In radionuclide therapy it is still common to administer standard activities or to scale administered activity with blunt parameters such as body weight or surface area. This is not ideal because, due to considerable variation in kinetics, large safety margins have to be applied to avoid radiation damage to healthy organs, which causes under-treatment of many patients. To base the administered activity on individual dosimetry, as in other therapy modalities using ionizing radiation, will essentially solve this problem. However, dosimetry in radionuclide therapy is resource-demanding and debilitating for the patient because it involves a number of measurements to determine the kinetics of the therapy radionuclide and needs to be optimized for clinical feasibility. First, the ability to measure radioactivity distributions of radionuclides for therapy was investigated. SPECT measurements of 177Lu, which was later used clinically, showed good spatial resolution and a reasonable quantitative accuracy. A new method to calculate absorbed dose to solid risk organs and tumours was developed and applied in the clinic. Kinetic data were obtained by repeated SPECT measurements. Radiation concentration determined in small volumes of interest could then be multiplied by a constant to obtain absorbed dose because it was shown that cross-fire was negligible in organs with high activity concentration. The new dosimetry method, compared to other methods, was found to give better results with less effort. In addition, a method to calculate absorbed dose to bone marrow was developed and clinically implemented. In 200 patients, individual kinetics and absorbed dose were studied and variations were found to be large. Kidney was the dose-limiting organ in almost all patients (98.5%). Keeping the kidney dose < 23Gy, about half of the patients could receive 5, or up to 10 treatments instead of the stipulated 4.

O objetivo deste trabalho foi estabelecer uma metodologia de calibração em termos de dose absorvida na água para câmaras de ionização de placas paralelas a serem utilizadas em feixes de radiação X de energia baixa (10 kV a 100 kV) para fins terapêuticos. Atualmente, no Brasil nenhum laboratório de calibração está oferecendo este tipo de serviço. Para o estabelecimento desta metodologia de calibração foram utilizadas duas câmaras de ionização PTW modelos 23344. Ambas as câmaras foram caracterizadas e testadas qualitativamente segundo recomendações de normas internacionais. Os testes de caracterização realizados foram: a medição da taxa de dose mínima efetiva, a curva de saturação, a eficiência da coleção de íons, a resposta quanto ao efeito da polaridade e a linearidade da câmara com a resposta. Os testes de controle de qualidade aplicados foram: estabilidade em curto e longo prazos, fuga de corrente sem irradiação, fuga de corrente após-irradiação e tempo de estabilização. Para a implantação da metodologia, foram estabelecidas as qualidades de radiação de T-10 a T-100, seguindo as recomendações do código de prática da AIEA. Desta forma, foi possível determinar a grandeza de referência, dose absorvida na água, utilizando-se as duas câmaras de ionizações e em todas as qualidades estabelecidas. / The objective of this study was to establish a calibration methodology in terms of absorbed dose to water for parallel plate ionization chambers to be used in low energy X rays beams (10kV to 100kV) for therapy purposes. Currently, in Brazil no calibration laboratory is offering this type of service. In order to establish this calibration methodology was used two ionization chambers PTW models 23344. Both chambers were characterized and tested qualitatively according to recommendations of international standards. The characterization tests performed were: measuring the effective minimum dose rate, the saturation curve, the efficiency of ions collection, polarity effect and the linearity of the ionization chamber with the response. The quality control tests applied were: stability in the short and long term, leakage current without irradiation, leakage current after irradiation and settling time. For the implementation of the methodology, the radiation qualities the T- 10 to T-100 were established, following the recommendations of the IAEA code of practice. Thus, it was possible to determine the magnitude of reference absorbed dose in water, using the two ionization chambers in the all established qualities.

