Um detetor HPGe foi calibrado na faixa de energia 4 a 10 MeV usando fótons provenientes do decaimento do produto da reação 27Al(p, g)28Si em linha, observando as ressonâncias com prótons de energias 992 e 1317 keV. Foram feitas calibrações de energia e eficiência de deteção de fótons e foi analisada a dependência da largura a meia altura dos picos com a meia vida do estado inicial e a energia da transição. Os efeitos do produto da reação estar em movimento, como o efeito Doppler no decaimento em vôo, perda de velocidade do núcleo ao recuar dentro do alvo e energia de recuo são importantes na calibração de energia e análise da largura do pico. A calibração da eficiência depende de outras calibrações: razão entre a área dos picos de absorção total de energia, escapes simples e duplo dos gamas de aniquilação; razão entre a área total do espectro pela área do pico. Os resultados experimentais foram comparados com simulações do espectro usando o código MCNP, sendo que as dimensões internas do detetor, inacessíveis para medição, foram escolhidas de modo a reproduzir parâmetros deduzidos de espectros gama experimentais. A simulação se mostrou capaz de descrever tanto a eficiência para absorção total de energia quanto a razão entre as áreas dos picos de absorção total de energia, escape simples e duplo do gama de aniquilação, mas não foi capaz de descrever a razão entre a área total do espectro e a do pico. / An HPGe detector was calibrated in the 4 to 10 MeV energy range using photons from the decay of the 992 and 1317 keV proton resonances in the reaction 27Al(p, g)28Si on-line. Energy and photon detection efficiencies were calibrated and the dependence of the peak full width at half maximum on the transition energy and initial level half-life was analyzed. The effects of the reaction product motion, like Doppler shift due to in-flight decay, slowing down in the target, and nuclear recoil energy from photon emission, are important for energy calibration and peak width analyses. The efficiency calibration required other calibrations: the full energy peak to single and double escape counting ratios, and total spectrum to peak areas ratio. The experimental results were compared to simulations with MCNP code, where internal detector dimensions, inaccessible to measurement, were chosen in order to fit the experimental gamma spectrum parameters. The simulation was able to explain the full energy peak to single escape and double escape counting ratios, and full-energy peak detection efficiency, but was unable to fit the total spectrum to peak areas ratio.

A dosimetria de pacientes associada à avaliação das condições de funcionamento dos equipamentos médicos e aos procedimentos empregados na realização dos exames, desempenha um papel fundamental no sistema de proteção radiológica das exposições médicas. Nesse sentido, foi realizado um levantamento em grande escala das doses recebidas pelos pacientes submetidos a exames radiológicos convencionais realizados em uma amostra representativa de estabelecimentos de saúde do estado de São Paulo. Nesse levantamento foi empregado um kit dosimétrico postal originalmente desenvolvido, que permitiu a determinação da dose de entrada na pele (DEP) através da técnica de dosimetria termoluminescente. Paralelamente foram realizadas visitas in-loco a uma sub-amostra de estabelecimentos, onde as condições de funcionamento dos equipamentos de raios X médicos e do sistema de imagem foram avaliadas empregando-se procedimentos e equipamentos já estabelecidos em protocolos de controle de qualidade. O estudo completou-se com a elaboração de um catálogo de espectros na faixa de energia do radiodiagnóstico, que, através de procedimento desenvolvido, permitiu inferir espectros equivalentes em equipamentos médicos. Na determinação dos espectros foi empregado um detector semicondutor de telureto de cádmio e zinco (CdZnTe), cujas curvas de eficiência e escape foram determinadas experimentalmente para realização do processo de correção dos espectros (stripping procedure). O processo de amostragem de estabelecimentos de saúde realizado neste estudo permitiu verificar a distribuição de equipamentos de diagnóstico por imagem e a freqüência de exames radiológicos no estado de São Paulo. A partir desses resultados foram escolhidos os exames de tórax, crânio (e seios da face) e coluna para avaliação de DEP, uma vez que os mesmos apresentam as maiores freqüências anuais de exames por 1.000 habitantes: 100, 46 e 29, respectivamente. Na técnica de amostragem dos estabelecimentos de saúde incluídos neste estudo foi empregado como critério de estratificação a quantidade anual de exames radiológicos associados ao município de localização do estabelecimento. Do total de 200 estabelecimentos sorteados, 50 participaram da primeira etapa e 38 da segunda. Um total de 83 salas de exames (ou equipamentos) e 868 pacientes foram incluídos, e um conjunto de 1415 valores de DEP foi determinado. O resultado da distribuição dos valores de DEP permitiu determinar os chamados níveis de referência, que, no caso de pacientes adultos, se mostraram bastante semelhantes aos encontrados em outros estudos internacionais. No caso de pacientes infantis, a situação é bem diferente, obtendo-se valores pelo menos 2 vezes superiores a outros recomendados internacionalmente para a radiografia infantil mais freqüente (tórax). Esse fato sugere que as práticas empregadas na realização dos exames devem ser revisadas e que recomendações específicas a esse grupo de pacientes, a partir de estudos dirigidos, sejam publicadas. Constatou-se também alguns casos de DEP elevada pelo uso desnecessário de radioscopia de localização. Os testes de desempenho dos equipamentos e a avaliação das imagens realizadas sugerem que há possibilidade de melhoria das condições de realização dos exames, sem perda de informação diagnóstica presente na imagem e com redução das doses. Alguns espectros de raios X determinados experimentalmente apresentaram divergência em relação a outros catálogos já estabelecidos, numa faixa específica de energia do espectro (entre 25 e 40 keV). Para a sua utilização em situações práticas há necessidade de algumas correções na curva de eficiência, o que não inviabiliza a metodologia e os procedimentos estabelecidos. De forma geral, os resultados encontrados neste estudo permitem traçar um panorama das exposições médicas em radiologia convencional no estado de São Paulo, contribuindo para o aperfeiçoamento de futuras pesquisas que sejam realizadas na área, ou mesmo, para a implementação de políticas públicas. / Patients dosimetry, associated with the assessment of the performance of the radiological equipment and of the series of procedures employed in the accomplishment of the examinations, plays fundamental role in the radiation protection system of medical exposures. Therefore, a large-scale survey of absorbed doses was carried out in health services localized in the state of São Paulo, including patients submitted to conventional radiological examinations. In this survey a postal dosimetric kit, originally developed, was employed. It allows the evaluation of the entrance surface dose (ESD) to patients with thermoluminescence dosimeters. Also a series visits to a sub-sample of services was carried out, giving rise to the in-loco evaluation of the performance of the medical x-ray equipment and of the image system, using procedures and equipments already established in protocols of quality control. The study is completed with the elaboration of a catalogue of x-ray spectra, which provides means to infer the spectra generated by medical x-ray equipments. Measurements of x-ray spectra were carried out with a cadmium zinc telluride detector (CdZnTe), and the stripping procedure was performed taking into account both the contributions of efficiency and x-ray escape fraction, experimentally determined in this work. The stratified sampling technique furnished important data on the distribution of equipments and the annual frequency of examinations performed in the state of São Paulo. From these results radiological examinations of the chest, skull and sinus, and spine were selected for the evaluation of ESD, as their annual frequencies are the highest observed: 100, 46 and 29 per thousand inhabitants, respectively. The number of x-ray examinations carried out annually in the cities of the state was employed as the stratification criterion to construct the sample. From a total of 200 health services sampled, 50 agreed to participate of the first stage, and 38 of the second. A total of 83 rooms (or x-ray equipments) and 868 patients was included, and a set of 1415 values of ESD was measured. Diagnostic reference levels were determined with the outcomes of the distribution of ESD. For adult patients, the reference levels achieved are very similar to others obtained in international surveys. However, as far as pediatric patients are concerned, the situation is very different: the values found in this survey are twice larger than the international recommendations to chest radiography of children. This points out that the practices need to be revised and that specific recommendations to this patient group, following specific surveys, should be provided. Also, a series of high ESD values due to unnecessary localizing radioscopy were detected among our data. The results of the equipment performance tests and of the evaluation of image quality suggest that it is possible to improve the conditions of the examinations and to reduce doses to patients, without impairment of the diagnostic information. Some of the experimentally determined x-ray spectra show a discrepancy, when compared to other catalogue spectra, in a particular energy range 25 to 40 keV. The practical application of them will require some corrections in the efficiency curve, but the established methodology and procedures remain legitimate. In an extensive approach, the results of this study supply a panorama of medical exposures in conventional radiology in the state of São Paulo, contributing with resources to future research in the field and also to governmental actions.

