A basic requirement for all therapeutic applications of ionizing radiation is the high accuracy of delivery of the prescribed dose to the target volume of tissue healing. Each radiotherapy department must have in the quality assurance program developed methodology for testing the operational stability, which are reviewed and approved by The State Office for Nuclear Safety (SÚJB). A part of testing the operational stability of linear accelerators is also a regular assessment and measurement of parameters of radiation field, which is done by measuring the dose profiles. The thesis presents the results of measurement and evaluation of photon beam dose profiles of a linear accelerator, measured using the line-semiconductor detector (LDA-99SC company IBA) in the automatic water phantom under the reference conditions and their comparison with results obtained from measurement with the ionization chamber under the same terms of reference. The advantage of using a linear detector is a semiconductor that consists of 99 individual detectors in one line at a distance of 5 mm from each other and is able to measure the radiation dose profile field in a much shorter time than using an ionization chamber, where only one detector output can measure dose point after point. Usage of any other independent system for...

Bisphenol A (BPA) is widely used in the production of plastics, epoxy resins and polycarbonates. It is a toxic, endocrine disruptor compound. Different studies have shown the presence of BPA in several environmental systems, classifying it as a worldwide persistent pollutant which may act synergistically with other pollutants. In this context, advanced oxidation processes (AOP) have received great attention due to their ability to degrade pollutants with such characteristics, through their transformation into less hazardous compounds or even their mineralization. Although there are investigations on the use of AOPs for BPA degradation, systematic studies on the effects of process variables, coupled with the statistical interpretation of the results are virtually non-existent. Furthermore, to the best of our knowledge, a rigorous kinetic model has not yet been proposed for the degradation of this pollutant by the H2O2/UV process. The objective of this work was to evaluate BPA degradation by the H2O2/UV process, investigating the effects of the initial H2O2 concentration and the specific rate of photons emission (EP,0) by means of a Doehlert experimental design, combined with the response surface methodology. The experiments were performed in a photochemical tubular reactor equipped with a 254-nm UV lamp, for [H2O2]0 and EP,0 in the ranges 1.6-9.6 mmol L-1 and 0.87 × 1018-3.6 × 1018 photons L-1 s-1, respectively. Total BPA degradation was achieved after 60 min of irradiation in all experiments. The best conditions were [H2O2]0 = 7.6 mmol L-1 and EP,0 = 3.6 × 1018 photons L-1 s-1, for which the best performance was obtained regarding the BPA degradation rate, BPA degradation after 15 min, and the second highest TOC removal after 180 min. However, in most experiments less than 75% TOC removal was observed, with 95% mineralization obtained only for the superior [H2O2]0 and EP,0. A mathematical model was developed, considering the reactor characteristics and the radiation field, based on the line source with parallel emission (LSPP) approach, in combination with the radiative transfer equation (RTE), mass balances, and a detailed kinetic model of the H2O2/UV process. The steady-state approximation was applied for all radical species. In the estimation of unknown kinetic constants, the non-linear least squares method was employed. The model was able to satisfactorily fit experimental BPA and H2O2 concentrations as a function of time. This work shows that the H2O2/UV process is a good alternative for BPA removal from aqueous streams, with total degradation of the target compound and adequate percent mineralization under optimal operating conditions. Such conditions may serve as first guidelines for pilot-plant and industrial processes operation. In addition, simulations using the proposed kinetic model may provide useful information for the design and scale-up of pre- or post-treatment of effluents containing this pollutant. / O bisfenol A (BPA) é amplamente utilizado na fabricação de plásticos, resinas epóxi e policarbonatos. Trata-se de um composto tóxico e um desregulador endócrino. Diferentes estudos evidenciam a presença do BPA em diversos compartimentos ambientais em todo planeta, identificando-o como um poluente persistente e resistente à degradação biológica, que apresenta efeitos sinergéticos com outros poluentes. Nesse contexto, os processos oxidativos avançados (POA) têm recebido atenção devido a sua capacidade em degradar poluentes com tais características, transformando-os em compostos menos perigosos ou até mesmo mineralizando-os totalmente. Apesar de haver trabalhos na literatura acerca da utilização de POA para degradação de BPA, estudos sistemáticos dos efeitos de variáveis de processo junto com a interpretação estatística dos resultados são virtualmente inexistentes. Além disso, até onde se sabe um modelo cinético rigoroso ainda não foi proposto para a degradação desse poluente por meio do processo H2O2/UV. Este trabalho teve por objetivo avaliar a degradação do BPA pelo processo H2O2/UV, investigando os efeitos da concentração inicial de H2O2 e da taxa específica de emissão de fótons (EP,0) por meio de um projeto experimental Doehlert, combinado com a análise de superfície de resposta. Os experimentos foram realizados em um reator tubular fotoquímico equipado com uma lâmpada UV de 254 nm, para [H2O2]0 e EP,0 entre 1,6-9,6 mmol L-1 e 0,87 × 1018 - 3,6 × 1018 fótons L-1 s-1, respectivamente. Todos os experimentos sob H2O2/UV resultaram em total degradação do BPA após 60 min de irradiação. Nesse caso, as melhores condições foram [H2O2]0 = 7,6 mmol L-1 e EP,0 = 3,6 × 1018 fótons L-1 s-1, para as quais se obteve o melhor desempenho quanto à taxa de degradação de BPA e à remoção após 15 min, e a segunda maior remoção de COT após 180 min. Entretanto, na maioria dos experimentos menos de 75% de remoção de COT foram observados, com 95% de mineralização obtida apenas para os maiores [H2O2]0 e EP,0. Elaborou-se um modelo matemático que considera as características do reator utilizado e o campo de radiação, baseado no modelo de fonte linear de emissão em planos paralelos (LSPP), combinado à equação de transferência radiativa (RTE), aos balanços materiais e a um modelo cinético detalhado do processo H2O2/UV. Foi empregada a aproximação de estado estacionário para todas as espécies radicalares. Na estimativa das constantes cinéticas desconhecidas, utilizou-se o método de mínimos quadrados não linear. Esse modelo foi capaz de ajustar satisfatoriamente as concentrações experimentais de BPA e de H2O2 em função do tempo. Este trabalho mostra que o processo H2O2/UV constitui uma alternativa conveniente para a degradação de BPA em matrizes aquosas, com total degradação do composto alvo e porcentagem de mineralização adequada nas condições ótimas de operação. Tais condições podem servir como diretrizes iniciais de processamento em escalas piloto e industrial. Por sua vez, simulações empregando o modelo matemático proposto permitem gerar informações úteis para projeto e aumento de escala de processos de pré- ou pós-tratamento de efluentes contendo esse poluente.

La mesure de la dose ionisante est aujourd'hui une tâche cruciale pour une large gamme d'applications fonctionnant dans des environnements de rayonnement sévères. Dans le contexte de l'amélioration de la luminosité du grand collisionneur de hadrons (LHC), la mesure des niveaux de rayonnement le long du complexe d'accélérateurs du CERN va devenir encore plus difficile. A cet effet, une connaissance plus détaillée du champ de rayonnement dans le tunnel de l'accélérateur et ses zones adjacentes devient nécessaire pour définir les exigences d'installation, de déplacement ou de blindage de l'électronique sensible au rayonnement. Dans l’objectif d’améliorer la mesure de la dose absorbée par les systèmes exposés au champ de rayonnement mixte généré par l’accélérateur, des investigations sur des nouveaux dosimètres ont été menées.Dans le cadre de cette recherche, deux dispositifs ont été étudiés et caractérisés pour être utilisés comme dosimètres et éventuellement pour compléter l'utilisation du dosimètre au silicium actuellement utilisé au CERN, à savoir le RADFET (RADiation-sensitive Field Effect Transistor) : un NMOS commercial et un ASIC (Application-specific Integrated Circuit) nommé FGDOS. Les dispositifs ont été sélectionnés selon deux approches opposées : d'une part, la réduction des coûts permettrait d'augmenter la densité des capteurs déployés. En conséquence directe, une carte des doses plus détaillée serait obtenue pour les grands systèmes distribués comme le LHC. D'autre part, la dosimétrie peut être améliorée en déployant des détecteurs plus sensibles, ce qui permettrait de mesurer la dose lorsque les niveaux sont trop faibles pour le RADFET. De plus, des capteurs à plus haute résolution permettraient de caractériser le champ de rayonnement dans un temps plus court, c'est-à-dire avec une luminosité intégrée plus faible.La première approche a été réalisée en recherchant des solutions alternatives basées sur des dispositifs COTS (Commercial Off-The-Shelf), qui réduiraient considérablement les coûts et garantiraient une disponibilité illimitée sur le marché. À cette fin, des recherches ont été menées sur un transistor NMOS discret commercial, qui s'est révélé très sensible au rayonnement.La nécessité d'améliorer la résolution de la mesure de dose a conduit à étudier le FGDOS, un dosimètre en silicium innovant à très haute sensibilité qui permet de détecter des doses extrêmement faibles.La calibration du transistor NMOS et du FGDOS a été effectuées en exposant les dosimètres à des rayons gamma. Leur réponse au rayonnement a été caractérisée en termes de linéarité, de variabilité d'un lot à l'autre et d'effet du débit de dose. L'influence de la température a été étudiée et une méthode pour compenser l'effet de la température a été développée et mise en œuvre.Le FGDOS étant un système sur puce (SoC) avec plusieurs caractéristiques qui font du dosimètre un système extrêmement flexible, la caractérisation de ses différents modes de fonctionnement (actif, passif et autonome) a été effectuée. Suite à la première caractérisation, des questions se sont posées concernant les mécanismes de dégradation de la sensibilité affectant le dosimètre. Pour étudier ce phénomène, des campagnes d’irradiations ont été effectuées avec une puce d'essai incorporant seulement le circuit sensible au rayonnement du FGDOS. L'analyse des expériences a permis de comprendre les processus responsables de la dégradation de la sensibilité, en séparant la contribution du transistor de lecture de celle du condensateur à grille flottante. Les résultats de cette étude nous ont amenés à envisager de nouvelles solutions de conception et des méthodes de compensation.L’aptitude du transistor NMOS et du FGDOS à mesurer la dose ionisante dans les champs de rayonnement mixtes produits par le complexe d’accélérateurs du CERN a été vérifiée à l’aide de test radiatifs accélérés effectués dans le centre de tests en champs mixte à haute énergie du CERN (CHARM). / The Total Ionizing Dose (TID) monitoring is nowadays a crucial task for a wide range of applications running in harsh radiation environments. In view of the High-Luminosity upgrade for the Large Hadron Collider, the monitoring of radiation levels along the CERN’s accelerator complex will become even more challenging. To this extent, a more detailed knowledge of the radiation field in the accelerator tunnel and its adjacent areas becomes necessary to design installation, relocation or shielding requirements of electronics sensitive to radiation. Aiming to improve the monitoring of the TID delivered by the mixed radiation field generated within the accelerator system, investigations on new suitable dosimeters have been carried out.With this research, two devices have been studied and characterized to be employed as dosimeter and possibly to complete the use of the silicon sensor currently employed at CERN for TID monitoring, i.e. the RADiation-sensitive Field Effect Transistor (RADFET): a commercial NMOS, and an ASIC (Application-Specific Integrated Circuit) named FGDOS. The devices have been selected following two opposite approaches: on the one hand, reducing the costs would allow the density of the deployed sensors to increase. As a direct consequence, a more detailed dose map would be obtained for large distributed systems like the LHC. On the other hand, the radiation monitoring can be further improved by deploying more sensitive detectors, which would allow to measure the dose where the levels are too