56 resultados para Radiology, nuclear medicine
em Repositório Científico do Instituto Politécnico de Lisboa - Portugal
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Introduction - European nuclear medicine technologists education is delivered by Higher Education Institutions and students obtain a grade of Bachelor of Sciences (BSc), during which they are initiated to research during their studies. Once BSc nuclear medicine technologists are in professional practice, they have very few opportunities to develop a real research experience and they rather become passive users than active contributors the growth of scientific knowledge in nuclear medicine. Aim - To describe and discuss an innovative educational and professional experience aimed in strengthen research knowledge, skills and competencies of former nuclear medicine technologists student in the context of an international mobility stay.
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Purpose - The education and training of a nuclear medicine technologist (NMT) is not homogeneous among European countries, which leads to different scope of practices and, therefore, different technical skills are assigned. The goal of this research was to characterize the education and training of NMT in Europe. Materials and methods - This study was based on a literature research to characterize the education and training of NMT and support the historical evolution of this profession. It was divided into two different phases: the first phase included analysis of scientific articles and the second phase included research of curricula that allow health professionals to work as NMT in Europe. Results - The majority of the countries [N=31 (89%)] offer the NMT curriculum integrated into the high education system and only in four (11%) countries the education is provided by professional schools. The duration in each education system is not equal, varying in professional schools (2-3 years) and high education level system (2-4 years), which means that different European Credit Transfer and Accumulation System, such as 240, 230, 222, 210 or 180 European Credit Transfer and Accumulation System, are attributed to the graduates. The professional title and scope of the practice of NMT are different in different countries in Europe. In most countries of Europe, nuclear medicine training is not specific and curriculum does not demonstrate the Nuclear Medicine competencies performed in clinical practice. Conclusion - The heterogeneity in education and training for NMT is an issue prevalent among European countries. For NMT professional development, there is a huge need to formalize and unify educational and training programmes in Europe.
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The DatScanTM and its Semiquantification (SQ) can provide advantages in the diagnosis of Parkinsonian Syndromes (PS). To improve the SQ is recommended the creation of adapted database (DB) with reference values for the Nuclear Medicine Departments. Previously to this work was created a adapted database (DBRV) to Nuclear Medicine Department's protocol and population of Infanta Cristina's Hospital located in Badajoz, for patients between the ages of 60 and 75, and reference values of the SQ were calculated. Aim: To evaluate the discrimination capacity of a department's adapted DB reference's values of healthy controls for DatScanTM.
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Semi quantification (SQ) in DaTScan studies is broadly used in clinic daily basis, however there is a suspicious about its discriminative capability, and concordance with the diagnostic classification performed by the physician. Aim: Evaluate the discriminate capability of an adapted database and reference's values of healthy controls for the Dopamine Transporters (DAT) with 123IFP-IT named DBRV adapted to Nuclear Medicine Department's protocol and population of Infanta Cristina's Hospital, and its concordance with the physician classification.
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Medical imaging is a powerful diagnostic tool. Consequently, the number of medical images taken has increased vastly over the past few decades. The most common medical imaging techniques use X-radiation as the primary investigative tool. The main limitation of using X-radiation is associated with the risk of developing cancers. Alongside this, technology has advanced and more centres now use CT scanners; these can incur significant radiation burdens compared with traditional X-ray imaging systems. The net effect is that the population radiation burden is rising steadily. Risk arising from X-radiation for diagnostic medical purposes needs minimising and one way to achieve this is through reducing radiation dose whilst optimising image quality. All ages are affected by risk from X-radiation however the increasing population age highlights the elderly as a new group that may require consideration. Of greatest concern are paediatric patients: firstly they are more sensitive to radiation; secondly their younger age means that the potential detriment to this group is greater. Containment of radiation exposure falls to a number of professionals within medical fields, from those who request imaging to those who produce the image. These staff are supported in their radiation protection role by engineers, physicists and technicians. It is important to realise that radiation protection is currently a major European focus of interest and minimum competence levels in radiation protection for radiographers have been defined through the integrated activities of the EU consortium called MEDRAPET. The outcomes of this project have been used by the European Federation of Radiographer Societies to describe the European Qualifications Framework levels for radiographers in radiation protection. Though variations exist between European countries radiographers and nuclear medicine technologists are normally the professional groups who are responsible for exposing screening populations and patients to X-radiation. As part of their training they learn fundamental principles of radiation protection and theoretical and practical approaches to dose minimisation. However dose minimisation is complex it is not simply about reducing X-radiation without taking into account major contextual factors. These factors relate to the real world of clinical imaging and include the need to measure clinical image quality and lesion visibility when applying X-radiation dose reduction strategies. This requires the use of validated psychological and physics techniques to measure clinical image quality and lesion perceptibility.
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Mestrado em Medicina Nuclear. rea de especializao: Radiofarmcia.
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In 2012 we were awarded an Erasmus Intensive Programme grant to facilitate OPTIMAX 2013, a three week duration residential summer school held within the UK during August 2013. The summer school helped to further develop student radiographer skills in optimising x-radiation dose and image quality. With a major emphasis on visual techniques to determine image quality, lesion visibility, lesion detection performance and physical measures of image quality (eg signal to noise ratio (SNR)) we conducted controlled laboratory experiments on phantoms using Computed Radiography, CT and Full Field Digital Mammography. Mathematical modelling was used for radiation dose estimation. Sixty seven people from 5 European countries participated. This included 49 PhD, MSc and BSc students. Discipline areas included radiography, physics, biomedical science and nuclear medicine.
