A manutenção dos níveis de dose abaixo dos limites exigidos pelas normas nacionais e internacionais é essencial em todas as aplicações das radiações ionizantes. Os níveis de restrição de dose no Brasil são estabelecidos utilizando a grandeza equivalente de dose ambiente, H* (10) e na prática de levantamentos radiométricos, os níveis de radiação são calculados por meio de medições com câmaras de ionização utilizando a grandeza kerma no ar convertidas para equivalente de dose ambiente por urn coeficiente constante. 0 presente trabalho tern por objetivo o estudo experimental das relações entre kerma no ar e a grandeza operacional equivalente de dose ambiente, pela medição de feixes de raios X transmitidos através de materiais utilizados em salas radiológicas dedicadas à exames de tórax. Uma metodologia experimental, baseada em técnicas de espectroscopia, foi desenvolvida para a medição dos espectros de raios X. Com os resultados, as estimativas da grandeza equivalente de dose ambiente, obtidas através de coeficientes de conversão entre o kerma no ar e esta grandeza, tornam-se mais realistas por levar em consideração as alterações espectrais decorrentes da atenuação dos feixes primários por objetos simuladores antropomórficos e por diferentes materiais atenuadores. Foi encontrada uma diferença máxima de 53,52% entre esses coeficientes e aquele adotado no Brasil por meio da ANVISA (1,14 Sv/Gy), o que indica uma subestimação desse valor. 0 comportamento espectral dos feixes de raios X transmitidos por barreiras primárias e atenuadores presentes em procedimentos radiológicos apresentou influencia sobre resultados relacionados a levantamentos radiométricos e procedimento de cálculos de barreiras. / The maintenance of dose levels below the limits required by national and international standards are essential in all applications of ionizing radiation. The dose constrains levels in Brazil are established in terms of the quantity ambient dose equivalent, H*(10), while the radiation levels in radiometric surveys are calculated by means of measurements with ion chambers using the quantity air-kerma converted to ambient dose equivalent by a constant factor. The present work aims the experimental study of the relationship between the air­ kerma and the operational quantity ambient dose equivalent, by measuring X-ray beams transmitted through materials used in dedicated chest radiographic facility. An experimental methodology, based on spectroscopic techniques was developed for the X-ray spectra measurements. With the results, estimates of ambient dose equivalent quantity through conversion factors between this quantity and the air-kerma, become more realistic by taking into account the spectral changes resulting from the attenuation of primary beams by anthropomorphic phantoms and different attenuating materials. The maximum difference founded between these coefficients and the one adopted in Brazil by ANVISA (1.14 Sv I Gy) was 53.52%, which indicates underestimation of the value. The spectral behavior of the X-ray beam transmitted by primary barriers and attenuators present in radiological procedures presented influences on results related to radiometric surveys and procedure calculations barriers.

A manutenção dos níveis de dose abaixo dos limites exigidos pelas normas nacionais e internacionais é essencial em todas as aplicações das radiações ionizantes. Os níveis de restrição de dose no Brasil são estabelecidos utilizando a grandeza equivalente de dose ambiente, H* (10) e na prática de levantamentos radiométricos, os níveis de radiação são calculados por meio de medições com câmaras de ionização utilizando a grandeza kerma no ar convertidas para equivalente de dose ambiente por urn coeficiente constante. 0 presente trabalho tern por objetivo o estudo experimental das relações entre kerma no ar e a grandeza operacional equivalente de dose ambiente, pela medição de feixes de raios X transmitidos através de materiais utilizados em salas radiológicas dedicadas à exames de tórax. Uma metodologia experimental, baseada em técnicas de espectroscopia, foi desenvolvida para a medição dos espectros de raios X. Com os resultados, as estimativas da grandeza equivalente de dose ambiente, obtidas através de coeficientes de conversão entre o kerma no ar e esta grandeza, tornam-se mais realistas por levar em consideração as alterações espectrais decorrentes da atenuação dos feixes primários por objetos simuladores antropomórficos e por diferentes materiais atenuadores. Foi encontrada uma diferença máxima de 53,52% entre esses coeficientes e aquele adotado no Brasil por meio da ANVISA (1,14 Sv/Gy), o que indica uma subestimação desse valor. 0 comportamento espectral dos feixes de raios X transmitidos por barreiras primárias e atenuadores presentes em procedimentos radiológicos apresentou influencia sobre resultados relacionados a levantamentos radiométricos e procedimento de cálculos de barreiras. / The maintenance of dose levels below the limits required by national and international standards are essential in all applications of ionizing radiation. The dose constrains levels in Brazil are established in terms of the quantity ambient dose equivalent, H*(10), while the radiation levels in radiometric surveys are calculated by means of measurements with ion chambers using the quantity air-kerma converted to ambient dose equivalent by a constant factor. The present work aims the experimental study of the relationship between the air­ kerma and the operational quantity ambient dose equivalent, by measuring X-ray beams transmitted through materials used in dedicated chest radiographic facility. An experimental methodology, based on spectroscopic techniques was developed for the X-ray spectra measurements. With the results, estimates of ambient dose equivalent quantity through conversion factors between this quantity and the air-kerma, become more realistic by taking into account the spectral changes resulting from the attenuation of primary beams by anthropomorphic phantoms and different attenuating materials. The maximum difference founded between these coefficients and the one adopted in Brazil by ANVISA (1.14 Sv I Gy) was 53.52%, which indicates underestimation of the value. The spectral behavior of the X-ray beam transmitted by primary barriers and attenuators present in radiological procedures presented influences on results related to radiometric surveys and procedure calculations barriers.