low for the RADFET. Moreover, sensors with higher resolution would permit the characterization of the radiation field in a shorter time, which means within a lower integrated luminosity.The first approach has been accomplished by searching for alternative solutions based on COTS (Commercial Off-The-Shelf) devices, which would significantly reduce the costs and guarantee unlimited availability on the market. For this aim, investigations on a commercial discrete NMOS transistor, which was found to be very sensitive to the radiation, has been carried out.The need for improving the resolution of TID monitoring led to investigate the FGDOS, which is an innovative silicon dosimeter with a very high sensitivity that permits to detect extremely low doses.The calibration of the NMOS and the FGDOS have been performed by exposing the dosimeters to γ-ray. Their radiation response has been characterized in terms of linearity, batch-to-batch variability, and dose rate effect. The influence of the temperature has been studied and a method to compensate the temperature effect has been developed and implemented.Being the FGDOS is a System-On-Chip with several features that make the dosimeter an extremely flexible system, the characterization of its operational modes (Active, Passive and Autonomous) have been performed. Following the first characterization, some questions arose concerning the sensitivity degradation mechanisms affecting the dosimeter. To investigate this phenomenon, radiation experiments were performed with a test chip embedding only the radiation sensitive circuit of the FGDOS. The analysis of the experiments allowed the understating of the processes responsible for the sensitivity degradation, by separating the contribution of the reading transistor and the floating gate capacitor. The results of this investigation led us to considerer new design solution and compensation methods.The suitability of the NMOS and the FGDOS for TID measurement in the mixed radiation field produced by the CERN’s accelerator complex has been verified by performing accelerated radiation tests at the Cern High energy AcceleRator Mixed field facility (CHARM). The consistency of both sensors with the RADFET measurement has been demonstrated. The high sensitivity of the FGDOS leads to a significant improvement in terms of TID measurement in mixed radiation fields with respect to the RadFET, especially for low radiation intensities.

[pt] O objetivo desta dissertação é o estudo de procedimentos para avaliação da confiabilidade metrológica do tamanho de campo irradiado (TCI) por aceleradores lineares. No contexto das recentes alterações no panorama regulamentar dos serviços de radioterapia, com a implementação da RDC número 20, em 2006, pela Agência Nacional de Vigilância Sanitária (ANVISA), foi estabelecida a compulsoriedade do uso do densitômetro óptico na verificação do TCI, como parte do controle da qualidade. Questões associadas à implementação prática dos recentes requisitos para medição do tamanho de campo irradiado e as recentes indicações do potencial uso de filmes radiocrômicos para o controle da qualidade em radioterapia motivaram a realização do presente trabalho. Foram empregados três diferentes procedimentos para avaliação do tamanho de campo irradiado por aceleradores lineares utilizados em treze serviços de radioterapia localizados no Estado do Rio de Janeiro, utilizando filmes radiocrômicos EBT QD mais, RTQA, densitômetro óptico DensiX tipo T52001 ou scanner de transmissão Microtek. Os resultados destacam a contribuição das fontes de incerteza de medição para cada procedimento realizado e indicam a necessidade de considerá-la na avaliação da conformidade utilizando o densitômetro óptico (DO). Devido às propriedades do filme radiocrômico RTQA, o mesmo não pode ser utilizado no procedimento de medição com DO. Em conclusão, o uso do procedimento de medição utilizando scanner mostrou-se mais adequado para avaliação das dimensões de campos de radiação não-homogêneos. / [en] The objective of the present work is to study different procedures for metrological evaluation of the size of the radiation field emitted by linear accelerators. In the context of the recent requirements determined by the publication of the RDC number 20, in 2006, by National Agency for Sanitary Vigilance (Anvisa), the compulsory use of the optical densitometer for the measurements of the field size during quality control tests was introduced. Practical implementation issues associated with these requirements and the recent studies indicating the potential use of radiochromic films for measurements of the field size motivated the present work. Three different procedures were employed in order to evaluate the radiation field size emitted by linear accelerators used in thirteen radiotherapy services located in Rio de Janeiro, using radiochromic films EBT QD plus and RTQA, optical densitometer DensiX type T52001 or scanner Microtek. The results indicate the contribution of the measurement uncertainty associated to each procedure performed, highlighting the importance of its consideration during tests for conformity assessment with the recently required optical densitometer. Nevertheless, the RTQA radiochromic film properties precluded its use in the procedure using optical densitometer. In conclusion, among the evaluated procedures for radiation field evaluation, the use of the scanner was the most appropriate, especially if dimensional non-homogeneities are present.