Este trabalho teve como objetivo validar uma ferramenta computacional para a realização de simulações da interação de elétrons e da radiação X com a matéria, utilizando o método de Monte Carlo para possíveis estudos em radiologia diagnóstica. Para esse propósito, foi desenvolvido um programa computacional que simula a produção de radiação de um equipamento de raios X, com a finalidade de obter a distribuição de energia dos fótons que alcançam uma determinada região de interesse, sem a necessidade de medições experimentais. Outra tarefa realizada neste trabalho foi o cálculo da resposta de um detector do tipo CdTe, para possibilitar a correção de espectros medidos com esse detector em experimentos na faixa de energia de radiodiagnóstico. A ferramenta computacional escolhida para essas aplicações foi o Geant4, que é um conjunto de programas de distribuição livre relativamente novo e que é utilizado para simulações da interação da radiação com a matéria. Um dos principais diferenciais do Geant4 é o emprego da tecnologia de programação orientada a objetos e de técnicas avançadas de engenharia de software. Os resultados da etapa de simulação de espectros de energia produzidos por um equipamento de raios X mostram que o Geant4 pode ser utilizado para esta aplicação, mas com ressalvas na simulação de espectros de raios X com alvos com molibdênio para a região de mamografia, que é a situação onde as diferenças dos rendimentos de raios X característicos dos espectros simulados com os seus respectivos espectros de referência são maiores. Na etapa de simulação da detecção da radiação X por um detector do tipo CdTe são apresentados resultados com excelente acordo com os dados de referência. As diferenças encontradas devem ser mais influenciadas pelos efeitos de armadilhamento de cargas e do comportamento do campo elétrico no interior do cristal do detector, que são específicos para este detector e não fazem parte dos modelos físicos fornecidos pelo Geant4. Desta forma, a validação do Geant4 realizada neste trabalho mostrou algumas das possibilidades de uso desta versátil ferramenta na área de radiologia diagóstica. / The aim of this work was the validation of a computational tool applied in simulations of electrons and X ray interactions with matter, using the Monte Carlo method for possible studies in diagnostic radiology. To perform this task, a computational program was developed to simulate the radiation production of a X ray equipment, with the purpose of obtaining the photon energy distribution which comprehends the region of interest, without the necessity of experimental measurements. Another task carried through in this work was the calculation of a CdTe detector response, which was used in the correction of measured spectra with energy distribution typically found in diagnostic radiology. The employed computational tool was Geant4, which is a free distribution set of computational programs used for simulation of the passage of particles through matter. One of the main differentials of Geant4 is the exploitation of advanced software-engineering techniques and object-oriented technology. The results of the simulation of energy spectra produced by a X ray equipment show that Geant4 can be used for this application, but with restrictions concerning the simulation of X ray spectra from molybdenum targets in the mammography energy range. This is the situation where the differences of the characteristic X ray yield between the simulated and reference spectra are more pronounced. For the simulation of X ray measurements with a CdTe detector, the results showed excellent agreement with the reference data. In this case the discrepancies must be originated mainly by effects of charge trapping and the nonuniformity of the electric field inside the CdTe crystal. In resume, the validation of the Geant4 carried through in this work showed some of the possibilities for the use of this versatile tool in diagnostic radiology.