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Mestrado em Gesto e Avaliao de Tecnologias em Sade
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Renal scintigraphy with 99mTc-dimercaptosuccinic acid (99mTc-DMSA) is performed with the aim of detect cortical abnormalities related to urinary tract infection and accurately quantify relative renal function (RRF). For this quantitative assessment Nuclear Medicine Technologist should draw regions of interest (ROI) around each kidney (KROI) and peri-renal background (BKG) ROI, although, controversy still exists about BKG-ROI. The aim of this work was to evaluate the effect of the normalization procedure, number and location of BKG-ROI on the RRF in 99mTc-DMSA scintigraphy.
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Introduo A monitorizao da exposio ocupacional a doses de radiao ionizante pode ser complementada por dosmetros eletrnicos individuais que permitem uma leitura direta da dose de radiao recebida. Dada a dependncia energtica e de dbito de dose j reportada para estes dosmetros, este trabalho pretende determinar a linearidade da resposta de um dosmetro eletrnico individual e estudar o comportamento da sua resposta em funo da energia de radiao e do dbito de dose. Metodologia Para estudar a dependncia da energia da radiao do dosmetro eletrnico pessoal Vertec Bleeper Sv procedeuse sua irradiao com um equivalente de dose individual, Hp(10), de 500 Sv de radiao gama do Cobalto 60 (60C) e Csio 137 (137Cs) e das qualidades de radiao X da srie Narrow (N): N30, N40, N60, N80, N100 e N120. Para investigar a dependncia da resposta em funo do dbito de dose aplicaramse ampola de raios X as intensidades de corrente eltrica de 1 mA, 5 mA, 10 mA, 15 mA e 20 mA. Resultados No existe uma relao entre a resposta do detetor e a energia de radiao a que este exposto. Ocorre uma subestimao 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 Sv. Tambm se constata que, medida que o dbito de dose aumenta, existe uma diminuio na resposta do dosmetro. O menor decrscimo na resposta deste dosmetro eletrnico individual dse para as qualidades de radiao N30 (1,1%), N40 (4,1%) e N120 (20,0%). Concluso Verificase que a resposta do dosmetro individual Vertec Bleeper Sv depende fortemente da energia da radiao e do dbito 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 Sv from the radionuclides Cobalt 60 (60C) and Cesium 137 (137Cs) as well as by the radiation qualities of the Narrow (N) series: N30, N40, N60, N80, N100 e N120. 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 Xray 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 Sv. 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 N30 (1.1%), N40 (4.1%) and N120 (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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The rapid growth in genetics and molecular biology combined with the development of techniques for genetically engineering small animals has led to increased interest in in vivo small animal imaging. Small animal imaging has been applied frequently to the imaging of small animals (mice and rats), which are ubiquitous in modeling human diseases and testing treatments. The use of PET in small animals allows the use of subjects as their own control, reducing the interanimal variability. This allows performing longitudinal studies on the same animal and improves the accuracy of biological models. However, small animal PET still suffers from several limitations. The amounts of radiotracers needed, limited scanner sensitivity, image resolution and image quantification issues, all could clearly benefit from additional research. Because nuclear medicine imaging deals with radioactive decay, the emission of radiation energy through photons and particles alongside with the detection of these quanta and particles in different materials make Monte Carlo method an important simulation tool in both nuclear medicine research and clinical practice. In order to optimize the quantitative use of PET in clinical practice, data- and image-processing methods are also a field of intense interest and development. The evaluation of such methods often relies on the use of simulated data and images since these offer control of the ground truth. Monte Carlo simulations are widely used for PET simulation since they take into account all the random processes involved in PET imaging, from the emission of the positron to the detection of the photons by the detectors. Simulation techniques have become an importance and indispensable complement to a wide range of problems that could not be addressed by experimental or analytical approaches.
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Mestrado em Radiaes Aplicadas s Tecnologias da Sade. rea de especializao: Proteco contra Radiaes
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Introduo No caso de uma eventual contaminao radioativa esta deve ser quantificada, pelo que necessrio garantir que as condies de funcionamento de um monitor de contaminao de superfcies se encontrem adequadamente caracterizadas, atravs da determinao da sua eficincia de deteo. Este estudo tem como objetivo determinar a eficincia de deteo de um monitor de contaminao e analisar a influncia da distncia e da atividade. Metodologia O monitor de contaminao Thermo Mini 900E e as fontes radioativas planas de referncia de Carbono 14 (C-14), Csio 137 (Cs-137), Estrncio 90 (Sr-90), Cloro 36 (Cl-36) e Amercio 241 (Am-241) com dbito de emisso superficial rastrevel ao Physikalish Technischen Bundesanstalt (PTB) foram utilizadas. Fontes de Sr-90 e C-14 com dois dbitos de emisso distintos para cada e distncias de 1 a 20mm foram usados para estudar a sua influncia na eficincia de deteo. Resultados Verificou-se que as fontes radioativas emissoras de partculas de maior energia apresentam uma maior eficincia de deteo e que esta diminui com o aumento da distncia do detetor fonte, sendo que os radioistopos de maior energia apresentam um decrscimo na eficincia de 15% ao longo de 20mm, enquanto os radioistopos de menor energia apresentam um decrscimo de 10%. No se verificou uma influncia expressiva do dbito de emisso na eficincia de deteo deste monitor de contaminao. Concluso A eficincia de deteo de um monitor de contaminao porttil dependente da distncia deste contaminao bem como do tipo de radiao emitida e energia dos radioistopos presentes na contaminao. - 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.
Anlogos do neuropptido Y marcados com 99mTc para deteco de receptores Y1 expressos no cancro da mama
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Mestrado em Medicina Nuclear. rea de especializao: Radiofarmcia.
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Mestrado em Medicina Nuclear.
