L'objectif de ce travail de thèse est de mettre au point un dispositif dédié à la mesure de spectres bêta avec une précision métrologique. Le dispositif conçu autour d'un semi-conducteur silicium tient compte des phénomènes physiques et de détection à l'origine de déformations dans le spectre mesuré, afin de les limiter et de les réduire au maximum. Des simulations Monte-Carlo de la chambre de détection ont permis de déterminer la géométrie et les matériaux à utiliser. La qualité des sources radioactives est également déterminante pour obtenir des spectres de qualité. Après la mesure, les spectres sont traiter afin de les corriger des déformations restantes. Une fonction de réponse doit donc être déterminée pour chaque géométrie de mesure. Cette détermination se fait à l'aide des simulations MC. Nos premiers résultats montrent qu'une déconvolution du spectre mesuré avec la réponse du système de détection permet d'obtenir la forme réelle du spectre bêta avec une grande précision. / The goal of this PhD work is to build an experimental device dedicated to measuring beta spectra with a precision relevant to modern metrology requirements. The device, which is based on a silicon semi-conductor detector, must take into account certain physical phenomena and detector characteristics which could lead to deformation of the measured spectra. These must be understood and minimized. Monte-Carlo simulations have allowed the geometry and construction materials to be optimized. The quality of the radioactive sources is paramount in obtaining spectra of high-quality. Nonetheless, the measured spectra must be corrected for any remaining distortion. A response function must therefore be determined for each measurement geometry. This can be achieved via Monte-Carlo simulations. The first results show that de-convolution of the measured spectra with the response function allows the accurate determination of the true form of the beta spectra.

Counting efficiencies were determined by empirical measurement and Monte Carlo simulation for carbon-14, strontium-89, strontium-90, and yttrium-90 standards counted by low-background gas flow proportional counter for strontium carbonate precipitates in the range from 3 to 33 mg cm⁻². The maximum beta particle energies range from 0.156 MeV for carbon-14 to 2.28 MeV for yttrium-90. The parameters for estimating the counting efficiency are summarized for sources with areal thickness of 14 mg cm⁻² and over the range in strontium carbonate areal thickness from 0.1 mg cm⁻² to 33 mg cm⁻². Uncertainty budgets providing estimates of the uncertainty, sources of variability in the calibration process, and the total expanded uncertainty are presented. Information is presented for the Monte Carlo simulation regarding the composition of the detector window, the energy excluded by the amplifier discriminator of the counting system, and the physical density of materials for this analytical process. The histogram normalization routine implemented within MCNP is described and found to bias the probability distribution for beta-particle energy spectra. The difference in the specification of the probability distribution for beta-particle energy spectra in ICRU 56 Appendix D and MCNP requirements are described and a correction for the bias introduced during the normalization process for beta spectra is provided. Counting efficiencies determined by empirical measurement and Monte Carlo simulations agree within the total expanded uncertainties of the measurements and the uncertainties of the Monte Carlo simulations.

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Made available in DSpace on 2014-10-09T12:42:10Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:04:49Z (GMT). No. of bitstreams: 0 / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Made available in DSpace on 2014-10-09T12:42:10Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:04:49Z (GMT). No. of bitstreams: 0 / No campo da medicina, a radiação ionizante é utilizada tanto para fins terapêuticos como para fins diagnósticos, englobando assim um amplo intervalo de doses de diferentes tipos de radiações. Para assegurar que a finalidade da prática esteja sendo alcançada, são necessários estudos detalhados de detectores e dispositivos que respondam a diferentes tipos de radiações. Neste trabalho foi realizada a caracterização dosimétrica de amostras de BeO utilizando as técnicas de termoluminescência (TL) e luminescência opticamente estimulada (OSL) comparando-se as respostas para as radiações alfa, beta e X e propondose um sistema adequado para sua utilização em monitoração de feixes destas radiações. Dentre os principais resultados obtidos estão: alta sensibilidade à radiação beta para ambas as técnicas empregadas, boa reprodutibilidade das respostas TL e OSL (coeficientes de variação inferiores a 5%), uma dependência energética máxima da radiação X de 28% para técnica TL, e de apenas 7% para a técnica OSL, dentro dos intervalos de energia estudados. As características dosimétricas obtidas neste trabalho mostram a possibilidade de aplicação das amostras de BeO em dosimetria das radiações ionizantes X, alfa e beta, considerando os intervalos de dose empregados, pelas técnicas de TL e OSL. Pelos resultados obtidos, as amostras de BeO apresentaram sua utilização potencial para dosimetria de feixes de radiodiagnóstico e radioterapia. / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP