) e das qualidades de radiação X da série Narrow (N): N‑30, N‑40, N‑60, N‑80, N‑100 e N‑120. Para investigar a dependência da resposta em função do débito de dose aplicaram‑se à ampola de raios X as intensidades de corrente elétrica de 1 mA, 5 mA, 10 mA, 15 mA e 20 mA. Resultados – Não existe uma relação entre a resposta do detetor e a energia de radiação a que este é exposto. Ocorre uma subestimação superior a 50% na grandeza medida para energias inferiores a 33 keV, mas ostenta uma medida relativamente linear da grandeza Hp(10) para doses inferiores a 100 μSv. Também se constata que, à medida que o débito de dose aumenta, existe uma diminuição na resposta do dosímetro. O menor decréscimo na resposta deste dosímetro eletrónico individual dá‑se para as qualidades de radiação N‑30 (1,1%), N‑40 (4,1%) e N‑120 (20,0%). Conclusão – Verifica‑se que a resposta do dosímetro individual Vertec Bleeper Sv depende fortemente da energia da radiação e do débito de dose. ABSTRACT: Introduction – The measurement of occupational exposure to radiation doses can be completed with an electronic personal dosemeter that allows a direct reading and alarm function of the received radiation dose. Due to the energy and dose rate dependence already reported for this type of dosemeter, it is intended, with this work, to determine the response linearity of an Electronic Personal Dosemeter and to study its response behavior to the dose rate and radiation energy. Methodology – The electronic personal dosemeter Vertec Bleeper Sv energy dependency was evaluated by its irradiation with 500 μSv from the radionuclides Cobalt – 60 (60C) and Cesium – 137 (137Cs) as well as by the radiation qualities of the Narrow (N) series: N‑30, N‑40, N‑60, N‑80, N‑100 e N‑120. To investigate the dose rate dependency, the intensities of electric current of 1 mA, 5 mA, 10 mA, 15 mA and 20 mA were applied to the X‑ray tube. Results – There is no relationship between the response of the detector and the radiation energy. For energies below 33 keV there is an underestimation over 50% of the radiation dose measured but the detector presents a linear response for energies under 100 μSv. A dependency on the dose rate is perceived since as the dose rate increases, the response of the individual monitor decreases. There is a smaller decrease for the radiation qualities of N‑30 (1.1%), N‑40 (4.1%) and N‑120 (20.0%). Conclusion – It is concluded that there is a strong dependence of radiation energy and dose rate on the response of an electronic personal dosemeter.

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Introdução – No caso de uma eventual contaminação radioativa esta deve ser quantificada, pelo que é necessário garantir que as condições de funcionamento de um monitor de contaminação de superfícies se encontrem adequadamente caracterizadas, através da determinação da sua eficiência de deteção. Este estudo tem como objetivo determinar a eficiência de deteção de um monitor de contaminação e analisar a influência da distância e da atividade. Metodologia – O monitor de contaminação Thermo Mini 900E e as fontes radioativas planas de referência de Carbono – 14 (C-14), Césio – 137 (Cs-137), Estrôncio – 90 (Sr-90), Cloro – 36 (Cl-36) e Amerício – 241 (Am-241) com débito de emissão superficial rastreável ao Physikalish Technischen Bundesanstalt (PTB) foram utilizadas. Fontes de Sr-90 e C-14 com dois débitos de emissão distintos para cada e distâncias de 1 a 20mm foram usados para estudar a sua influência na eficiência de deteção. Resultados – Verificou-se que as fontes radioativas emissoras de partículas de maior energia apresentam uma maior eficiência de deteção e que esta diminui com o aumento da distância do detetor à fonte, sendo que os radioisótopos de maior energia apresentam um decréscimo na eficiência de 15% ao longo de 20mm, enquanto os radioisótopos de menor energia apresentam um decréscimo de 10%. Não se verificou uma influência expressiva do débito de emissão na eficiência de deteção deste monitor de contaminação. Conclusão – A eficiência de deteção de um monitor de contaminação portátil é dependente da distância deste à contaminação bem como do tipo de radiação emitida e energia dos radioisótopos presentes na contaminação. - ABSTRACT - Introduction – A radioactive contamination needs to be quantified in case it eventually occurs. Therefore it is necessary to ensure that the operating conditions of a surface contamination monitor are characterized by determining its detection efficiency. This experimental study aims to determine the detection efficiency of a contamination monitor and evaluate the distance and surface emission rate influence on the detection efficiency. Methodology – A contamination monitor Thermo Mini 900E was tested with reference radiation sources of Carbon – 14 (C-14), Cesium – 137 (Cs-137), Strontium – 90 (Sr-90), Chlorine – 36 (Cl-36) and Americium – 241 (Am-241) with its emission rate traced to the Physikalish Technischen Bundesanstalt (PTB). Sources of Sr-90 and C-14 with two different emission rates for each one and distances of 1 to 20mm were used to study its influence in the detection efficiency. Results – With the increasing of distance, the detection efficiency decreases. The most energetic radiation sources have higher detection efficiency, boasting a 15% decrease over 20mm whereas the sources bearing a smaller efficiency decrease 10%. No influence of the surface emission rate in the detection efficiency was verified. Conclusion – Thus, it is concluded that the detection efficiency of a contamination monitor is dependent of the distance between it and the contamination as well as the type and energy of the radioisotopes present in the contamination.