Um detetor HPGe foi calibrado na faixa de energia 4 a 10 MeV usando fótons provenientes do decaimento do produto da reação 27Al(p, g)28Si em linha, observando as ressonâncias com prótons de energias 992 e 1317 keV. Foram feitas calibrações de energia e eficiência de deteção de fótons e foi analisada a dependência da largura a meia altura dos picos com a meia vida do estado inicial e a energia da transição. Os efeitos do produto da reação estar em movimento, como o efeito Doppler no decaimento em vôo, perda de velocidade do núcleo ao recuar dentro do alvo e energia de recuo são importantes na calibração de energia e análise da largura do pico. A calibração da eficiência depende de outras calibrações: razão entre a área dos picos de absorção total de energia, escapes simples e duplo dos gamas de aniquilação; razão entre a área total do espectro pela área do pico. Os resultados experimentais foram comparados com simulações do espectro usando o código MCNP, sendo que as dimensões internas do detetor, inacessíveis para medição, foram escolhidas de modo a reproduzir parâmetros deduzidos de espectros gama experimentais. A simulação se mostrou capaz de descrever tanto a eficiência para absorção total de energia quanto a razão entre as áreas dos picos de absorção total de energia, escape simples e duplo do gama de aniquilação, mas não foi capaz de descrever a razão entre a área total do espectro e a do pico. / An HPGe detector was calibrated in the 4 to 10 MeV energy range using photons from the decay of the 992 and 1317 keV proton resonances in the reaction 27Al(p, g)28Si on-line. Energy and photon detection efficiencies were calibrated and the dependence of the peak full width at half maximum on the transition energy and initial level half-life was analyzed. The effects of the reaction product motion, like Doppler shift due to in-flight decay, slowing down in the target, and nuclear recoil energy from photon emission, are important for energy calibration and peak width analyses. The efficiency calibration required other calibrations: the full energy peak to single and double escape counting ratios, and total spectrum to peak areas ratio. The experimental results were compared to simulations with MCNP code, where internal detector dimensions, inaccessible to measurement, were chosen in order to fit the experimental gamma spectrum parameters. The simulation was able to explain the full energy peak to single escape and double escape counting ratios, and full-energy peak detection efficiency, but was unable to fit the total spectrum to peak areas ratio.

O presente estudo teve como objetivo avaliar, in vitro, os efeitos da radiação com cobalto-60 nas propriedades mecânicas, morfológicas e químicas do esmalte e da dentina de dentes permanentes através da: 1- microdureza longitudinal; 2- microscopia eletrônica de varredura (MEV); e 3- espectroscopia de energia dispersiva de raios X (EDX). A microdureza do esmalte e da dentina (n=12 hemissecções vestibulares) foi avaliada em três profundidades (superficial, média e profunda), antes e a cada 10 Gy de irradiação, até uma dose cumulativa de 60 Gy. A morfologia do esmalte e da dentina foi avaliada por meio de MEV (n=8 hemissecções), em 2 hemissecções vestibulares irradiadas com dose cumulativa de 30 Gy, 2 hemissecções vestibulares irradiadas com dose cumulativa de 60 Gy e 4 hemissecções palatinas não irradiadas. A composição química do esmalte e da dentina foi avaliada por meio de EDX (n=4 hemissecções), utilizando-se as mesmas hemissecções previamente submetidas à MEV (com dose cumulativa de 60 Gy de irradiação, e nas hemissecções não irradiadas). Os dados foram analisados quanto à sua distribuição e submetidos à Análise de Variância a dois critérios. Para a diferenciação das médias, empregou-se o teste de Fisher. O nível de significância adotado foi de 5%. Com relação à microdureza no esmalte, pôde-se observar que houve diferença estatisticamente significante entre os grupos (p < 0,05). A microdureza no esmalte não irradiado não apresentou diferença estatisticamente significante em comparação com a do esmalte após irradiação com doses de 40, 50 e 60 Gy (p > 0,05), e apresentou-se maior que os valores de microdureza nas doses de 10, 20 e 30 Gy (p < 0,05). Com relação à microdureza nas diferentes profundidades pôde-se observar diferença significante (p < 0,05) entre elas, observando-se no esmalte superficial seus maiores valores. Na análise morfológica do esmalte observou-se que os espécimes irradiados apresentaram alterações crescentes, em função do aumento da dose de radiação, em comparação ao esmalte não irradiado. A porção interprismática tornou-se mais evidente após as doses de 30 e 60 Gy. Em relação à microdureza da dentina, pôde-se observar que houve diferença significante entre os grupos (p < 0,05). A microdureza na dentina não irradiada não apresentou diferença estatisticamente significante em comparação com a microdureza na dose de 40 Gy (p > 0,05) e apresentou valores superiores aos observados nas doses de 10, 20, 30, 50 e 60 Gy (p < 0,05). Em relação à microdureza nas diferentes profundidades avaliadas pôde-se observar diferença significante (p < 0,05) entre elas, sendo que a dentina média apresentou seus maiores valores. Na análise morfológica da dentina observou-se a presença de fendas na estrutura dentinária, túbulos dentinários colabados/destruídos e fragmentação das fibras colágenas nas doses de 30 e 60 Gy, sendo as alterações mais intensas com aumento da dose de irradiação, para todas as regiões analisadas, em comparação à dentina não irradiada. Na análise química do esmalte e da dentina irradiados observou-se discreto