Estudo teórico da contribuição à dose de partículas secundárias geradas por prótons de energias entre 100 e 200 MeV num Phantom de substituto de tecido MS20

The goal of this project is the reproduction, through the simulation code based on the MCNPX (Monte Carlo N-Particle eXtended) v2.50 method, of the proton beam interaction with the material, since, in proton therapy, only the particle ionization and excitation are analyzed and the occurence of nuclear interactive inelastic process are not considered. This work will help the development of studies concerning the contribution to the total dosis of secondary particles generated by nuclear interaction in proton therapy. They are: alpha particles ( ), deuterium(2H), tritium (3H), neutron (n) and helium (3He). A MS20 tissue substitute phantom was used as the target and the energy of the proton beams was within an interest range of 100 to 200MeV. With the results obtained, it was possible to generate graphics which allows the analysis of the dosis deposition relation with and without nuclear interaction, the percentage of secondary particles deposited dosis, the radial dispersion of neutrons in the material, the secondary particles multiplicity, as well as the relation between the secondary particles spectrum with the próton generated spectrum

Análise da viabilidade de simulações com feixes de prótons de 150MeV em alvos heterogêneos

A protonterapia é um tipo de tratamento promissor quanto a diminuição de dose nos tecidos adjacentes ao tumor, devido às suas característica de deposição de energia ao interagir com a matéria. Para aumentar a acurácia do tratamento é necessário que as simulações sejam feitas a partir de um sistema de formação de imagem que utilize também um feixe de prótons, como a tomografia por feixe de prótons (pCT). Essa área atualmente está em desenvolvimento e se defronta com inúmeros problemas na formação de uma imagem precisa. Este trabalho tem o intuito de analisar a viabilidade de simulações computacionais para este tipo de feixe. O código computacional SRIM é um conjunto de programas que calcula o freamento e o alcance de íons ao interagir com a matéria. Esse cálculo baseia-se em ferramentas oriundas da mecânica quântica e também no método de Monte Carlo, para determinar, de modo probabilístico, trajetórias, colisões e ângulos. Foram realizadas simulações no programa SRIM para um alvo heterogêneo envolvendo água e osso cortical. Para analisar o comportamento do feixe transmitido, foram feitas alterações na posição e no tamanho da heterogeneidade. A partir dos dados obtidos pode-se obter valores médios, histogramas e gaussianas dos mesmos para cada simulação e tirar conclusões sobre a viabilidade e as dependências desse tipo de simulação

Estudo teórico das funções de anisotropia e radial de dose para braquiterapia com semente de Ir192 em diferentes materiais de interesse em radiologia

The brachytherapy braquiterapia is an x-ray modality radiotherapy in which stamped or halfstamped radioactive sources in format of seeds are used, wires or to one short distance, in contact or implanted to the fabric to be treated. All the treatment modalities require a previous planning.The formalism recommended for calculation of dose was considered by the AAPM for the first TG-43 Report. In it distributions of dose of isolated seeds measured and calculated by Monte Carlo method in water instead of with models half-empiricists.In this work we in accordance with present some preliminary results of the calculation of functions of radial anisotropy and of dose in the distance for seed of 192Ir, wide used in brachytherapy treatments of high tax of dose (HDR), with the aid of the program based on the Monte Carlo method MCNPX v2.50 (Mount Carlo N ParticleeXtended).The materials chosen in the simulation beyond water, had been MS20 and estriado muscle

Estudo da contribuição do espalhamento nuclear não elástico de prótons na dose depositada em alvos com composição homogênea

Due the differences between interaction physics process with matter for protons and photons, the proton beam tomography (pCT) has some vantages to comparison with conventional tomography. Also it is confirmed that usually pCT has better dose distribution and highest contrast resolution. The pCT allow not only view the internal structure of an object without destroying it, but also directly measure of volume density of electrons. Also it is confirmed that usually pCT has better dose distribution and highest contrast resolution. At the same time, there are many scientific and technical aspects to a detailed study: the capacity and limitations of the pCT methods are not well clarified. Through computations, based on Monte Carlo Method was carried out a detailed study of the contribution of non-elastic nuclear spreading, and together was compared with an analytical model for the deflection angle and the lateral deflection of protons in the target volume. The programs used were SRIM 2006 code and MCNPX v.2.50 code

Estudo teórico da contribuição a dose de partículas secundárias geradas por prótons de energias entre 100-200 MeV num phantom de músculo estriado

In the treatment plans in conventional Proton therapy are considered only the elastic interactions of protons with electrons and/or nuclei, it means, mainly ionization and coulomb excitation processes. As the energy needed to reach the deep tumors should be of several hundred of MeVs, certainly the nuclear inelastic channels are open. Only some previous studies of the contribution of these processes in the full dose have been made towards targets composed of water. In this study will be presented the results of the simulation of the processes of interaction of beams of protons in the range of 100-200 MeV of energy with a cylindrical phantom composed by striated muscle (ICRU), emphasizing in the contribution to total dose due to the deposition of energy by secondary particles alpha (α), deuterium (2H), tritium (3H), neutron (n) and hélio3 (3He), originated by nuclear inelastic processes. The simulations were performed by using the method of Monte Carlo, via the computer code MCNPX v2.50 (Monte Carlo N-Particle eXtended). The results will be shown demonstrated through the graphics of the deposited dose with or without nuclear interaction, the percentual of dose deposited by secondary particles, the radial dispersion of neutrons, as well as the multiplicity of secondary particles

Estudo teórico da contribuição à dose de partículas secundárias geradas por Prótons de energias entre 100 e 200 MeV num Phantom de osso cortical

In proton therapy, the deposition of secondary particles energy originated by nuclear inelastic process (n, 2H, 3H, 3He and α) has a contribution in the total dose that deserves to be discussed. In calculations of plans implemented for routine treatment, the paid dose is calculated whereas the proton loses energy by ionization and or coulomb excitement. The contribution of inelastic processes associated with nuclear reactions is not considered. There are only estimates for pure materials or simple composition (water, for example), because of the difficulty of processing targets consisting of different materials. For this project, we use the Monte Carlo method employing the code MCNPX v2.50 (Monte Carlo N-Particle eXtended) to present results of the contribution to the total dose of secondary particles. In this work, it was implemented a cylindrical phantom composed by cortical bone, for proton beams between 100 and 200 MeV. With the results obtained, it was possible to generate graphics to analyze: the dose deposition relation with and without nuclear interaction, the multiplicity and percentage of deposited dose for each secondary particle and a radial dispersion of neutrons in the material

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 ...

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

Estudo teórico da contribuição do espalhamento nuclear não elástico na trajetória de prótons de energias entre 50 e 250 MeV em materiais de interesse em radiologia: aplicação em tomografia com prótons

The goal of this work is to study the process of interaction of protons with matter through Monte Carlo simulation. For this purpose, it was employed the SRIM program (Stopping and Range of Ions in Matter ) and MCNPX (Monte Carlo N-Particle eXtended) v2.50. This work is going to support the development of a tomography system with protons. It was studied the interaction of proton with the follow materials: Polimethyl Mehacralate (PMMA), MS20 Tissue Substitute and water. This work employed energies in range of 50 MeV and 250 MeV, that is the range of clinical interest. The energy loss of proton after cross a material layer, the decreasing of its intensity, the angular and lateral de ection of incident beam, including and excluding nuclear interactions. This work is related with Medical Physics and Material Physics, like interaction of radiation with matter, particle transport phenomena, and the experimental methods in Nuclear Physics like simulation and computational by Monte Carlo method

Calibração do Modelo de TBC para cálculos de espectros de raios-X

As normas nacionais e internacionais prevêem que a manutenção dos níveis de radiação deve estar abaixo do permitido. Sendo assim, a ICRP [1] (International Commission on Radiological Protection) exige métodos de otimização para garantir que o público esteja exposto aos menores níveis de radiação possíveis. Como método de otimização, aproximações teóricas e semi-empiricas podem realizar uma determinação do espectro de raios-X, sendo fundamental para o diagnóstico de energia, estimando a dose de radiações em pacientes e formulando modelos de blindagem. Métodos adequados de radioproteção foram desenvolvidos na física médica como a medicina nuclear, a radioterapia e a radiologia diagnóstica. Um dos métodos semi-empiricos utilizados é o modelo de TBC que é capaz de reproduzir e calcular os espectros gerados pelo anodo de tungstênio. Com o modelo de TBC modificado é possível também obedecer às exigências das barreiras protetoras presentes na radiologia, levando em conta a forma de onda arbitrária e a filtração adicional na geração do espectro não presente no modelo original. Além disso, realiza-se a calibração do espectro gerado para que o modelo de TBC represente a quantidade e comportamento de radiações típicas. Dessa forma, realiza-se uma revisão do modelo de TBC implementando-o ao programa matemático Matlab e comparando-o com os resultados adquiridos pelo Código MCNP-5 no Método de Monte Carlo. Os resultados encontrados são bastante satisfatórios, tanto em termos quantitativos quanto qualitativos dos feixes. Para a calibração, desenvolve-se uma análise dos espectros gerados pelo TBC Modificado aplicado ao programa Mathcad e Matlab sob as mesmas condições. Os espectros gerados apresentam o mesmo comportamento, diferindo em até 12% nos valores encontrados para camadas semi-redutoras, coeficiente de homogeneidade e energia efetiva

Produção de partículas secundárias em reações de “spallation” induzidas por prótons

Cosmic radiation has been identi ed as one of the main hazard to crew, aircraft and sensitive equipments involved in long-term missions and even high-altitude commercial ights. Generally, shields are used in spatial units to avoid excessive exposure, by holding the incident radiation. Unfortunatelly, shielding in space is problematic, especially when high-energy cosmic particles are considered, due to the production of large number of secondary particles, mainly neutrons, protons and alpha particles, caused by spallation reactions and quasi-elastic processes of the corpuscular radiation with the shield. Good parameters for checking the secondary particle production at target material are diferential cross section and energy deposited in the shield. Addition experiments, some computer codes based on Monte Carlo method show themselves a suitable tool to calculate shield parameters, due to have evaluated nuclear data libraries implemented on the algorithm. In view of this, the aim of this work is determining the parameters evaluated in shielding materials, by using MCNPX code, who shows good agreement with experimental data from literature. Among the materials, Aluminium had lower emission and production of secondary particles

Estudo teórico da contribuição a dose de partículas secundárias geradas por prótons de energias entre 100-200 MeV num phantom de osso compacto

The contribution of the total dose due to deposition of secondary energy particles caused by nuclear inelastic processes (n, 2H, 3H, 3He and  ) in proton therapy is an opened problem and in discussion. In the calculations of plans implemented for routine treatment, the paid dose is calculated whereas that the proton loses energy by ionization and or coulomb excitement. The contribution of inelastic processes associated with nuclear reactions is not considered, mainly due to the difficulty of processing targets consisting of various materials. In this sense, there are only estimates for pure materials or simple composition (water, for example).This work presents the results of simulations by the Monte Carlo method employing the code MCNPX v2.50 (Monte Carlo N-Particle eXtended) of the contribution to the total dose of secondary particles. The study was implemented in a cylindrical phantom composed by compact bone, for monochromatic beams of protons between 100 and 200 MeV with pencil beam form

Métodos de Calibração e Dosimetria de Aplicadores de Betaterapia

The sources of betatherapy for clinical use in Brazil are, the vast majority of strontium-90, radioactive element that is not produced in the country, and therefore requires importation of international laboratories accredited by the International Atomic Energy Agency (IAEA).The use of these resources is always limited the crediting of characteristic values supplied by the manufacturer tables that provide the nominal value of activity and dose distribution to determine the irradiation time of the injury. The Institute of Nuclear Energy Research (IPEN / CNEN-SP) has recently researching the emission profile of these types of radiation sources, and some jobs are being developed with ionization chambers extrapolation for the purpose of standardizing a systematic calibration sources betatherapy. Other studies using parallel measures dosimeters (TLD's) and simulations with the Monte Carlo method. Radiological films have also been used in studies of applicators dosimetric analysis of strontium-90. This paper seeks to analyze the different methods for calibration of applicators betatherapy, already consolidated in studies by examining the advantages and disadvantages of each procedure

Análise espacial do potencial fotovoltaico em telhados de residências usando modelagem hierárquica bayesiana

Coordenação de Aperfeiçoamento de Pessoal de Nível Superior (CAPES)

Simulación en el aula : Prueba de normalidad para muestras pequeñas usando test gráficos

Los métodos gráficos son populares para chequear modelos, un gráfico cuantil- cuantil (qq-plot) permite observar cuan cerca está la distribución de un conjunto de datos a alguna distribución ideal o comparar la distribución de dos conjuntos de datos. La forma del gráfico debería ser idealmente una línea recta específica. Si interesa comparar con la distribución Gaussiana se llama gráfico de probabilidad Normal. El objetivo del presente trabajo es testear normalidad de una muestra en especial para el caso de tamaños muestrales pequeños para los cuales el comportamiento de estos gráficos suele ser errático y conducir a falsas interpretaciones, mostraremos además que no suele ser así con tamaños muestrales más grandes. Proponemos, también establecer una banda de probabilidad o banda envolvente basada en un método empírico, específicamente mediante el método de Monte Carlo, dicha banda nos establecerá un marco de referencia probabilístico para evitar falsas interpretaciones. Se presenta un código computacional, de fácil implementación, empleado por los alumnos para la aplicación de esta metodología de análisis de normalidad, el cual es utilizado para la enseñanza de la temática en cuestión