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O presente trabalho tem como objectivo avaliar economicamente e determinar a viabilidade da implementação de um reactor nuclear para produção de energia eléctrica. Faz-se uma abordagem a aspectos da energia nuclear no mundo e em particular a energia nuclear na união europeia, faz-se uma análise sobre a estrutura do sector nuclear em Espanha e o futuro da energia no mundo. É realizada uma análise sobre a energia nuclear em Portugal, são abordados aspectos como o planeamento energético, a localização da central nuclear, os recursos nacionais e internacionais, a inspecção e regulação nuclear e o impacto industrial. Por fim, faz-se uma análise sobre o mix energético português. Faz-se uma descrição do ciclo de combustível, isto é, um estudo a todas as fases pela qual o combustível nuclear passa desde a sua extracção, passando pela produção de energia e processamento dos resíduos. São descritos os principais componentes de uma central nuclear e o seu princípio de funcionamento. São analisados em detalhe os principais componentes de um reactor PWR (Objecto de estudo deste trabalho) e faz-se uma breve descrição de alguns modelos de reactores nucleares. É feita uma breve abordagem aos principais acidentes nucleares que ocorreram, e descrita a escala de ocorrências nucleares e as várias fases de desmantelamento de uma central. São apresentados os principais custos da central nuclear. Também é apresentado um estudo de viabilidade económica analisando três cenários diferentes e é apresentada uma análise de sensibilidade do VAL em função de algumas variáveis que têm grande influência na avaliação económica. São apresentadas as principais conclusões.

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A crucial method for investigating patients with coronary artery disease (CAD) is the calculation of the left ventricular ejection fraction (LVEF). It is, consequently, imperative to precisely estimate the value of LVEF--a process that can be done with myocardial perfusion scintigraphy. Therefore, the present study aimed to establish and compare the estimation performance of the quantitative parameters of the reconstruction methods filtered backprojection (FBP) and ordered-subset expectation maximization (OSEM). Methods: A beating-heart phantom with known values of end-diastolic volume, end-systolic volume, and LVEF was used. Quantitative gated SPECT/quantitative perfusion SPECT software was used to obtain these quantitative parameters in a semiautomatic mode. The Butterworth filter was used in FBP, with the cutoff frequencies between 0.2 and 0.8 cycles per pixel combined with the orders of 5, 10, 15, and 20. Sixty-three reconstructions were performed using 2, 4, 6, 8, 10, 12, and 16 OSEM subsets, combined with several iterations: 2, 4, 6, 8, 10, 12, 16, 32, and 64. Results: With FBP, the values of end-diastolic, end-systolic, and the stroke volumes rise as the cutoff frequency increases, whereas the value of LVEF diminishes. This same pattern is verified with the OSEM reconstruction. However, with OSEM there is a more precise estimation of the quantitative parameters, especially with the combinations 2 iterations × 10 subsets and 2 iterations × 12 subsets. Conclusion: The OSEM reconstruction presents better estimations of the quantitative parameters than does FBP. This study recommends the use of 2 iterations with 10 or 12 subsets for OSEM and a cutoff frequency of 0.5 cycles per pixel with the orders 5, 10, or 15 for FBP as the best estimations for the left ventricular volumes and ejection fraction quantification in myocardial perfusion scintigraphy.