aumento de oxigênio (O) e diminuição de fósforo (P) e cálcio (Ca), em comparação aos espécimes não irradiados. Os resultados permitiram concluir que a radioterapia não influenciou a microdureza do esmalte, como um todo, entretanto, quando analisou-se nas diferentes profundidades do esmalte, verificou-se um aumento da microdureza na região superficial. Na dentina, a radioterapia ocasionou diminuição da microdureza após praticamente todas as doses de radiação, em comparação à dentina não irradiada, sendo que na região da dentina média observaram-se seus menores dos valores. As alterações morfológicas das estruturas do esmalte e da dentina foram crescentes com o aumento das doses de irradiação observando-se a porção interprismática mais evidente, presença de fendas e túbulos dentinários colabados/destruídos e fragmentação progressiva das fibras colágenas. Quimicamente, após a irradiação, tanto no esmalte como na dentina, observouse um discreto aumento na porcentagem de oxigênio e redução nas porcentagens de fósforo e cálcio. / The present study had as objective to evaluate, in vitro, the effect of the radiation of 60 Cobalt (Co 60) in the mechanical, morphological and chemical properties of the enamel and of the dentine of permanent teeth by means of: 1- longitudinal microhardness; 2- scanning electron microscopy (SEM); and 3; energy dispersive X-ray spectroscopy (EDX). The microhardness of the enamel and of the dentine (n = 12 vestibular hemisections) was evaluated in three depths (superficial, medium and deep), before and at each 10 Gy of irradiation, until a total cumulative dose of 60 Gy. The morphology of the enamel and of the dentine was evaluated by means of a SEM (n = 8 hemisections), in 2 irradiated vestibular hemisections with total cumulative dose of 30 Gy, 2 irradiated vestibular hemisections with total cumulative dose of 60 Gy and 4 not irradiated palatine hemisections (control). The chemical composition of the enamel and of the dentine was evaluated by means of EDX (n = 4 hemisections), using the same hemisections previously submitted to SEM (with cumulative dose of 60 Gy of irradiation, and in the not irradiated hemisections). The data were analyzed about their distribution and submitted to the Analysis of Variance at two criteria. For the differentiation of the averages, the test of Fisher was used. The level of significance adopted was of 5%. About the longitudinal microhardness in the enamel, it was possible to be observed that there was no statistically significant difference between the groups (p < 0,05). The microhardness in the not irradiated enamel was similar to the enamel after the irradiation with doses of 40, 50 and 60 Gy (p > 0,05) and higher than the microhardness values in the doses of 10, 20, e 30 Gy (p < 0,05). About the microhardness in the different depths it was observed significant difference (p < 0,05) between them, being observed in the superficial enamel the greatest values of microhardness. In the morphological analysis of the enamel it was observed that the irradiated specimens presented growing alterations, due to the increase of the radiation dose, comparing to the not irradiated enamel. There was no difficulty in observing the prisms and the crystals after the irradiation, however the interprismatic portion became more evident after the radiation doses of 30 and 60 Gy. About the longitudinal microhardness of the dentine, it could be observed that there was significant difference between the groups (p < 0,05). The microhardness of the not irradiated dentine was not statistically significant compared to the microhardness in the dose of 40 Gy (p > 0,05) and it presented higher values to the observed ones in the doses of 10, 20, 30, 50 and 60 Gy (p < 0,05). About the relation to the microhardness in the different evaluated depths it was possible to observe significant difference (p < 0,05) among them, being that the medium dentine presented the highest values of microhardness. In the morphological analysis of the dentine it was observed the presence of cracks in the dentine structure, collapsed/destroyed dentine tubules and fragmentation of the collagen fibers in the doses of 30 and 60 Gy, being the alterations more intense with the increase of the dose of irradiation, for all the analyzed regions, comparing to the not irradiated dentine. In the chemical analysis of the irradiated enamel and the dentine it was observed the slight increase of oxygen (O) and decrease of phosphorus (P) and Calcium (Ca), comparing to the not irradiated specimens. The result allowed to be concluded that the radiotherapy occasioned the decrease of the microhardness of the enamel after the doses from 10 to 30 Gy, but in the following doses there was an increase of the microhardness, which became similar to the not irradiated enamel, being that in the superficial region it was observed the biggest increase of the microhardness. In the dentin, the radiotherapy caused decrease of the microhardness after practically all doses of radiation, comparing to the not irradiated dentine, being that in the region of the medium dentine the lowest values of microhardness were observed. The morphological alterations of the enamel and of the dentine structure were growing with the increase of the radiation doses observing the more evident interprismatic portion, presence of cracks and collapsed/destroyed dentine tubules and progressive fragmentation of collagen fibers. Chemically, after the irradiation, not only in the enamel but also in the dentin, it was observed a slight increase of percentage of the oxygen and decrease in the percentages of phosphorus and calcium.

