Made available in DSpace on 2014-10-09T12:27:41Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:05:28Z (GMT). No. of bitstreams: 0 / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Made available in DSpace on 2014-10-09T12:27:41Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:05:28Z (GMT). No. of bitstreams: 0 / Este trabalho tem como objetivo a avaliação dosimétrica de componentes semicondutores (detectores Barreira de Superfície e fotodiodos PIN) para aplicação em medições de dose equivalente em campos de baixo fluxo de nêutrons (rápidos e térmicos), utilizando uma fonte de AmBe de alto fluxo, a instalação de Neutrongrafia do reator IEA-R1 (fluxos térmicos/epitérmicos) e fluxo de nêutrons rápidos do núcleo do reator IPEN/MB-01 (UCRI Unidade Crítica). Para a detecção de nêutrons (térmicos, epitérmicos e rápidos) foram usados componentes moderadores e conversores (parafina, boro e polietileno). Os fluxos resultantes da moderação e conversão foram utilizados para a irradiação de componentes semicondutores (SSB - Barreira de Superfície e fotodiodos). Foi utilizado também um conversor misto constituído de uma folha de polietileno borado (marca Kodak). O método de simulação por Monte Carlo foi utilizado para avaliar de forma analítica a espessura ótima da parafina. O resultado obtido foi similar ao verificado experimentalmente e serviu para avaliar o fluxo de nêutrons emergentes do moderador (parafina). Da mesma forma, através de simulação, foi avaliado também o fluxo de nêutrons rápidos que atinge o conversor de polietileno que cobre a face sensível dos semicondutores. O nível de radiação gama foi avaliado cobrindo o detector por inteiro com uma folha de cádmio de 1 mm de espessura. O reator IPEN/MB-01 foi usado para avaliar a resposta dos detectores para nêutrons rápidos de alto fluxo. Os resultados, de uma forma geral, mostraram concordância e similaridade com os trabalhos desenvolvidos por outros grupos de pesquisas. Foi também estabelecida uma abordagem para o cálculo de dose equivalente utilizando os espectros obtidos nas experiências. / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

<p> In experimental microdosimetry one of the goals is to measure the absorbed dose in microscopic volumes of tissue. The traditional spherical tissue-equivalent proportional counter (TEPC) is the most common detector currently used for microdosimetry. A new microdosimetric detector based on a thick gas electron multiplier (THGEM) was developed. To investigate the feasibility of the THGEM type detector for microdosimetry, a prototype detector was designed and manufactured. The THGEM detector is robust, easy to manufacture and is cost effective. The THGEM foil is composed of a thin FR4-epoxy insulator coated with copper on both sides. The THGEM contains 32 holes each with a diameter of 0.35 mm and pitch of 0.64 mm. The sensitive volume of the detector is a right cylinder with a diameter of ~5 mm and height of ~5 mm and is located in the center of the detector. Systematic tests were conducted at the McMaster Accelerator Laboratory to investigate its overall performance. A neutron-gamma ray radiation field was generated using the 7Li(p,n) reaction. The detector was operated at low bias voltages initially to test the stability and then the relative multiplication gain was measured as a function of the operating high voltage. The detector performance was observed with different THGEM insulator thicknesses ranging from 0.12 mm to 1.48 mm. The multiplication gain was assessed and both neutron and gamma-ray radiation was detected by the THGEM detector. The spectra obtained with the THGEM detector were analyzed and compared to the data collected with the standard spherical TEPC. The investigations provided information about the THGEM detector operation for microdosimetry and the THGEM microdosimetric spectra observed are comparable to the standard TEPC data.</p> / Thesis / Doctor of Philosophy (PhD)