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Mestrado em Medicina Nuclear. Área de especialização: Radiofarmácia.

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Copyright: © 2014 Rodrigues et al. This is an open-access article distributed under the terms of the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original author and source are credited.

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Aims: This paper aims to address some of the main possible applications of actual Nuclear Medicine Imaging techniques and methodologies in the specific context of Sports Medicine, namely in two critical systems: musculoskeletal and cardiovascular. Discussion: At the musculoskeletal level, bone scintigraphy techniques proved to be a mean of diagnosis of functional orientation and high sensibility compared with other morphological imaging techniques in the detection and temporal evaluation of pathological situations, for instance allowing the acquisition of information of great relevance in athletes with stress fractures. On the other hand, infection/inflammation studies might be of an important added value to characterize specific situations, early diagnose of potential critical issues – so giving opportunity to precise, complete and fast solutions – while allowing the evaluation and eventual optimization of training programs. At cardiovascular system level, Nuclear Medicine had proved to be crucial in differential diagnosis between cardiac hypertrophy secondary to physical activity (the so called "athlete's heart") and hypertrophic cardiomyopathy, in the diagnosis and prognosis of changes in cardiac function in athletes, as well as in direct - and non-invasive - in vivo visualization of sympathetic cardiac innervation, something that seems to take more and more importance nowadays, namely in order to try to avoid sudden death episodes at intense physical effort. Also the clinical application of Positron Emission Tomography (PET) has becoming more and more widely recognized as promising. Conclusions: It has been concluded that Nuclear Medicine can become an important application in Sports Medicine. Its well established capabilities to early detection of processes involving functional properties allied to its high sensibility and the actual technical possibilities (namely those related with hybrid imaging, that allows to add information provided by high resolution morphological imaging techniques, such as CT and/or MRI) make it a powerful diagnostic tool, claiming to be used on an each day higher range of clinical applications related with all levels of sport activities. Since the improvements at equipment characteristics and detection levels allows the use of smaller and smaller doses, so minimizing radiation exposure it is believed by the authors that the increase of the use of NM tools in the Sports Medicine area should be considered.

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Introduction: Image resizing is a normal feature incorporated into the Nuclear Medicine digital imaging. Upsampling is done by manufacturers to adequately fit more the acquired images on the display screen and it is applied when there is a need to increase - or decrease - the total number of pixels. This paper pretends to compare the “hqnx” and the “nxSaI” magnification algorithms with two interpolation algorithms – “nearest neighbor” and “bicubic interpolation” – in the image upsampling operations. Material and Methods: Three distinct Nuclear Medicine images were enlarged 2 and 4 times with the different digital image resizing algorithms (nearest neighbor, bicubic interpolation nxSaI and hqnx). To evaluate the pixel’s changes between the different output images, 3D whole image plot profiles and surface plots were used as an addition to the visual approach in the 4x upsampled images. Results: In the 2x enlarged images the visual differences were not so noteworthy. Although, it was clearly noticed that bicubic interpolation presented the best results. In the 4x enlarged images the differences were significant, with the bicubic interpolated images presenting the best results. Hqnx resized images presented better quality than 4xSaI and nearest neighbor interpolated images, however, its intense “halo effect” affects greatly the definition and boundaries of the image contents. Conclusion: The hqnx and the nxSaI algorithms were designed for images with clear edges and so its use in Nuclear Medicine images is obviously inadequate. Bicubic interpolation seems, from the algorithms studied, the most suitable and its each day wider applications seem to show it, being assumed as a multi-image type efficient algorithm.