The new millennium has seen revolutionary advances in photonsource technology. As the newly constructed synchrotron facilityMAX IV in Lund, Sweden, pushes brilliance toward what isphysically possible, low-yield spectroscopic techniques, such asresonant inelastic X-ray scattering (RIXS), open new doors inmolecular and condensed matter research. The VERITAS beamline atMAX IV is designed for high-resolution vibrational RIXS on gases.X-rays interact with flowing molecules inside a window-cappedcell, but the radiation intensity is expected to be large enoughto damage the windows, and cause build-up of photochemicalproducts, which lowers transmission. To address these issues, anovel gas cell design is presented, wherein the distance betweensample gas and window is increased by using a flowing heliumbuffer. The main challenge is maintaining a steep sample gasconcentration gradient within the cell, and to that end, gas flowswere simulated on various geometries by using the finite elementmethod to solve the Navier-Stokes equations. Results were used toconstruct a prototype, and confocal Raman microscopy was used forconcentration characterization. Preliminary measurements revealeda uniform sample gas distribution, and the technique proved to beinefficient for wide scanning of parameter values. This suggeststhat a supplementary experiment is required to find roughestimates of good parameter values, which can then be followed upwith new Raman measurements for fine-tuning of the properparameter space. Real-time visualization of the sample gas flow,using a visible gas under an optical microscope, is one candidatefor this supplementary experiment.

<p>Presently there is a clear trend of increasing demands on in-pile performance of nuclear fuel. Higher target burnups, part length rods and various fuel additives are some examples of this trend. Together with an increasing demand from the public for even safer nuclear power utilisation, this implies an increased focus on various experimental, preferably non-destructive, methods to characterise the fuel.</p><p>This thesis focuses on the development and experimental evaluation of such methods. In its first part, the thesis presents a method based on gamma-ray spectroscopy with germanium detectors that have been used at various power reactors in Europe. The aim with these measurements is to provide information about the thermal power distribution within fuel assemblies in order to validate core physics production codes. The early closure of the Barsebäck 1 BWR offered a unique opportunity to perform such validations before complete depletion of burnable absorbers in Gd-rods had taken place. To facilitate the measurements, a completely submersible measuring system, LOKET, was developed allowing for convenient in-pool measurements to be performed.</p><p>In its second part, the thesis describes methods that utilise in-pile measurements. These methods have been used in the Halden test-reactor for determination of fission gas release, pellet-cladding interaction studies and fuel development studies.</p><p>Apart from the power measurements, the LOKET device has been used for fission gas release (FGR) measurements on single fuel rods. The significant reduction in fission gas release in the modern fuel designs, in comparison with older designs, has been demonstrated in a series of experiments. A FGR database covering a wide range of burnup, power histories and fuel designs has been compiled and used for fuel performance analysis. The fission gas release has been measured on fuel rods with average burnups well above 60 MWd/kgU. The comparison between core physics calculations (PHOENIX-4/POLCA-7) and the in-pool measurements of thermal power indicates that the nodal power can generally be predicted with an accuracy within 4% and the bundle power with an accuracy better than 2%, expressed as rms errors.</p><p>In-pile experiments have successfully simulated the conditions that occur in a fuel rod following a primary debris failure, being secondary fuel degradation. It was concluded that massive hydrogen pick-up takes place during the first few days following the primary failure and that a pre-oxidized layer does not function as a barrier towards hydriding in an environment with a very high partial pressure of hydrogen. Another series of in-pile experiments clearly indicate that increased UO₂ grain size is an effective way of suppressing fission gas release in LWR fuel up to the burnup level covered (55 MWd/kgUO₂).</p>

This study is aimed at investigating the feasibility of using the radiometric technique as an alternative to traditional methods for determining soil physico-chemical parameters which are important for terroir characterization. In-situ and ex-situ radiometric analyses of soil from three vineyard blocks of Simonsig Wine Estate in the Stellenbosch district (Western Cape, South Africa) were studied. A mobile MEDUSA gamma-ray detection system comprising a CsI(Na) crystal (length 15 cm, diameter 7 cm) and associated electronics mounted on a portable trolley were used for partial terroir characterisation. Thereafter activity concentrations of 40K, 232Th series and 238U series in soil (top ~30 cm) from the measured MEDUSA spectra (0 – 3 MeV) were extracted by means of the full-spectrum analysis (FSA) method. A lead-shielded HPGe detector was used for analyzing collected soil samples while soil physico-chemical parameters were analysed using standard methods at research and commercial laboratories.