O objetivo deste trabalho foi estabelecer uma metodologia de calibração em termos de dose absorvida na água para câmaras de ionização de placas paralelas a serem utilizadas em feixes de radiação X de energia baixa (10 kV a 100 kV) para fins terapêuticos. Atualmente, no Brasil nenhum laboratório de calibração está oferecendo este tipo de serviço. Para o estabelecimento desta metodologia de calibração foram utilizadas duas câmaras de ionização PTW modelos 23344. Ambas as câmaras foram caracterizadas e testadas qualitativamente segundo recomendações de normas internacionais. Os testes de caracterização realizados foram: a medição da taxa de dose mínima efetiva, a curva de saturação, a eficiência da coleção de íons, a resposta quanto ao efeito da polaridade e a linearidade da câmara com a resposta. Os testes de controle de qualidade aplicados foram: estabilidade em curto e longo prazos, fuga de corrente sem irradiação, fuga de corrente após-irradiação e tempo de estabilização. Para a implantação da metodologia, foram estabelecidas as qualidades de radiação de T-10 a T-100, seguindo as recomendações do código de prática da AIEA. Desta forma, foi possível determinar a grandeza de referência, dose absorvida na água, utilizando-se as duas câmaras de ionizações e em todas as qualidades estabelecidas. / The objective of this study was to establish a calibration methodology in terms of absorbed dose to water for parallel plate ionization chambers to be used in low energy X rays beams (10kV to 100kV) for therapy purposes. Currently, in Brazil no calibration laboratory is offering this type of service. In order to establish this calibration methodology was used two ionization chambers PTW models 23344. Both chambers were characterized and tested qualitatively according to recommendations of international standards. The characterization tests performed were: measuring the effective minimum dose rate, the saturation curve, the efficiency of ions collection, polarity effect and the linearity of the ionization chamber with the response. The quality control tests applied were: stability in the short and long term, leakage current without irradiation, leakage current after irradiation and settling time. For the implementation of the methodology, the radiation qualities the T- 10 to T-100 were established, following the recommendations of the IAEA code of practice. Thus, it was possible to determine the magnitude of reference absorbed dose in water, using the two ionization chambers in the all established qualities.

Radiotherapy has commonly been utilised to cure cancer for more than a century. It is counted among the fundamental branches of medicine and represents an effective local or locally-regional method of curing both cancer and some non-cancerous conditions. It utilises ionising radiation which unfortunately eliminates tumour cells along with healthy ones. This is why a wide range of harmful effects of the radiation can be observed on humans. Patients treated with radiotherapy are in some cases monitored with dosimeters so that the intended dose can be compared with what is really absorbed. Nemocnice České Budějovice, a. s. monitors the dose in expected locations of non-homogeneous irradiation using the aforementioned TL dosimeters during the process of rotary irradiation of Mycosis fungoides. Before actually being used in an in vivo dosimetry, these dosimeters must be properly calibrated and have their sensitivity adjusted. Other than that, they are fairly easy to use, do not require much time or money invested and are able to constantly monitor the dose received by a patient treated with rotary irradiation. This diploma thesis discusses the usage of TL dosimeters to measure non-homogeneity of irradiation. It therefore compares the doses received by patients in various parts of the body during irradiation by the TSEI method. These 22 irradiated patients had thorough measurements taken of the doses they received in the so-called black hole region, their axillae and neck while holding their arms up and with arms loosely positioned close to the body. The thesis also suggests the possibility of the dosimeters being used by the integrated emergency service to assist during rescues and demolitions performed in emergency situations when a leak of ionising radiation occurs. Using TL dosimeters would mean more precise measurements of the dose received by the involved personnel in various parts of their body. If a patient is treated with the TSEI method, the dose received is monitored in a reference point, critical areas and areas with residual infiltrations or tumours. Doses measured in critical areas indicate that should the acral parts of limbs be left uncovered, they absorb larger doses than the rest of the body. They thus exceed the intended dose significantly. In the case of fingers, the dose tends to reach as much as 3 Gy. Depending on clinical picture, the attending physician determines whether special covering should be used. This covering reduces the doses received to merely a few tenths of a Gy. There also tends to be a large difference in absorbed doses in axillar areas and the neck, depending on whether the patient's arms are held up or close to the body respectively. Test results indicate that holding arms up or keeping them close to the body on a particular side have always had a profound effect on the dose absorbed by the patient in this particular area. This means that the position of the body greatly influences how much is absorbed in various parts of the body. TL dosimeters are also used in other areas than in vivo dosimetry in radiotherapy. An example of this could be determining the dose received in upper limbs of the workers monitored with thermoluminescent dosimeters in the form of bracelets or rings. They also serve to monitor the external irradiation of persons within the limits of the Czech Republic (TLD network). In radiation therapy, both the doses in skin and body are taken into account when conducting measurements. Depending on the data extracted, it is then possible to assess the course of treatment and ensure safe implementation of ionising radiation. Integrated emergency service teams deployed in cases of radiation emergencies are not considering using TL dosimeters so far, although they could most likely be used to ascertain the exact doses absorbed. Further research would however need to be conducted to either confirm or disprove the benefits of using TLD.