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This work has been a study of systems, mostly of sulfa-drugs, showing polymorphic behaviour. Using different means as solid state NMR, X-ray analysis, and theoretical calculations, we have seen how it is possible to understand results obtained from the different techniques, proving how the study of polymorphic systems needs cooperative advice from the different techniques that are able to detect polymorphic differences. Within the sulfa-drugs I have been mostly concentrating on sulfanilamide, studying (^13)C and (^15)N solid state NMR spectra of the different polymorphs. The NMR parameters that have been most interesting to study, have been the relaxation times that have revealed complicated motion of the molecule despite it being a small molecule. In order to obtain detailed information from (^15)N spectra it has been necessary to enrich the samples and this has enabled a study of the shielding tensors of the nitrogens in the molecule. (^13)C spectra were also recorded of systems studied sulfathiazole solvates that proved to show some of the same solid state effects in the NMR spectra as sulfanilamide. Shielding calculations have proved to be still limited in order to obtain reliable information on the shielding of both and (^13)C (^15)N nuclei but considering hydrogen-bonded molecules, as opposed to isolated molecules, seemed to have improved the calculations quite a lot, so that some idea of intermolecular effects could be deducted. Exact positions of the hydrogen has proved to be essential as well in order to improve the calculations. Finally a case study for the REDOR pulse sequence has been carried out. Different attempts to understand the effects influencing this particular experiment have been carried out on 20% and 99% doubly enriched glycine, as well as on a particular sample, doubly enriched BRL55834, but the internuclear distances measured with this technique still displayed some uncertainties that made results not thoroughly reliable.

<p>Reference radiation fields for x-ray qualities are described by the International Organization of Standards (ISO). This study describes the procedure to establish nine different low energy X-ray qualities at the national metrology laboratory, Swedish Radiation Protection Authority, following the document ISO 4037. Measurements of tube voltage, half-value layer, mean energy and spectral resolution have been performed for qualities N-15, N-20, N-25, N-30, N-40, L-20, L-30, L-35 and L-55. Furthermore, dose equivalent conversion coefficients for operational quantities ambient dose equivalent, personal dose equivalent and directional dose equivalent have been calculated by folding the mono-energetic conversion factors with measured spectral distributions of the x-ray qualities. The spectral distributions were unfolded from pulse-height distributions to photon distributions using simulated data of the semi-conductor detector used for measurements, generated with the Monte Carlo code PENELOPE.</p>

Reference radiation fields for x-ray qualities are described by the International Organization of Standards (ISO). This study describes the procedure to establish nine different low energy X-ray qualities at the national metrology laboratory, Swedish Radiation Protection Authority, following the document ISO 4037. Measurements of tube voltage, half-value layer, mean energy and spectral resolution have been performed for qualities N-15, N-20, N-25, N-30, N-40, L-20, L-30, L-35 and L-55. Furthermore, dose equivalent conversion coefficients for operational quantities ambient dose equivalent, personal dose equivalent and directional dose equivalent have been calculated by folding the mono-energetic conversion factors with measured spectral distributions of the x-ray qualities. The spectral distributions were unfolded from pulse-height distributions to photon distributions using simulated data of the semi-conductor detector used for measurements, generated with the Monte Carlo code PENELOPE.

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