Presently there is a clear trend of increasing demands on in-pile performance of nuclear fuel. Higher target burnups, part length rods and various fuel additives are some examples of this trend. Together with an increasing demand from the public for even safer nuclear power utilisation, this implies an increased focus on various experimental, preferably non-destructive, methods to characterise the fuel. This thesis focuses on the development and experimental evaluation of such methods. In its first part, the thesis presents a method based on gamma-ray spectroscopy with germanium detectors that have been used at various power reactors in Europe. The aim with these measurements is to provide information about the thermal power distribution within fuel assemblies in order to validate core physics production codes. The early closure of the Barsebäck 1 BWR offered a unique opportunity to perform such validations before complete depletion of burnable absorbers in Gd-rods had taken place. To facilitate the measurements, a completely submersible measuring system, LOKET, was developed allowing for convenient in-pool measurements to be performed. In its second part, the thesis describes methods that utilise in-pile measurements. These methods have been used in the Halden test-reactor for determination of fission gas release, pellet-cladding interaction studies and fuel development studies. Apart from the power measurements, the LOKET device has been used for fission gas release (FGR) measurements on single fuel rods. The significant reduction in fission gas release in the modern fuel designs, in comparison with older designs, has been demonstrated in a series of experiments. A FGR database covering a wide range of burnup, power histories and fuel designs has been compiled and used for fuel performance analysis. The fission gas release has been measured on fuel rods with average burnups well above 60 MWd/kgU. The comparison between core physics calculations (PHOENIX-4/POLCA-7) and the in-pool measurements of thermal power indicates that the nodal power can generally be predicted with an accuracy within 4% and the bundle power with an accuracy better than 2%, expressed as rms errors. In-pile experiments have successfully simulated the conditions that occur in a fuel rod following a primary debris failure, being secondary fuel degradation. It was concluded that massive hydrogen pick-up takes place during the first few days following the primary failure and that a pre-oxidized layer does not function as a barrier towards hydriding in an environment with a very high partial pressure of hydrogen. Another series of in-pile experiments clearly indicate that increased UO2 grain size is an effective way of suppressing fission gas release in LWR fuel up to the burnup level covered (55 MWd/kgUO2).

The nucleus is a mesoscopic system that retains features from both the quantum and macroscopic worlds. A basic property of a macroscopic body is its shape. Nuclear shapes can be deduced from experimental data as they influence the excitation mode of the nucleus and hence the energies and lifetimes of its excited levels. Various short-lived nuclei were created in fusion-evaporation experiments performed at international heavy-ion accelerator facilities. The emitted γ rays and, in some experiments, also the charged particles and neutrons emitted in the reactions were detected. The studied neutron-deficient isotopes were either selected by the type and number of particles emitted in the reactions, or by using their characteristic decays. The excited states of the different isotopes were extracted from the γ-ray analyses. Spectroscopic properties, such as the lifetimes of the excited states or the angular distribution of the emitted γ rays were measured when possible. The experimentally obtained level schemes together with the other spectroscopic information were used to deduce the excitation modes and the shapes of the studied nuclei. The detector systems are described in the first chapter and in the second chapter some techniques used to extract information from the experimental data are explained. Finally, a brief theoretical overview on the nuclear models which were used to interpret the experimental results is given. / QC 20100621