Desenvolvimento de um protocolo de dosimetria para o tratamento de total skin irradiation (TSI)

A técnica radioterápica Total Skin Irradiation (TSI), utilizada para tratamento de Micose Fungóide e doenças similares, apresenta grande complexidade na sua dosimetria e implementação nos Serviços de Radioterapia. No SUS – Sistema Único de Saúde - do Brasil, só há esse tratamento no Serviço de Radioterapia do Hospital das Clínicas da UNICAMP (Campinas) e no Instituto Nacional do Câncer (INCA) (Rio de Janeiro). O objetivo deste trabalho é o estudo e o desenvolvimento de um protocolo de controle de qualidade e dosimetria a ser implementado na técnica utilizada no Serviço de Radioterapia do Hospital de Clínicas da Universidade Estadual de Campinas (HC - UNICAMP). Todos os estudos e análises para a elaboração do protocolo foram baseados no Report 23[1] da AAPM – American Association of Physicists in Medicine - e no TRS-398[3] da IAEA – International Atomic Energy Agency. A metodologia e os resultados obtidos apresentam-se descritos neste relatório

Avaliação da dose de radiação: angiotomografia coronariana - métodos retrospectivo e prospectivo

The aim of this study was to evaluate the effective dose received by patients undergoing CCTA in both acquisition methods in the period June 1st to October 30th, 2013. Data collection was performed at the Clínica Sabedotti in Ponta Grossa/PR, with General Electric Equipment VCT XT, 64 detections lines. The effective dose was measured from the thirty cases randomly selected of Picture Archival and Communication System – PACS, reported by Dose Lenght Product (DLP) equipment for each examination and the conversion factor (EDLP) set by the European Commission for cardiac region (EDLP = 0.014). The results showed significant differences in radiation dose delivered to the patient according to the employee acquisition method, Retrospective or Prospective of ECG.

Utilização do mapa espacial de radiação e dose acumulada como ferramenta para otimização de doses em pacientes e trabalhadores nas clínicas de medicina nuclear

This study has as general aim to propose a spatial map of doses as an auxiliary tool in assessing the need for optimization of the workplace in nuclear medicine services. As specific aims, we assessed the workers individual dosimetry; we analyzed the facilities of the nuclear medicine services; and we evaluated environment exposure rates. The research is characterized as a case study, with an exploratory and explanatory nature. It was conducted in three Nuclear Medicine Services, all established in the Northwest of the Paraná State. Results indicated that the evaluated dose rates and workers dosimetry, in all the dependencies of the surveyed services, are within the limits of annual doses. However some exceeded the limits recommended in the standard CNEN-NN 3:01 (2014). It was concluded that the spatial map dose is an important tool for nuclear medicine services because it facilitates the visualization of areas with highest concentration of radiation, and also helps in the constant review of these measures and resources, aiding in the identification of any failures and shortcomings, providing resources to correct any issues and prevent their repetition. The spatial map dose is also important for the regular inspection, evaluating if the radiation protection objectives are being met.