Bisphenol A (BPA) is widely used in the production of plastics, epoxy resins and polycarbonates. It is a toxic, endocrine disruptor compound. Different studies have shown the presence of BPA in several environmental systems, classifying it as a worldwide persistent pollutant which may act synergistically with other pollutants. In this context, advanced oxidation processes (AOP) have received great attention due to their ability to degrade pollutants with such characteristics, through their transformation into less hazardous compounds or even their mineralization. Although there are investigations on the use of AOPs for BPA degradation, systematic studies on the effects of process variables, coupled with the statistical interpretation of the results are virtually non-existent. Furthermore, to the best of our knowledge, a rigorous kinetic model has not yet been proposed for the degradation of this pollutant by the H2O2/UV process. The objective of this work was to evaluate BPA degradation by the H2O2/UV process, investigating the effects of the initial H2O2 concentration and the specific rate of photons emission (EP,0) by means of a Doehlert experimental design, combined with the response surface methodology. The experiments were performed in a photochemical tubular reactor equipped with a 254-nm UV lamp, for [H2O2]0 and EP,0 in the ranges 1.6-9.6 mmol L-1 and 0.87 × 1018-3.6 × 1018 photons L-1 s-1, respectively. Total BPA degradation was achieved after 60 min of irradiation in all experiments. The best conditions were [H2O2]0 = 7.6 mmol L-1 and EP,0 = 3.6 × 1018 photons L-1 s-1, for which the best performance was obtained regarding the BPA degradation rate, BPA degradation after 15 min, and the second highest TOC removal after 180 min. However, in most experiments less than 75% TOC removal was observed, with 95% mineralization obtained only for the superior [H2O2]0 and EP,0. A mathematical model was developed, considering the reactor characteristics and the radiation field, based on the line source with parallel emission (LSPP) approach, in combination with the radiative transfer equation (RTE), mass balances, and a detailed kinetic model of the H2O2/UV process. The steady-state approximation was applied for all radical species. In the estimation of unknown kinetic constants, the non-linear least squares method was employed. The model was able to satisfactorily fit experimental BPA and H2O2 concentrations as a function of time. This work shows that the H2O2/UV process is a good alternative for BPA removal from aqueous streams, with total degradation of the target compound and adequate percent mineralization under optimal operating conditions. Such conditions may serve as first guidelines for pilot-plant and industrial processes operation. In addition, simulations using the proposed kinetic model may provide useful information for the design and scale-up of pre- or post-treatment of effluents containing this pollutant. / O bisfenol A (BPA) é amplamente utilizado na fabricação de plásticos, resinas epóxi e policarbonatos. Trata-se de um composto tóxico e um desregulador endócrino. Diferentes estudos evidenciam a presença do BPA em diversos compartimentos ambientais em todo planeta, identificando-o como um poluente persistente e resistente à degradação biológica, que apresenta efeitos sinergéticos com outros poluentes. Nesse contexto, os processos oxidativos avançados (POA) têm recebido atenção devido a sua capacidade em degradar poluentes com tais características, transformando-os em compostos menos perigosos ou até mesmo mineralizando-os totalmente. Apesar de haver trabalhos na literatura acerca da utilização de POA para degradação de BPA, estudos sistemáticos dos efeitos de variáveis de processo junto com a interpretação estatística dos resultados são virtualmente inexistentes. Além disso, até onde se sabe um modelo cinético rigoroso ainda não foi proposto para a degradação desse poluente por meio do processo H2O2/UV. Este trabalho teve por objetivo avaliar a degradação do BPA pelo processo H2O2/UV, investigando os efeitos da concentração inicial de H2O2 e da taxa específica de emissão de fótons (EP,0) por meio de um projeto experimental Doehlert, combinado com a análise de superfície de resposta. Os experimentos foram realizados em um reator tubular fotoquímico equipado com uma lâmpada UV de 254 nm, para [H2O2]0 e EP,0 entre 1,6-9,6 mmol L-1 e 0,87 × 1018 - 3,6 × 1018 fótons L-1 s-1, respectivamente. Todos os experimentos sob H2O2/UV resultaram em total degradação do BPA após 60 min de irradiação. Nesse caso, as melhores condições foram [H2O2]0 = 7,6 mmol L-1 e EP,0 = 3,6 × 1018 fótons L-1 s-1, para as quais se obteve o melhor desempenho quanto à taxa de degradação de BPA e à remoção após 15 min, e a segunda maior remoção de COT após 180 min. Entretanto, na maioria dos experimentos menos de 75% de remoção de COT foram observados, com 95% de mineralização obtida apenas para os maiores [H2O2]0 e EP,0. Elaborou-se um modelo matemático que considera as características do reator utilizado e o campo de radiação, baseado no modelo de fonte linear de emissão em planos paralelos (LSPP), combinado à equação de transferência radiativa (RTE), aos balanços materiais e a um modelo cinético detalhado do processo H2O2/UV. Foi empregada a aproximação de estado estacionário para todas as espécies radicalares. Na estimativa das constantes cinéticas desconhecidas, utilizou-se o método de mínimos quadrados não linear. Esse modelo foi capaz de ajustar satisfatoriamente as concentrações experimentais de BPA e de H2O2 em função do tempo. Este trabalho mostra que o processo H2O2/UV constitui uma alternativa conveniente para a degradação de BPA em matrizes aquosas, com total degradação do composto alvo e porcentagem de mineralização adequada nas condições ótimas de operação. Tais condições podem servir como diretrizes iniciais de processamento em escalas piloto e industrial. Por sua vez, simulações empregando o modelo matemático proposto permitem gerar informações úteis para projeto e aumento de escala de processos de pré- ou pós-tratamento de efluentes contendo esse poluente.

