Made available in DSpace on 2014-10-09T12:45:36Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:09:31Z (GMT). No. of bitstreams: 1 07306.pdf: 9914890 bytes, checksum: 6fe7e1a8d060f6bbbccd63db16915245 (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Fundação de Amparo a Pesquisa do Estado de Minas Gerais / Os radionuclídeos utilizados na tomografia por emissão de posítrons (PET) são produzidos utilizando um acelerador cíclotron. Os nêutrons produzidos durante a operação do cíclotron contribuem para exposição direta ou indireta dos Indivíduos Ocupacionalmente Expostos (IOEs), devido ao aumento da radiação de fundo da casamata. Além disso, há um aumento nas emissões de gases radioativos provenientes da ativação dos elementos do ar dentro da casamata, que quando liberados constitui um problema para radioproteção dos indivíduos do público. Dos vários métodos utilizados para caracterizar o espectro neutrônico, o espectrômetro de multiesferas de Bonner (EB) é um dos sistemas espectrométricos mais utilizados. Neste trabalho foi utilizado o sistema EB com detectores termoluminescentes (TL), do tipo TLD600 e TLD700 como detector de nêutrons, para medir os espectros de energia de nêutrons em quatro pontos no interior da casamata do cíclotron GE PETtrace-8 do Centro de Desenvolvimento da Tecnologia Nuclear (CDTN). Foram realizadas medidas em quatro pontos em torno do cíclotron. Os espectros de nêutrons foram desdobrados utilizando os códigos BUMS, NSDUAZ e BUNKIUT e os resultados convertidos em equivalente de dose ambiente H*(10). Considerando o termo fonte de radiação fornecido pelo fabricante do cíclotron, pôde-se constatar a grande influência dos nêutrons de recuo nos espectros de energia encontrados em todos os pontos. Houve uma boa concordância nos espectros de nêutrons obtidos, utilizando os códigos BUNKIUT (com espectros iniciais retangular e Maxwelliano) e NSDUAZ. Os valores de taxa de fluência encontrados no presente trabalho foram da mesma magnitude dos valores reportados na literatura e são coerentes com os obtidos por cálculos téóricos utilizando o termo fonte de radiação disponibilizado pelo fabricante. Com relação aos valores de equivalente de dose ambiente, as taxas horárias por A (microampère) variaram de aproximadamente 67 mSv/h a 936 mSv/h . Para uma corrente típica de 40 A, esses valores são próximos de 2,7 Sv/h a 37 Sv/h, valores da mesma ordem dos reportados na literatura. A metodologia empregada para a caracterização do campo de radiação em torno do cíclotron do CDTN mostrou-se adequada e pode ser utilizada em mais pontos da casamata, de maneira a descrever melhor o espectro e, consequentemente, estimar o equivalente de dose ambiente. / The radionuclides used in positron emission tomography (PET) are generally produced using a cyclotron accelerator. The operation of the cyclotron produces an undesirable neutron radiation field. The knowledge of the neutron radiation field around not-self-shielded PET cyclotrons is an important issue for optimization of radiation protection of the workers and individuals of the public. For the workers, neutrons contribute not only for immediate radiation exposure as for long-term exposure due to activation of cyclotron components and the concrete in the bunker walls. For the individuals of the public the main concern is the dispersal of radioactive gases produced by activation of the air inside the cyclotron vault. The multisphere system, or Bonner sphere spectrometer (BSS), has been widely used to measure neutron spectrum. The substitution of the active detectors of the BSS system by thermoluminescent detectors (specifically TLD-600 and TLD-700 pairs) has become a reliable procedure in spectrometry of high intensity mixed radiation field. In this study we utilized the BSS system with TLD600 and TLD700 to measure the energy spectra of neutrons at four points inside the bunker of the cyclotron GE PETtrace-8 of the Development Centre of Nuclear Technology (CDTN). Four points inside the bunker of the cyclotron were studied. The neutron spectra were unfolded using codes BUMS, NSDUAZ e BUNKIUT and the results converted to ambient dose equivalent H*(10). Considering the source-term of radiation provided by the manufacturer of the cyclotron, we could see the great influence of room return effect in energy spectra at all points. The values of total fluence rates for all points have the same magnitudes of values reported in the literature and are consistent with those obtained by theoretical calculations using the source-term of radiation provided by the manufacturer of the cyclotron. The ambient equivalent dose rates for 1 A ranged from about 67 mSv/h to 936 mSv/h. For a typical 40 A typical current these values were 2.7 Sv/h and 37 Sv/h. These values are of the same order than the reported in the literature. The methodology utilized in this study to characterize the neutron radiation field around the CDTN cyclotron proved to be adequate and can be used in more points inside the bunker in order to better describe the spectrum and thereby estimate the ambient dose equivalent.