Exposição à radiação em exames de corpo inteiro de 18F-FDG PET-TC

O sistema de PET-TC resulta da combinação de duas modalidades de imagem médica: a Tomografia Computorizada (TC), que permite obter imagens anatómicas precisas, e a Tomografia por Emissão de Positrões (PET), que oferece imagens moleculares do corpo humano. Num exame hibrido de PET-TC, para além da exposição interna, o doente é também submetido a uma exposição externa devida à irradiação do mesmo por uma fonte externa, referente à aquisição dos dados de TC. Como tal, o exame de PET-TC tem associado um aumento da exposição para o doente [Huang, 2009], pelo que normalmente os scans de TC são adquiridos com baixa dose [Nunes,2011]. Pretende-se com este trabalho, estabelecer um método capaz de estimar a dose efetiva em exames de corpo inteiro de 18F-FDG PET-TC, uma vez que existem diversos métodos para realizar análise dosimétrica dos exames individuais de PET e de TC, e comparar os valores obtidos com os valores utilizados em outros países. Foram recolhidos dados de 24 pacientes que efetuaram exames de corpo inteiro de PET-TC com 18F-FDG no ICNAS, por questões de saúde e por necessidade própria, com o intuito de estimar a dose efetiva associada a esses exames. Para estimar a dose efetiva referente ao exame de TC recorreu-se ao valor de DLP, fornecido pelo equipamento de TC com controlo de qualidade em dia, e ao método dos coeficicientes de dose efetiva normalizados, proposto pela CE, obtendo-se um valor de dose de 4.75 mSv. A dose efetiva do exame de PET foi calculada com base nos valores da atividade no momento de aquisição das imagens e em coeficientes de dose para a PET, obtendo-se um valor de dose de 4.77 mSv. Concluiu-se que para os pacientes sujeitos ao exame de corpo inteiro de 18F-FDG PET-TC, foi registado um valor de dose de 9.47 mSv de dose efetiva. Este valor de dose efetiva para os exames de PET-TC é significativamente mais baixo comparativamente aos valores registados em vários estudos internacionais (13.65 mSv, 14.3 mSv, 18.85 mSv, 24.8 mSv, 25 mSv, 32.18 mSv), dos quais apenas no estudo de Brix um dos hospitais estudados regista um valor ligeiramente inferior, de 8.5 mSv. Com este estudo foi possível determinar o valor de exposição à radiação a que os pacientes do ICNAS se encontram sujeitos em exames de corpo inteiro de 18F-FDG PET-TC considerando as duas modalidades de imagem médica.

Estudo das propriedades dosimétricas de polímeros conjugados

Conselho Nacional de Desenvolvimento Científico e Tecnológico (CNPq)

Estudo de propriedades dosimétricas utilizando polímero organometálico em solução

Coordenação de Aperfeiçoamento de Pessoal de Nível Superior (CAPES)

Coleta de dados, modelagem e controle de qualidade do sistema de planejamento pinnacle3

Qualidade na coleta de dados do feixe de radiação, modelagem por meio do sistema de planejamento de tratamento (SPT) e controle da qualidade do processo envolvido são cruciais à fidedignidade do serviço de radioterapia de forma a contribuir à eficácia do tratamento e segurança do principal ente envolvido no final de toda essa sistemática, o paciente. Para isso foi proposto nesse presente trabalho a coleta de dados do feixe de raios-x de 6MV seguido da introdução desses dados ao SPT para processo de modelagem computacional que teve agregado, a todo esses processos, o controle da qualidade segundo critérios de aceitação

Sistema de Acelerador Linear Comercial para Radioterapia

This paper presents a study about the operation of the major system’s components of a linear particle acclerator (Linac). It addresses the components mainly responsible for the formation of the beam, through the inclusion of several block diagrams showing the details of the structure. Among the systems discussed may be mentioned the system modulator, automatic frequency control, dosimetry and auxiliary systems. The main objective is the dissemination of basic technology applied in linear accelerators and create literature about this subject in national language. Despite the high complexity and large number of devices that comprise a linear accelerator, it has been developed an easy to understand text that adresses the most relevant issues to the operation of the linear accelerator from the point of view of electrical engineering

Distribuição e dispersão dos níveis radiométricos do setor técnico de medicina nuclear do hospital das clínicas da faculdade de medicina de botucatu

Nuclear medicine uses non-sealed sources for exams and treatments, because the movement of these sources, source of patients injected or not, involve a wide range of environmental radiometric levels. To better control of these levels this study was aimed at monitoring points strategically distributed in all environments Sector Technical Nuclear Medicine, Hospital of the Botucatu Medical School, performing two measurements at random times daily for a period of three months, sampling the normal routine of the sector. The detector Geiger-Muller was used for the acquisition of exposure rates of the points, efficiency and reprodutibility test have shown good performance of this equipment for this purpose. The results allowed to make a projection of annual dose for each environment indicating higher risks for Occupationally Exposed Individuals as well as Public Individuals compared with the limits established by the National Commission of Nuclear Energy. Was developed a spatial map of dose that can be used as a visual warning to the regions with the highest exposure to ionizing radiation, enabling reduced risk of a potential exposure

Análise de algoritmos computacionais utilizados em sistemas de planejamento de braquiterapia de alta taxa de dose: estudo comparativo com o Código MCNP-5C