Neste trabalho, medidas microdosimétricas foram realizadas usando um contador proporcional equivalente à tecido - TEPC. com uma cavidade esférica de diâmetro de 1.27 cm. O TEPC foi preenchido com gás propane puro, C3HS, à pressão de 5,6 kPa (42 Torr), que é equivalente a 1,3 &mu;m em diâmetro de unidade de densidade do tecido. O instrumento de medida microdosimétrica foi irradiado com radiação de nêutrons rápidos do reator de pequisa do Nuclear Science Center da Texas A&M University, em College Station,-Texas. Os feixes de nêutrons rápidos foram emitidos com três diferentes valores de potência. 0,5, 1,0, e 2,0 kVV, durante 1 hora para alto ganho e o mesmo tempo para baixo ganho, totalizando 2 horas para cada potência, com 0,0083 Gy/min de taxa de dose. O neutron foi filtrado usando o sistema de irradiação de néutrons rápidos fortemente nitrados (FNIS). do Nuclear Science Center, para obter uma redução da contaminação da radiação de neutron por radiação gama e assim obter espectros microdosimetricos de neutrons como, distribuição de freqüência de energia lineal e distribuição de dose de energia lineal, com boa precisão, e outras grandezas como, freqüência média de energia lineal, dose média de energia lineal, dose absorvida, dose equivalente e fator de qualidade médio de neutron rápido. Os resultados obtidos foram satisfatórios, com os espectros microdosimetricos de nêutrons mostrando uma contaminação de radiação gama abaixo de 5 %, especialmente para distribuição de dose de energia lineal. Os resultados obtidos neste trabalho foram comparados com outros da literatura científica, que usaram outros procedimentos para a redução da contaminação do neutron por radiação gama. estando em concordância com eles. / In this work, microdosimetric measurements were performed using a Wall-less Tissue Equivalent Proportional Counter - TEPC was filled with spherical cavity with an inner diameter of 1.27 cm. The TEPC was tilled with pure propane gas, C3H8 at 5.6 kPa (42 Torr) pressure, which is equi\\alent to 1.3&mu;m in diameter of unit density tissue. The microdosimetric measurement device was irradiated with fast neutron radiation from Texas A&M University Nuclear Science Center research reactor, in College Station, Texas. The fast neutron beams were emitted with three different power values, 0.5, 1.0 and 2.0 kW. during Ih for both high gain and low gain, totalizing two hours for each power with 0.0083 Gy/min of dose rate. The neutron was filtered using the heavily filtered fast neutron irradiation s\\stem (FNIS). from Nuclear Science Center, to obtain a decrease of neutron radiation contamination by gamma ray and so, to gain the neutron microdosimetric spectra as. frequency distribution of lineal energy, dose distribution of lineal energy with good precision, and another quantities as frequency-mean of lineal energy, dose- mean of lineal energy, absorbed dose, equivalent dose and average quality factor of fast neutron. The obtained results were satisfactory, with the neutron microdosimetric spectra showing a gamma ray contamination under 5 %, especially to dose distribution of lineal energy. The results obtained in this work were in agreement when compared with another results from scientific literature, which used another procedure to reduce the neutron contamination by gamma ray.