In the breeding of grain sorghum (Sorghum bicolour L. Moench) towards improved nutrition and agronomic performance, new methodologies are required to increase genetic diversity and lower the inputs required to track and screen breeding populations. Near-infrared calibration models were developed by partial least squares (PLS) and test-set validation on 364 sorghum samples to predict crude protein and moisture content on whole-grain and milled flour samples. Models using milled flour spectra were more accurately predictive than those from whole grain spectra for all constituents (eg. Protein: R2 = 0.986 on flour vs R2 = 0.962 on whole grain). Discriminant calibrations were established to classify grain colour using partial least squares discriminant analysis (PLS-DA) based upon CIE L*a*b* reference values and visual ranking. Preliminary calibrations were developed for quantities of 18 amino acids, fat and apparent metabolisable energy (AME) on 40 samples using cross-validation, highlighting potential for reliable calibration for these parameters in sorghum. An investigation into the potential of 12C6+ heavy-ion beam mutagenesis of sorghum seed was undertaken by treatment at RIKEN Accelerator Research Facility (Saitama, Japan) and subsequent breeding at Ukulinga research farm and analysis at the Department of Plant Pathology, University of KwaZulu-Natal, Pietermaritzburg, South Africa. Dosage rates of 75, 100 and 150 Gy were compared in seven sorghum varieties to establish optimal dose treatments as determined by germination and survival rates, visible morphological changes and field data over two seasons of field trials. Crude protein variation within the M2 generation was analysed to compare dose rate effects. The need for higher dose rates was indicated by few quantified differences between treatments and control although good correlations between protein deviation and treatment dose rate were elucidated. Differences in varietal response suggest a need to optimize dose rate for specific varieties in future endeavours. In addition, all mutagenized populations were screened for crude protein content using near-infrared spectroscopy (NIRS). Significant differences in protein levels and standard deviations were observed between treated self-pollinated M2 generations and untreated control populations. Individual plants displaying significantly different protein levels were isolated. / Thesis (M.Sc.)-University of KwaZulu-Natal, Pietermaritzburg, 2009.

Made available in DSpace on 2014-10-09T12:35:06Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:00:42Z (GMT). No. of bitstreams: 0 / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Made available in DSpace on 2014-10-09T12:35:06Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:00:42Z (GMT). No. of bitstreams: 0 / Neste trabalho foi desenvolvido o método de padronização do 123I em sistema de coincidências 4π(X,A)-γ. O 123I foi produzido no cíclotron Cyclone-30 do IPEN CNEN/SP, por meio da irradiação do 124Xe. O 123I decai com uma meia vida de 13,22 horas pelo processo de captura eletrônica seguido da emissão de radiação gama. Foi aplicada a técnica de extrapolação linear da eficiência para determinação da atividade e para determinação do coeficiente de conversão interna total do nível de 159 keV, obtido a partir da inclinação da curva de extrapolação. A curva de extrapolação experimental foi comparada com a simulação de Monte Carlo, executada pelo código ESQUEMA. As fontes radioativas foram também medidas em um sistema de espectrometria de HPGe, a fim de determinar a probabilidade de emissão gama por decaimento para várias transições gama. Todas as incertezas envolvidas e suas correlações foram analisadas aplicando a metodologia de matriz de covariância e os parâmetros medidos foram comparados com os da literatura. / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Thesis (Ph.D.); Submitted to Univ. of California, Berkeley, CA (US); 1 Jun 2003. / Published through the Information Bridge: DOE Scientific and Technical Information. "LBNL--54350" Scielzo, Nicholas David. USDOE Director. Office of Science. Nuclear Physics (US) 06/01/2003. Report is also available in paper and microfiche from NTIS.