Made available in DSpace on 2014-10-09T12:37:43Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:00:17Z (GMT). No. of bitstreams: 1 05382.pdf: 3611357 bytes, checksum: aeefc0f052bf6399692f11e4b2ff1e2b (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Doses absorvidas e doses efetivas podem ser calculadas utilizando códigos computacionais de transporte de radiação. A qualidade desses cálculos depende dos dados nucleares, no entanto, são raras as informações sobre as diferenças nas doses causadas por diferentes bibliotecas. O objetivo desse estudo é comparar os valores de dose (absorvida e efetiva) obtidos utilizando diferentes bibliotecas de dados nucleares devido a uma fonte externa de nêutrons na faixa de 10-11 a 20 MeV. As bibliotecas de dados nucleares são: JENDL 4.0, JEFF 3.1.1 e ENDF/B-VII.0. Cálculos de doses foram realizados utilizando o código MCNPX considerando o modelo antropomórfico da ICRP-110. As diferenças nos valores das doses absorvidas utilizando as bibliotecas JEFF 3.1.1 e a ENDF/B.VII são pequenas, em torno de 1%, porém os resultados obtidos com a JENDL 4.0 apresentam diferenças de até 85 % compara aos resultados da ENDF/B-VII.0 e JEFF 3.1.1. Diferenças nas doses efetivas são em torno de 1,5% entre ENDF/B-VII.0 e JEFF 3.1.1, e 11 % entre ENDF/B-VII.0 e JENDL 4.0. / Absorbed dose and Effective dose are usually calculated using radiation transport computer codes. The quality of the calculations of absorbed dose depends on nuclear data utilized, however, there are rare information about the differences in dose caused by the use of different libraries. The objective of this study is to compare dose values obtained using different nuclear data libraries due to external source of neutrons in the energy range from 10-11 to 20 MeV. The nuclear data libraries used are: JENDL 4.0, JEFF 3.3.1 and ENDF/B.VII. Dose calculations were carried out with the MCNPX code considering the anthropomorphic ICRP 110 model. The differences in the absorbed dose values using JEFF 3.3.1 and ENDF/B.VII libraries are small, around 1%, but the results obtained with JENDL 4.0 presented differences up to 85% compared to ENDF and JEFF results. Differences in effective dose values are around 1.5% between ENDF and JEFF and 11% between ENDF/B.VII and JENDL 4.0.

Os níveis de radioatividade natural do planeta e suas eventuais consequencias são objeto de estudo da radioproteção ambiental. Nos últimos anos, as agências internacionais ligadas à proteção radiológica têm debatido as práticas até então estipuladas, no que diz respeito à proteção da fauna e flora, cuja filosofia acreditava que as recomendações sugeridas para a proteção do homem asseguravam que outras espécies estariam também protegidas. Assim, são necessários estudos sobre as concentrações de atividade dos radionuclídeos dispersos no meio ambiente, assim como as doses absorvidas por organismos de diferentes ecossistemas, pela exposição interna e externa. O Brasil possui a segunda maior população de cães e gatos do mundo e produz anualmente mais de 2 milhões de toneladas de rações. O presente trabalho investigou os níveis de radioatividade presentes em rações comerciais para cães e gatos, por meio da espectrometria gama de alta resolução. Os resultados mostraram concentrações abaixo da MDA para radionuclídeos artificiais e baixas concentrações para radionuclídeos naturais, cujos valores variaram de 0,9 ± 0,3 Bq/kg a 5,1 ± 0,7 Bq/kg para o 226Ra, de 1,2 ± 0,4 Bq/kg a 11,1 ± 1,0 Bq/kg para o 232Th e de 156 ± 7 Bq/kg a 410 ± 19 Bq/kg para o 40K. Para verificar a composição de alguns minerais, foi empregada a técnica por EDXRF e, utilizando estatística multivariada, foi possível verificar as correlações entre os radionuclídeos e o conteúdo mineral encontrado. A boa correlação que foi observada entre as concentrações de 226Ra, 232Th e cálcio, pode estar associada ao uso de farinhas de carne e ossos na fabricação das rações. As doses internas para alguns órgãos foram inferidas pelo método de Monte Carlo, obtendo valores menores que 1 μGy/dia. Em síntese, os resultados mostraram que os níveis de atividade encontrados nas rações são baixos o suficiente para concluir que as marcas de ração canina avaliadas não fornecem riscos radiológicos para os animais que as consomem. / The levels of natural radioactivity throughout the planet and their eventual consequences are studied by Environmental Radioprotection. Over the past years, the international agencies concerned with radiation protection have debated over the practices conducted so far, regarding the protection of the fauna and flora, which believed that the recommendations implemented for human beings assured that other species were also protected. Thus, assessments of the activity concentration of different radionuclides in the environment, as well as the absorbed doses for species from different ecosystems, due to internal and external exposures, are needed. Brazil holds the second largest dog and cat population in the world and annually produces over 2 million tons of feed. The present work has investigated the radioactivity levels in commercial brands of dry dog and cat food, using high resolution gamma spectrometry. The results have shown activity concentrations for artificial radionuclides below the detector\'s Minimum Detectable Activity and also, low concentration levels for the natural radionuclides, varying from 0,9 ± 0,3 Bq/kg up to 5,1 ± 0,7 Bq/kg for 226Ra, from 1,2 ± 0,4 Bq/kg up to 11,1 ± 1,0 Bq/kg for 232Th and from 156 ± 7 Bq/kg up to 410 ± 19 Bq/kg for 40K. In order to verify the mineral content in pet food, EDXRF technique was applied and, using multivariate statistics, correlations between the mineral and radionuclide content were verifyied. The good correlation observed between concentrations of 226Ra, 232Th and calcium could be associated with meat and bone flour used in feed manufacturing. The internal dose for some organs were inferred by Monte Carlo method and the results were no higher than 1 μGy/day. In summary, results have shown that the activity levels found in the pet food are low enough to conclude that the brands evaluated carry no radiological risks for the animals that consume them.

Os níveis de radioatividade natural do planeta e suas eventuais consequencias são objeto de estudo da radioproteção ambiental. Nos últimos anos, as agências internacionais ligadas à proteção radiológica têm debatido as práticas até então estipuladas, no que diz respeito à proteção da fauna e flora, cuja filosofia acreditava que as recomendações sugeridas para a proteção do homem asseguravam que outras espécies estariam também protegidas. Assim, são necessários estudos sobre as concentrações de atividade dos radionuclídeos dispersos no meio ambiente, assim como as doses absorvidas por organismos de diferentes ecossistemas, pela exposição interna e externa. O Brasil possui a segunda maior população de cães e gatos do mundo e produz anualmente mais de 2 milhões de toneladas de rações. O presente trabalho investigou os níveis de radioatividade presentes em rações comerciais para cães e gatos, por meio da espectrometria gama de alta resolução. Os resultados mostraram concentrações abaixo da MDA para radionuclídeos artificiais e baixas concentrações para radionuclídeos naturais, cujos valores variaram de 0,9 ± 0,3 Bq/kg a 5,1 ± 0,7 Bq/kg para o 226Ra, de 1,2 ± 0,4 Bq/kg a 11,1 ± 1,0 Bq/kg para o 232Th e de 156 ± 7 Bq/kg a 410 ± 19 Bq/kg para o 40K. Para verificar a composição de alguns minerais, foi empregada a técnica por EDXRF e, utilizando estatística multivariada, foi possível verificar as correlações entre os radionuclídeos e o conteúdo mineral encontrado. A boa correlação que foi observada entre as concentrações de 226Ra, 232Th e cálcio, pode estar associada ao uso de farinhas de carne e ossos na fabricação das rações. As doses internas para alguns órgãos foram inferidas pelo método de Monte Carlo, obtendo valores menores que 1 μGy/dia. Em síntese, os resultados mostraram que os níveis de atividade encontrados nas rações são baixos o suficiente para concluir que as marcas de ração canina avaliadas não fornecem riscos radiológicos para os animais que as consomem. / The levels of natural radioactivity throughout the planet and their eventual consequences are studied by Environmental Radioprotection. Over the past years, the international agencies concerned with radiation protection have debated over the practices conducted so far, regarding the protection of the fauna and flora, which believed that the recommendations implemented for human beings assured that other species were also protected. Thus, assessments of the activity concentration of different radionuclides in the environment, as well as the absorbed doses for species from different ecosystems, due to internal and external exposures, are needed. Brazil holds the second largest dog and cat population in the world and annually produces over 2 million tons of feed. The present work has investigated the radioactivity levels in commercial brands of dry dog and cat food, using high resolution gamma spectrometry. The results have shown activity concentrations for artificial radionuclides below the detector\'s Minimum Detectable Activity and also, low concentration levels for the natural radionuclides, varying from 0,9 ± 0,3 Bq/kg up to 5,1 ± 0,7 Bq/kg for 226Ra, from 1,2 ± 0,4 Bq/kg up to 11,1 ± 1,0 Bq/kg for 232Th and from 156 ± 7 Bq/kg up to 410 ± 19 Bq/kg for 40K. In order to verify the mineral content in pet food, EDXRF technique was applied and, using multivariate statistics, correlations between the mineral and radionuclide content were verifyied. The good correlation observed between concentrations of 226Ra, 232Th and calcium could be associated with meat and bone flour used in feed manufacturing. The internal dose for some organs were inferred by Monte Carlo method and the results were no higher than 1 μGy/day. In summary, results have shown that the activity levels found in the pet food are low enough to conclude that the brands evaluated carry no radiological risks for the animals that consume them.