Neste trabalho, medidas microdosimétricas foram realizadas usando um contador proporcional equivalente à tecido - TEPC. com uma cavidade esférica de diâmetro de 1.27 cm. O TEPC foi preenchido com gás propane puro, C3HS, à pressão de 5,6 kPa (42 Torr), que é equivalente a 1,3 &mu;m em diâmetro de unidade de densidade do tecido. O instrumento de medida microdosimétrica foi irradiado com radiação de nêutrons rápidos do reator de pequisa do Nuclear Science Center da Texas A&M University, em College Station,-Texas. Os feixes de nêutrons rápidos foram emitidos com três diferentes valores de potência. 0,5, 1,0, e 2,0 kVV, durante 1 hora para alto ganho e o mesmo tempo para baixo ganho, totalizando 2 horas para cada potência, com 0,0083 Gy/min de taxa de dose. O neutron foi filtrado usando o sistema de irradiação de néutrons rápidos fortemente nitrados (FNIS). do Nuclear Science Center, para obter uma redução da contaminação da radiação de neutron por radiação gama e assim obter espectros microdosimetricos de neutrons como, distribuição de freqüência de energia lineal e distribuição de dose de energia lineal, com boa precisão, e outras grandezas como, freqüência média de energia lineal, dose média de energia lineal, dose absorvida, dose equivalente e fator de qualidade médio de neutron rápido. Os resultados obtidos foram satisfatórios, com os espectros microdosimetricos de nêutrons mostrando uma contaminação de radiação gama abaixo de 5 %, especialmente para distribuição de dose de energia lineal. Os resultados obtidos neste trabalho foram comparados com outros da literatura científica, que usaram outros procedimentos para a redução da contaminação do neutron por radiação gama. estando em concordância com eles. / In this work, microdosimetric measurements were performed using a Wall-less Tissue Equivalent Proportional Counter - TEPC was filled with spherical cavity with an inner diameter of 1.27 cm. The TEPC was tilled with pure propane gas, C3H8 at 5.6 kPa (42 Torr) pressure, which is equi\\alent to 1.3&mu;m in diameter of unit density tissue. The microdosimetric measurement device was irradiated with fast neutron radiation from Texas A&M University Nuclear Science Center research reactor, in College Station, Texas. The fast neutron beams were emitted with three different power values, 0.5, 1.0 and 2.0 kW. during Ih for both high gain and low gain, totalizing two hours for each power with 0.0083 Gy/min of dose rate. The neutron was filtered using the heavily filtered fast neutron irradiation s\\stem (FNIS). from Nuclear Science Center, to obtain a decrease of neutron radiation contamination by gamma ray and so, to gain the neutron microdosimetric spectra as. frequency distribution of lineal energy, dose distribution of lineal energy with good precision, and another quantities as frequency-mean of lineal energy, dose- mean of lineal energy, absorbed dose, equivalent dose and average quality factor of fast neutron. The obtained results were satisfactory, with the neutron microdosimetric spectra showing a gamma ray contamination under 5 %, especially to dose distribution of lineal energy. The results obtained in this work were in agreement when compared with another results from scientific literature, which used another procedure to reduce the neutron contamination by gamma ray.

Este trabalho realizou uma comparação entre alguns dos principais códigos de transporte que empregam a abordagem estocástica de Monte Carlo para aplicação em cálculos dosimétricos em Medicina Nuclear. Foram analisados com detalhes os diversos modelos físicos e numéricos utilizados pelo código MCNP5 em relação códigos como Penelope e EGS. A identificação de suas potencialidades e limitações para solução de problemas microdosimétricos foram destacados. A metodologia condensada usada pelo MCNP resultou em valores para energia depositada normalmente menores, evidenciando uma conhecida característica do método das historias condensadas: o fato de subestimar tanto o número de colisões ao longo da trajetória do elétron quanto do número de partículas secundárias criadas. O uso de códigos de transporte como Penelope e MCNP em escalas micrométricas recebeu especial atenção neste trabalho. Códigos classe I e II foram estudados e seus principais recursos foram explorados visando o transporte de elétrons, que são de especial importância em dosimetria. Espera-se que a avaliação das metodologias disponíveis, aqui abordadas contribua para um maior entendimento do comportamento de tais códigos principalmente para esta classe de problemas, comuns em microdosimetria. / This study made a comparison between some of the major transport codes that employ the Monte Carlo stochastic approach in dosimetric calculations in nuclear medicine. We analyzed in detail the various physical and numerical models used by MCNP5 code in relation with codes like EGS and Penelope. The identification of its potential and limitations for solving microdosimetry problems were highlighted. The condensed history methodology used by MCNP resulted in lower values for energy deposition calculation. This showed a known feature of the condensed stories: its underestimates both the number of collisions along the trajectory of the electron and the number of secondary particles created. The use of transport codes like MCNP and Penelope for micrometer scales received special attention in this work. Class I and class II codes were studied and their main resources were exploited in order to transport electrons, which have particular importance in dosimetry. It is expected that the evaluation of available methodologies mentioned here contribute to a better understanding of the behavior of these codes, especially for this class of problems, common in microdosimetry.

<p>Radiation quality is described by the RBE (relative biological effectiveness) that varies with the ionizing ability of the radiation. Microdosimetric quantities describe distributions of energy imparted to small volumes and can be related to RBE. This has made microdosimetry a powerful tool for radiation quality determinations in both radiation protection and radiation therapy. The variance-covariance method determines the dose-average of the distributions and has traditionally been used with two detectors to correct for beam intensity variations. Methods to separate dose components in mixed radiation fields and to correct for beam variations using only one detector have been developed in this thesis. Quality factor relations have been optimized for different neutron energies, and a new algorithm that takes single energy deposition events from densely ionizing radiation into account has been formulated. The variance-covariance technique and the new methodology have been shown to work well in the cosmic radiation field onboard aircraft, in the mixed photon and neutron fields in the nuclear industry and in pulsed fields around accelerators.</p><p>The method has also been used for radiation quality characterization in therapy beams. The biological damage is related to track-structure and ionization clusters and requires descriptions of the energy depositions in nanometre sized volumes. It was shown that both measurements and Monte Carlo simulation (condensed history and track-structure) are needed for a reliable nanodosimetric beam characterization. The combined experimental and simulated results indicate that the dose-mean of the energy imparted to an object in the nanometre region is related to the clinical RBE in neutron, proton and photon beams. The results suggest that the variance-covariance technique and the dose-average of the microdosimetric quantities could be well suited for describing radiation quality also in therapy beams.</p>

Radiation quality is described by the RBE (relative biological effectiveness) that varies with the ionizing ability of the radiation. Microdosimetric quantities describe distributions of energy imparted to small volumes and can be related to RBE. This has made microdosimetry a powerful tool for radiation quality determinations in both radiation protection and radiation therapy. The variance-covariance method determines the dose-average of the distributions and has traditionally been used with two detectors to correct for beam intensity variations. Methods to separate dose components in mixed radiation fields and to correct for beam variations using only one detector have been developed in this thesis. Quality factor relations have been optimized for different neutron energies, and a new algorithm that takes single energy deposition events from densely ionizing radiation into account has been formulated. The variance-covariance technique and the new methodology have been shown to work well in the cosmic radiation field onboard aircraft, in the mixed photon and neutron fields in the nuclear industry and in pulsed fields around accelerators. The method has also been used for radiation quality characterization in therapy beams. The biological damage is related to track-structure and ionization clusters and requires descriptions of the energy depositions in nanometre sized volumes. It was shown that both measurements and Monte Carlo simulation (condensed history and track-structure) are needed for a reliable nanodosimetric beam characterization. The combined experimental and simulated results indicate that the dose-mean of the energy imparted to an object in the nanometre region is related to the clinical RBE in neutron, proton and photon beams. The results suggest that the variance-covariance technique and the dose-average of the microdosimetric quantities could be well suited for describing radiation quality also in therapy beams.

Theoretical modeling of biological response to radiation describes qualitatively and quantitatively the results of radiobiological effects at the molecular, chromosomal, and cellular level. The repair-misrepair (RMR) model is the radiobiological model chosen for our study. It models deoxyribonucleic acid (DNA) damage formation and lesion repair through linear and quadratic processes. Double strand breaks (DSB) are a critical lesion in DNA. With increasing LET, the number of DSB per track traversing the cell nucleus increases. Using a compound Poisson process (CPP), we describe DNA damage formation. Three models were considered: a simple CPP using constant LET, a CPP using a chord length distribution, and a CPP using specific energy distribution. In the two first cases, and for low LET radiation the initial distribution of DSB was well approximated by a Poisson distribution, while for high LET radiation the initial distribution of DSB deviated slightly from a Poisson distribution. In the last case, DSB distribution was much broader than a pure Poisson distribution. Datasets from the literature for seven human cell lines, exhibiting various sensitivities to radiation were analyzed. We compared stochastic, CPP, and CPP using chord length distribution, with deterministic RMR models. For low LET radiation and at high dose rates the stochastic survival results agree well with the deterministic survival results. Also the stochastic model allows for non-linearity at low doses due to the accumulation of sub-lethal damage. At low dose rates deterministic results overestimate the surviving fraction compared to stochastic results. For high LET radiation stochastic and deterministic survival results agree. Stochastic survival results using specific energy distribution diverged from deterministic results by underestimating the surviving fraction at low and high LET radiation. The dose rate sparing curve, representing surviving fraction at a dose of 10Gy vs. dose rate shows that deterministic survival results are consistent with stochastic survival results, using CPP, or CPP with chord length distribution, for low and high dose rate values. Compared to deterministic aspects of DNA damage formation we concluded that stochastic aspects of DNA damage formation and repair using CPP or CPP with chord length distribution are not as prominent as reported in the earlier studies.

The dosimetric properties of fast-neutron beams with energies ≤80 MeV were explored using Monte Carlo techniques. Taking into account transport of all relevant types of released charged particles (electrons, protons, deuterons, tritons, 3He and α particles) pencil-beam dose distributions were derived and used to calculate absorbed dose distributions. Broad-beam depth doses in phantoms of different materials were calculated and compared and the scaling factors required for converting absorbed dose in one material to absorbed dose in another derived. The scaling factors were in good agreement with available published data and show that water is a good substitute for soft tissue even at neutron energies as high as 80 MeV. The inherent penumbra and the fraction of absorbed dose due to photon interactions were also studied, and found to be consistent with measured values reported in the literature. Treatment planning in fast-neutron therapy is commonly performed using dose calculation algorithms designed for photon beam therapy. When applied to neutron beams, these algorithms have limitations arising from the physical models used. Monte Carlo derived neutron pencil-beam kernels were parameterized and implemented in the photon dose calculation algorithms of the TMS (MDS Nordion) treatment planning system. It was shown that these algorithms yield good results in homogeneous water media. However, the method used to calculate heterogeneity corrections in the photon dose calculation algorithm did not yield correct results for neutron beams in heterogeneous media. To achieve results with adequate accuracy using Monte Carlo simulations, fundamental cross-section data are needed. Neutron cross-sections are still not sufficiently well known. At the The Svedberg Laboratory in Uppsala, Sweden, an experimental facility has been designed to measure neutron-induced charged-particle production cross-sections for (n,xp), (n,xd), (n,xt), (n,x3He) and (n,xα) reactions at neutron energies up to 100 MeV. Depending on neutron energy, these generated particles account for up to 90% of the absorbed dose. In experimental determination of the cross-sections, measured data have to be corrected for the energies lost by the charged particles before leaving the target in which they were generated. To correct for the energy-losses, a computational code (CRAWL) was developed. It uses a stripping method. With the limitation of reduced energy resolution, spectra derived using CRAWL compares well with those derived using other methods. In fast-neutron therapy, the relative biological effectiveness (RBE) varies from 1.5 to 5, depending on neutron energy, dose level and biological end-point. LET and other physical quantities, developed within the field of microdosimetry over the past couple of decades, have been used to describe RBE variations between different fast-neutron beams as well as within a neutron irradiated body. In this work, a Monte Carlo code (SHIELD-HIT) capable of transporting all charged particles contributing to absorbed dose, was used to calculate energy-differential charged particle spectra. Using these spectra, values of the RBE related quantities LD, γD, γ* and R were derived and studied as function of neutron energy, phantom material and position in a phantom. Reasonable agreement with measured data in the literature was found and indicates that the quantities may be used to predict RBE variations in an arbitrary fast-neutron beam.