In radiotherapy, computational systems are used for radiation dose determination in the treatment’s volume and radiometric parameters quality analysis of equipment and field irradiated. Due to the increasing technological advancement, several research has been performed in brachytherapy for different computational algorithms development which may be incorporated to treatment planning systems, providing greater accuracy and confidence in the dose calculation. Informatics and information technology fields undergo constant updating and refinement, allowing the use Monte Carlo Method to simulate brachytherapy source dose distribution. The methodology formalization employed to dosimetric analysis is based mainly in the American Association of Physicists in Medicine (AAPM) studies, by Task Group nº 43 (TG-43) and protocols aimed at dosimetry of these radiation sources types. This work aims to analyze the feasibility of using the MCNP-5C (Monte Carlo N-Particle) code to obtain radiometric parameters of brachytherapy sources and so to study the radiation dose variation in the treatment planning. Simulations were performed for the radiation dose variation in the source plan and determined the dosimetric parameters required by TG-43 formalism for the characterization of the two high dose rate iridium-192 sources. The calculated values were compared with the presents in the literature, which were obtained with different Monte Carlo simulations codes. The results showed excellent consistency with the compared codes, enhancing MCNP-5C code the capacity and viability in the sources dosimetry employed in HDR brachytherapy. The method employed may suggest a possible incorporation of this code in the treatment planning systems provided by manufactures together with the equipment, since besides reducing acquisition cost, it can also make the used computational routines more comprehensive, facilitating the brachytherapy ...

Preparo (calibração e tratamento) de Dosímetros Termoluminescetes de Flureto de Lítio (TLD-LiF)

A Dosímetria Termoluminescente (TLD) é uma ferramenta extremamente versátil para a avaliação da dose absorvida por tecidos humanos, devido à interação dos mesmos com a radiação ionizante. As características termoluminescentes (TL) do fluoreto de lítio (LiF) foram estudadas extensivamente primeiramente por apresentar número atômico muito próximo ao do tecido humano e, portanto, conseguir quantificar com fidelidade a radiação recebida na ordem de μGy (micro Gray) a kGy (kilo Gray) . Foram abordados os princípios físicos envolvido no procedimento de calibração e tratamento dos dosímetros (total de 224 pastilhas), os quais foram separados, após tratamento, em 75 grupos. Este trabalho foi de suma importância na aplicação dos conceitos físicos abordados durante a formação da graduação no curso de Bacharelado em Física Médica, e pode auxiliar em projetos, em andamento, junto ao grupo de pesquisa de Física Aplicada ao Radiodiagnóstico

Avaliação teórico-experimental da distribuição de dose absorvida em radioterapia em tumores de pele

O trabalho propõe rotinas computacionais usando o Método de Monte Carlo com o Código MCNP-5, para analisar os perfis de dose de radiação liberada nos tratamentos de tumores de pele e otimizar os cálculos radiométricos dos feixes de radiação estudados. Foram realizadas medidas dosimétricas do feixe de radiação, comparando os resultados obtidos com os respectivos valores fornecidos pelo serviço de física médica das instituições, com resultados informados pelo fabricante do equipamento e com as simulações computacionais efetuadas com o Código MCNP-5. A quantificação dos erros relativos percentual entre os resultados simulados e os fornecidos pelo Serviço de Radioterapia (E1), os informados pelo fabricante (E2) e os medidos experimentalmente (E3) são inferiores a 4,0% e validam a metodologia computacional proposta para avaliação do comportamento do feixe de raios-X superficial e do feixe de raios γ da unidade de Cobaltoterapia. A metodologia de análise do espectro energético e da curva de porcentagem de dose profunda (PDP) desenvolvida neste trabalho pode ser estendida para estudos de outros feixes clínicos e subsidiar os dados radiométricos utilizados nos planejamentos e cálculos de dose realizados pelo profissional da física médica na sua rotina nos Serviços de Radioterapia

Radioterapia em câncer de mama: importância da determinação da curva de isodose

The study analyzed contours of the thoracic region of patients undergoing radiotherapy of breast tumors in Hospital Manuel de Abreu of Bauru (institution 1) and the Hospital da Faculdade de Medicina of Botucatu (Institution 2). Were prepared isodose curves corresponding to the contours of the patient, which were presented for radiotherapists doctors both hospital services that enabled the choice of the curve isodose that provides the best distribution of radiation dose in the irradiated volume. Some boundaries were digitized in one institution and sent for preparation of isodose lines in the institution 2, both curves plotted in each of the institutions and for the same contour, were compared, showing that the methodology of Curves of distance is feasible and reliable, while optimizing the routine procedures regarding the handling of isodose plans provided by different radiation equipment. It compares the calculation of the exposure time determined using the isodose curve selected by calculating the value obtained considering the PDP at the point of the middle line of separation between the internal and external fields, the difference between the two methods for determining exposure time was around 2.4%. A study on the angle of the radiation beam at the input field (region breast-air) was conducted showing that, once known a tangent angle of the input beam, one can estimate the angle of the wedge filter used in some procedures for uniformity of dose within the irradiated volume compensation and the lack of tissue in the treatment volume. A comparative study between the isodose curves produced manually with the curves obtained in a two-dimensional computer system, the computer system showed that provides further information regarding the dose gradient within the irradiated volume, in addition to reducing the time spent in preparing the curves isodose

Análise quantitativa dos parâmetros físicos e radiométricos de procedimetnos radioterapicos em tumores de mama

The paper presents the radiometric parameters determined by the medical physicist during routine radiotherapy planning service in cases of breast cancer . The contours of the breast volume in patients undergoing radiation breast tumors at the Hospital das Clinicas, Faculty of Medicine , UNESP, Botucatu ( HCFMB ) during the year 2012 were analyzed . In order to analyze the influence of physical and radiometric parameters for the determination of the dose distribution of irradiated breast volume , four measurements of isodose curves were prepared in four different heights breast , and compared with the isodose curves plotted computationally . In the routine of planning , the medical physicist must determine the isodose curve that gives the best dose distribution homogeneity in the irradiated volume . The choice of the treatment plan can be done by dedicated computer systems , which require significantly costly investments available services having better financial support . In the Service of Medical Physics , Department of Radiotherapy , HC FMB , we use a two-dimensional software for determination of isodose curves , however , this software is out of date and frequently becomes inoperable due to the lack of maintenance and it is a closed system without feasibility of interference from computer professionals . This fact requires manual preparation of isodose curves , which are subject to uncertainties due to the subjectivity in the clinical interpretation of medical radiation oncologist and medical physicist responsible for planning , plus dispendiar significant calculation time . The choice of the optimal isodose curve depends on the energy of the radiation beam , the geometry and dimensions of the irradiated area . The contours of the breast studied in this work evaluations showed that , for a given energy input , such as the energy of 1.25 MeV of gamma radiation Unit Telecobaltoterapia , the determination of the percentage depth dose ( PDP ) ...

Mapeamento do nível radiométrico e construção de mapa espacial em serviço de medicina nuclear

Nuclear Medicine is a medical modality of therapy and diagnostic imaging using unsealed radioactive sources for its purposes. This routine activity promotes the transit of radioactive sources for the area of installation, beyond the transit of patients injected with radioisotope, which also contribute to raising the radiometric level of environment. As a consequence, it has exposured workers and public individuals to the ionizing radiation. There are protective mechanisms of radiation exposure, personal protective equipments, and measurement planes established in standard measurement at certain points of the environment in order to identify any increase in radiometric levels and \ or contamination, but do not cover the entire space occupied by workers and patients. To accomplish with the individual dose limits established by the National Commission of Nuclear Energy, it is interesting if there is an individualized classification for each Nuclear Medicine service. This work aimed to promote an analysis of the radiometric level distribution across the extent of the Technical Nuclear Medicine Sector of Hospital of the Botucatu Medical School, and produce a spatial map to identify locations with higher exposure rate to the ionizing radiation, can be used as a risk map to assist the Occupationally Exposed Individuals (IOE). To perform the radiometric levels checking it was used a digital Geiger-Muller detector available in the sector, due to its practicality compared to other detectors. Measurements were carried out at four different times for all days of the week, at points strategically established to cover all the installation