Radiation therapy with light ions improves treatment outcome for a number of tumor types. The advantageous dose distributions of light ion beams en-able exceptional target conformity, which assures high dose delivery to the tumor while minimizing the dose to surrounding normal tissues. The demand of high target conformity necessitates development of accurate methods to calculate absorbed dose distributions. This is especially important for heavy charged particle irradiation, where the patient is exposed to a complex radia-tion field of primary and secondary ions. The presented approach combines accurate Monte Carlo calculations using the SHIELD-HIT07 code with a fast analytical pencil beam model, to pro-vide dose distributions of light ions. The developed model allows for ana-lytical descriptions of multiple scattering and energy loss straggling proc-esses of both primary ions and fragments, transported in tissue equivalent media. By applied parameterization of the radial spread of fragments, im-proved description of radial dose distributions at every depth is obtained. The model provides a fast and accurate tool of practical value in clinical work. Compared to conventional radiation modalities, an enhanced tissue response is seen after light ion irradiation and biological optimization calls for accu-rate model description and prediction of the biological effects of ion expo-sure. In a joint study, the performance of some radiobiological models is compared for facilitating the development towards more robust and precise models. Specifically, cell survival after exposure to various ion species is modeled by a fast analytical cellular track structure approach in conjunction with a simple track-segment model of ion beam transport. Although the stud-ies show that descriptions of complex biological effects of ion beams, as given by simple radiobiological models, are approximate, the models may yet be useful in analyzing clinical results and designing new strategies for ion therapy.

The dependence on oil and the fact that petroleum conventional reservoirs are becoming depleted direct attentions toward unconventional-and harder to access-reservoirs. Among those, heavy and extremely heavy oil reservoirs and tar sands form a considerable portion of all petroleum resources. Conventional thermal and thermocatalytic refining methods are not affordable choices in some cases, as they demand a considerable energy investment. On the other hand, electron irradiation, as a novel technology, provides more promising results in heavy oil upgrading. Electron irradiation, as a method of delivering energy to a target molecule, ensures that most of the energy is absorbed by the molecule electronic structure. This leads to a very efficient generation of reactive species, which are capable of initiating chemical reactions. In contrast, when using thermal energy, only a small portion of the energy goes into the electronic structure of the molecule; therefore, bond rupture will result only at high energy levels. The effect of electron irradiation on different heavy petroleum fluids is investigated in this study. Radiation-induced physical and chemical changes of the fluids have been evaluated using different analytical instruments. The results show that high energy electron particles intensify the cracking of heavy hydrocarbons into lighter species. Moreover, irradiation is seen to limit any post-treatment reactions, providing products of higher stability. Depending on the characteristics of the radiolyzed fluid, irradiation may change the distribution pattern of the products, or the radiolysis process may follow the same mechanism that thermal cracking does. In addition to that, we have studied the effectiveness of different influencing variables such as reaction temperature, absorbed dose values, and additives on radiolytic reactions. More specifically, the following subjects are addressed in this study: *Radiation?induced chain reactions of heavy petroleum fluids *Complex hydrocarbon cracking mechanism *High and low temperature radiolysis *Synergetic effects of different chemical additives in radiolysis reactions *Time stability of radiation products