The THick Gas Electron Multiplier (THGEM) based tissue-equivalent proportional counter (TEPC) has been proven to be useful for microdosimetry due to its flexibility in varying the gaseous sensitive volume and achieving high multiplication gain. Aiming at measuring the spatial distribution of radiation dose for mixed neutron-gamma fields, an advanced two-dimensional (2D) THGEM TEPC was designed and constructed at McMaster University which will enable us to overcome the operational limitation of the classical TEPCs, particularly for high dose rate fields. Compared to the traditional TEPCs, anode wire electrodes were replaced by THGEM layer, which not only enhances the gas multiplication gain but also offers a flexible and convenient fabrication or building 2D detectors. The 2D THGEM TEPC consists of an array of 3×3 sensitive volumes, equivalent to 9 individual TEPCs, each of which has a dimension of 5 mm diameter and length. Taking the overall cost, size and flexibility into account, to process 9 detectors signals simultaneously, a multi-input digital pulse processing system was developed by using modern microcontrollers, each of which is coupled to a 12-bit sampling ADC with a sampling rate of 42 Msps. The signal processing system was tested using a NaI(Tl) detector, which has proven that is it faster than a traditional analogue system and a commercial digital system. Using the McMaster Tandetron 7Li(p,n) accelerator neutron source, both fundamental detector performance, as well as neutron dosimetric response of the 2D THGEM TEPC, has been extensively investigated and compared to the data acquired by a spherical TEPC. It was shown that the microdosimetric response and the measured absorbed dose rate of the 2D THGEM detector developed in this study are comparable to the standard 1/2" TEPC which is commercially available. / Thesis / Doctor of Philosophy (PhD)

Eine mit Polyethylen abgeschirmte Americium-Beryllium-Quelle wurde bzgl. ihres schnellen und thermischen Neutronenfeldes sowie Photonenfeldes durch Messungen und Simulationen quantifiziert. Dafür wurden Strahlungsfeldgrößen wie spektrale Teilchenflussdichten, Teilchenflussdichten, UmgebungsÄquivalentdosisleistungen und Richtungs-Äquivalentdosisleistungen für die jeweiligen Felder in unterschiedlichen Abständen der Strahlungsquelle bestimmt. Die ermittelten Ergebnisse werden verwendet, um einen neuen Bestrahlungsstand als Referenzfeld für Neutronen und Photonen zu errichten.:Einleitung 1. Theoretische Grundlagen 1.1. Strahlungsfeldgrößen 1.1.1. Radiometrische Größen 1.1.2. Interaktionskoeffizienten 1.1.3. Dosimetrische Größen 1.1.4. Fluenz-zu-Dosis-Konversionskoeffizienten 1.2. Photonen 1.2.1. Wechselwirkung mit Materie 1.2.2. Nachweis durch Szintillationsdetektoren 1.3. Neutronen 1.3.1. Klassifizierung 1.3.2. Wechselwirkung mit Materie 1.3.3. Nachweis schneller Neutronen durch organische Szintillationsdetektoren 1.3.4. Nachweis thermischer Neutronen durch ³He-Zählrohre 1.4. Americium-Beryllium-Quellen 1.4.1. Neutronenerzeugung 1.4.2. Abschirmung 1.5. Detektoren 1.5.1. Szintillationsdetektoren 1.5.2. ³He-Zählrohre 1.6. Digitale Pulsverarbeitung 1.6.1. Pulsformdiskriminierung mit organischen Szintillationsdetektoren 1.7. Monte-Carlo-Strahlungstransportsimulationen 2. Geräte und Materialien 3. Methoden 3.1. Quantifizierung des schnellen Neutronenfeldes 3.1.1. PFD-unterstützte Flugzeitmethode 3.1.2. Einfache Entfaltungstechnik 3.2. Quantifizierung des thermischen Neutronenfeldes 3.3. Quantifizierung des Photonenfeldes 4. Messungen 4.1. Messung 1 4.2. Messung 2 4.3. Messung 3 4.4. Messung 4 4.5. Messung 5 4.6. Messung 6 4.7. Messung 7 4.8. Messung 8 4.9. Messung 9 4.10. Messung 10 5. Simulationen mit FLUKA 5.1. Nachmodellierung der Versuchsaufbauten 5.2. Nachbildung der Strahlungsfelder 5.2.1. Bestimmung der Korrekturfaktoren 5.3. Simulierte Größen 6. Ergebnisse 6.1. Quantifizierung des schnellen Neutronenfeldes 6.1.1. Strahlungsfeldgrößen mittels des Stilbendetektors 6.1.2. Strahlungsfeldgrößen mittels der Plausibilitätsmessungen 6.1.3. Strahlungsfeldgrößen mittels der FLUKA-Simulationen 6.2. Quantifizierung des thermischen Neutronenfeldes 6.2.1. Strahlungsfeldgrößen mittels des ³He-Zählrohrs 6.2.2. Strahlungsfeldgrößen mittels der FLUKA-Simulationen 6.3. Quantifizierung des Photonenfeldes 6.3.1. Strahlungsfeldgrößen mittels des CeBr₃-Detektors 6.3.2. Strahlungsfeldgrößen mittels der Plausibilitätsmessungen 6.3.3. Strahlungsfeldgrößen mittels der FLUKA-Simulationen 7. Diskussion 7.1. Quantifizierung des schnellen Neutronenfeldes 7.1.1. Spektrale Teilchenflussdichten 7.1.2. Umgebungs-Äquivalentdosisleistungen 7.2. Quantifizierung des thermischen Neutronenfeldes 7.2.1. Teilchenflussdichten 7.3. Quantifizierung des Photonenfeldes 7.3.1. Teilchenflussdichten der Photonen mit den Energien 511 keV, 2,2 MeV und 4,4 MeV 7.3.2. Umgebungs-Äquivalentdosisleistungen 7.3.3. Richtungs-Äquivalentdosisleistungen 8. Zusammenfassung A. Bestimmte Strahlungsfeldgrößen A.1. Schnelles Neutronenfeld A.1.1. Spektrale Teilchenflussdichten A.1.2. Umgebungs-Äquivalentdosisleistungen A.2. Thermisches Neutronenfeld A.2.1. Teilchenflussdichten A.3. Photonenfeld A.3.1. Teilchenflussdichten der Photonen mit den Energien 511 keV, 2,2 MeV und 4,4 MeV A.3.2. Umgebungs-Äquivalentdosisleistungen A.3.3. Richtungs-Äquivalentdosisleistungen B. Zwischenergebnisse B.1. Quantifizierung des schnellen Neutronenfeldes B.1.1. Pulsladungshistogramme des Stilbendetektors für n₁-Neutronen B.1.2. Anzahlen der Rückstoßprotonen B.2. Quantifizierung des Photonenfeldes B.2.1. Simulierte und gemessene Größen zur Bestimmung der Teilchenflussdichten der Photonen mit den Energien 511 keV, 2,2 MeV und 4,4 MeV / An americium-beryllium source shielded with polyethylene was quantified in regards to its fast and thermal neutron field, as well as its photon field via measurements and simulations. Therefore, radiation field quantities like spectral fluence rates, fluence rates, ambient dose rate equivalents and directional dose rate equivalents of the respective fields were determined in different distances from the radiation source. The produced results will be used for establishing a new irradiation workbench as reference field for neutrons and photons.:Einleitung 1. Theoretische Grundlagen 1.1. Strahlungsfeldgrößen 1.1.1. Radiometrische Größen 1.1.2. Interaktionskoeffizienten 1.1.3. Dosimetrische Größen 1.1.4. Fluenz-zu-Dosis-Konversionskoeffizienten 1.2. Photonen 1.2.1. Wechselwirkung mit Materie 1.2.2. Nachweis durch Szintillationsdetektoren 1.3. Neutronen 1.3.1. Klassifizierung 1.3.2. Wechselwirkung mit Materie 1.3.3. Nachweis schneller Neutronen durch organische Szintillationsdetektoren 1.3.4. Nachweis thermischer Neutronen durch ³He-Zählrohre 1.4. Americium-Beryllium-Quellen 1.4.1. Neutronenerzeugung 1.4.2. Abschirmung 1.5. Detektoren 1.5.1. Szintillationsdetektoren 1.5.2. ³He-Zählrohre 1.6. Digitale Pulsverarbeitung 1.6.1. Pulsformdiskriminierung mit organischen Szintillationsdetektoren 1.7. Monte-Carlo-Strahlungstransportsimulationen 2. Geräte und Materialien 3. Methoden 3.1. Quantifizierung des schnellen Neutronenfeldes 3.1.1. PFD-unterstützte Flugzeitmethode 3.1.2. Einfache Entfaltungstechnik 3.2. Quantifizierung des thermischen Neutronenfeldes 3.3. Quantifizierung des Photonenfeldes 4. Messungen 4.1. Messung 1 4.2. Messung 2 4.3. Messung 3 4.4. Messung 4 4.5. Messung 5 4.6. Messung 6 4.7. Messung 7 4.8. Messung 8 4.9. Messung 9 4.10. Messung 10 5. Simulationen mit FLUKA 5.1. Nachmodellierung der Versuchsaufbauten 5.2. Nachbildung der Strahlungsfelder 5.2.1. Bestimmung der Korrekturfaktoren 5.3. Simulierte Größen 6. Ergebnisse 6.1. Quantifizierung des schnellen Neutronenfeldes 6.1.1. Strahlungsfeldgrößen mittels des Stilbendetektors 6.1.2. Strahlungsfeldgrößen mittels der Plausibilitätsmessungen 6.1.3. Strahlungsfeldgrößen mittels der FLUKA-Simulationen 6.2. Quantifizierung des thermischen Neutronenfeldes 6.2.1. Strahlungsfeldgrößen mittels des ³He-Zählrohrs 6.2.2. Strahlungsfeldgrößen mittels der FLUKA-Simulationen 6.3. Quantifizierung des Photonenfeldes 6.3.1. Strahlungsfeldgrößen mittels des CeBr₃-Detektors 6.3.2. Strahlungsfeldgrößen mittels der Plausibilitätsmessungen 6.3.3. Strahlungsfeldgrößen mittels der FLUKA-Simulationen 7. Diskussion 7.1. Quantifizierung des schnellen Neutronenfeldes 7.1.1. Spektrale Teilchenflussdichten 7.1.2. Umgebungs-Äquivalentdosisleistungen 7.2. Quantifizierung des thermischen Neutronenfeldes 7.2.1. Teilchenflussdichten 7.3. Quantifizierung des Photonenfeldes 7.3.1. Teilchenflussdichten der Photonen mit den Energien 511 keV, 2,2 MeV und 4,4 MeV 7.3.2. Umgebungs-Äquivalentdosisleistungen 7.3.3. Richtungs-Äquivalentdosisleistungen 8. Zusammenfassung A. Bestimmte Strahlungsfeldgrößen A.1. Schnelles Neutronenfeld A.1.1. Spektrale Teilchenflussdichten A.1.2. Umgebungs-Äquivalentdosisleistungen A.2. Thermisches Neutronenfeld A.2.1. Teilchenflussdichten A.3. Photonenfeld A.3.1. Teilchenflussdichten der Photonen mit den Energien 511 keV, 2,2 MeV und 4,4 MeV A.3.2. Umgebungs-Äquivalentdosisleistungen A.3.3. Richtungs-Äquivalentdosisleistungen B. Zwischenergebnisse B.1. Quantifizierung des schnellen Neutronenfeldes B.1.1. Pulsladungshistogramme des Stilbendetektors für n₁-Neutronen B.1.2. Anzahlen der Rückstoßprotonen B.2. Quantifizierung des Photonenfeldes B.2.1. Simulierte und gemessene Größen zur Bestimmung der Teilchenflussdichten der Photonen mit den Energien 511 keV, 2,2 MeV und 4,4 MeV

Les seize détecteurs MPX constituant le réseau ATLAS-MPX ont été placés à différentes positions dans le détecteur ATLAS et sa averne au CERN dans le but de mesurer en emps réel les champs de radiation produits ar des particules primaires (protons des faisceaux) et des particules secondaires (kaons, pions, g, protons) issues des collisions proton-proton. Des films de polyéthylène (PE) et de fluorure de lithium (6LiF) recouvrent les détecteurs afin d’augmenter leur sensibilité aux neutrons produits par les particules primaires et secondaires interagissant avec les matériaux présents dans l’environnement d’ATLAS. La reconnaissance des traces laissées par les particules dans un détecteur ATLAS-MPX se fait à partir des algorithmes du logiciel MAFalda (“Medipix Analysis Framework”) basé sur les librairies et le logiciel d’analyse de données ROOT. Une étude sur le taux d’identifications erronées et le chevauchement d’amas a été faite en reconstruisant les activités des sources 106Ru et 137Cs. L’efficacité de détection des neutrons rapides a été mesurée à l’aide des sources 252Cf et 241AmBe (neutrons d’énergie moyenne de 2.13 et 4.08 MeV respectivement). La moyenne des efficacités de détection mesurées pour les neutrons produits par les sources 252C f et 241AmBe a été calculée pour les convertisseurs 6LiF et PE et donnent (0.8580 ± 0.1490)% et (0.0254 ± 0.0031)% pour LiF et (0.0510 ± 0.0061)% et (0.0591 ± 0.0063)% pour PE à bas et à haut seuil d’énergie respectivement. Une simulation du calcul de l’efficacité de détection des neutrons dans le détecteur MPX a été réalisée avec le logiciel GEANT4. Des données MPX correspondant aux collisions proton-proton à 2.4 TeV et à 7 TeV dans le centre de masse ont été analysées. Les flux détectés d’électrons et de photons sont particulièrement élevés dans les détecteurs MPX01 et MPX14 car ils sont plus près du point de collision. Des flux de neutrons ont été estimés en utilisant les efficacités de détection mesurées. Une corrélation avec la luminosité du LHC a été établie et on prédit que pour les collisions à 14 TeV dans le centre de masse et avec une luminosité de 10^34 cm-1*s-1 il y aura environ 5.1x10^8 ± 1.5x10^7 et 1.6x10^9 ± 6.3x10^7 particules détectées par les détecteurs MPX01 et MPX14 respectivement. / The sixteen detectors forming the ATLAS-MPX network have been placed in different positions inside the ATLAS detector and its cavern at CERN in order to measure, in real time, the radiation fields produced by primary particles (beam protons) and secondary particles (kaons, pions, photons, protons) resulting from the proton-proton collisions. Films of polyethylene (PE) and lithium fluoride (6LiF) cover the detectors so as to increase their sensitivity to neutrons produced by the primary and secondary particles interacting with the materials present in the ATLAS environment. The tracks identification in an ATLAS-MPX detector is obtained with the algorithms of the MAFalda software (Medipix Analysis Framework) based on the libraries and data-analysis software ROOT. A study on the mistag rate and blob overlap was made by reconstructing the activities of 106Ru and 137Cs sources. The fast neutron detection efficiency was measured with the help of 252C f and 241AmBe sources (neutrons with an average energy of 2.13 and 4.08 MeV, respectively). The detection efficiency measured for neutrons produced by 252Cf et 241AmBe sources was calculated for the 6LiF and PE converters. It averaged at low and high energy respectively (0.8580 ± 0.1490)% and (0.0254 ± 0.0031)% for LiF and (0.0510 ± 0.0061)% and (0.0591 ± 0.0063)% for PE. A simulation of the neutron detection efficiency calculation in the MPX detector was carried out with the GEANT4 software. MPX data corresponding to the proton-proton collisions at 2.4 TeV and 7 TeV at the center of mass were analyzed. The detected flux of electrons and photons are particularly high in the MPX01 and MPX14 detectors because they are closer to the point of collision. Fluxes of neutrons were estimated using the measured detection efficiencies. A correlation with the luminosity of the LHC was established. We predict that for 14 TeV collisions at the center of mass, with a luminosity of 1034 cm^2*s^1, the number of particle detected by MPX01 and MPX14 respectively will be about 5.1x10^8 ± 1.5x10^7 and 1.6x10^9 ± 6.3x10^7.

Bei der theoretischen Beschreibung von spektroskopischen Experimenten wird in der Regel das Materiesystem quantenmechanisch beschrieben, während das Strahlungsfeld klassisch behandelt wird. Diese semiklassische Näherung ist zur Beschreibung von Experimenten, bei denen eine starke Kopplung zwischen dem Matriesystem und einzelnen Photonen besteht, nicht mehr gültig. Dies kann beispielsweise innerhalb eines optischen Resonators der Fall sein. In dieser Arbeit wird am Beispiel eines Pump-Test- Experiments zum Nachweis des optischen Stark-Effekts untersucht, welche zusätzlichen Effekte sich bei einer quantisierten Beschreibung des Strahlungsfeldes ergeben. Ein signifikanter Effekt ist, dass die Photonenstatistik des Pumpfeldes sich in der Linienform der verschobenen Resonanzlinie widerspiegelt. Weiter wurde in dieser Arbeit bei kleiner Pumpverstimmung ein Verstärkungseffekt gefunden, der ebenfalls auf der quantisierten Behandlung des Strahlungsfeldes beruht (nichtklassische Verstärkung). Es treten ferner bei grosseren Ensemblen von Zwei-Niveau -Systemen zusätzliche Unterstrukturen und Resonanzen auf. Auch kann der Nachweis des optischen Stark-Effekts Aufschluss über die Nichtdiagonalelemente bezüglich der Photonenzahl des quantisierten Pumpfeldes geben.Im Hinblick auf die Beschreibung komplexer Materiesystemen wurde in dieser Arbeit auch eine näherungsweise Berechnung der Testabsorption mit quantisiertem Strahlungsfeld im Rahmen einer Dichtematrixtheorie untersucht. Insbesondere war hier für die quantitative Beschreibung der nichtklassischen Verstärkung eine Berücksichtigung hoherer Korrelationen zwingend erforderlich. Auch wurden näherungsweise Entkopp- lungen unter Berücksichtigung der Erhaltungsgrossen durch- geführt. Die Dichtematrixtheorie wurde auf die Untersuchung des optischen Stark-Effektes an storstellengebundenen Exzitonen in Halbleitern angewandt. Da diese Resonanzen vergleichsweise kleine homogene und inhomogene Linienbreiten aufweisen,ist hier experimentell zu erwarten, dass sich feine Effekte des quantisierten Pumpfeldes bemerkbar machen konnen. / The theoretical description of spectroscopic experiments usu ally relies on a semiclassical approach where the matter system is described in terms of quantum mechanics while the radiation field is treated classically. This approach does n ot work well for systems with a strong coupling between the matter system and photons of the radiation field. The latter can be the case within an optical resonator.In this thesis, additional effects of a quantized radiation field are inves tigated on a pump-probe experiment for detecting the optical Stark effect. One significant effect is that the lineshape of the shifted resonance displays the photon statistics of the pump field. For small pump detuning probe gain results in a frequency regime where the semiclassical treatment predicts absorption. This effect is refered to nonclassical gain. For larger ensembles of two-level systems, additional substructures and resonances appear within the probe absorption spectrum. Also non- diagonal elements of the field density matrix can be detected in such an experiment. In order to describe a more complex matter systems, the optical Stark effect has been treated in terms of a density matrix approach with quantized radiation fields. For a quantitative description of nonclassical gain, higher correlation terms had to be treated properly. Moreover, conserved quantities were taken into account in approximate decouplings. The density matrix approach was applied to the description of the optical Stark effect on impurity-bound excitons in semiconductors. These systems are of high interest as their narrow resonances might allow the demonstration of fine effects of the quantized radiation field.

Les seize détecteurs MPX constituant le réseau ATLAS-MPX ont été placés à différentes positions dans le détecteur ATLAS et sa averne au CERN dans le but de mesurer en emps réel les champs de radiation produits ar des particules primaires (protons des faisceaux) et des particules secondaires (kaons, pions, g, protons) issues des collisions proton-proton. Des films de polyéthylène (PE) et de fluorure de lithium (6LiF) recouvrent les détecteurs afin d’augmenter leur sensibilité aux neutrons produits par les particules primaires et secondaires interagissant avec les matériaux présents dans l’environnement d’ATLAS. La reconnaissance des traces laissées par les particules dans un détecteur ATLAS-MPX se fait à partir des algorithmes du logiciel MAFalda (“Medipix Analysis Framework”) basé sur les librairies et le logiciel d’analyse de données ROOT. Une étude sur le taux d’identifications erronées et le chevauchement d’amas a été faite en reconstruisant les activités des sources 106Ru et 137Cs. L’efficacité de détection des neutrons rapides a été mesurée à l’aide des sources 252Cf et 241AmBe (neutrons d’énergie moyenne de 2.13 et 4.08 MeV respectivement). La moyenne des efficacités de détection mesurées pour les neutrons produits par les sources 252C f et 241AmBe a été calculée pour les convertisseurs 6LiF et PE et donnent (0.8580 ± 0.1490)% et (0.0254 ± 0.0031)% pour LiF et (0.0510 ± 0.0061)% et (0.0591 ± 0.0063)% pour PE à bas et à haut seuil d’énergie respectivement. Une simulation du calcul de l’efficacité de détection des neutrons dans le détecteur MPX a été réalisée avec le logiciel GEANT4. Des données MPX correspondant aux collisions proton-proton à 2.4 TeV et à 7 TeV dans le centre de masse ont été analysées. Les flux détectés d’électrons et de photons sont particulièrement élevés dans les détecteurs MPX01 et MPX14 car ils sont plus près du point de collision. Des flux de neutrons ont été estimés en utilisant les efficacités de détection mesurées. Une corrélation avec la luminosité du LHC a été établie et on prédit que pour les collisions à 14 TeV dans le centre de masse et avec une luminosité de 10^34 cm-1*s-1 il y aura environ 5.1x10^8 ± 1.5x10^7 et 1.6x10^9 ± 6.3x10^7 particules détectées par les détecteurs MPX01 et MPX14 respectivement. / The sixteen detectors forming the ATLAS-MPX network have been placed in different positions inside the ATLAS detector and its cavern at CERN in order to measure, in real time, the radiation fields produced by primary particles (beam protons) and secondary particles (kaons, pions, photons, protons) resulting from the proton-proton collisions. Films of polyethylene (PE) and lithium fluoride (6LiF) cover the detectors so as to increase their sensitivity to neutrons produced by the primary and secondary particles interacting with the materials present in the ATLAS environment. The tracks identification in an ATLAS-MPX detector is obtained with the algorithms of the MAFalda software (Medipix Analysis Framework) based on the libraries and data-analysis software ROOT. A study on the mistag rate and blob overlap was made by reconstructing the activities of 106Ru and 137Cs sources. The fast neutron detection efficiency was measured with the help of 252C f and 241AmBe sources (neutrons with an average energy of 2.13 and 4.08 MeV, respectively). The detection efficiency measured for neutrons produced by 252Cf et 241AmBe sources was calculated for the 6LiF and PE converters. It averaged at low and high energy respectively (0.8580 ± 0.1490)% and (0.0254 ± 0.0031)% for LiF and (0.0510 ± 0.0061)% and (0.0591 ± 0.0063)% for PE. A simulation of the neutron detection efficiency calculation in the MPX detector was carried out with the GEANT4 software. MPX data corresponding to the proton-proton collisions at 2.4 TeV and 7 TeV at the center of mass were analyzed. The detected flux of electrons and photons are particularly high in the MPX01 and MPX14 detectors because they are closer to the point of collision. Fluxes of neutrons were estimated using the measured detection efficiencies. A correlation with the luminosity of the LHC was established. We predict that for 14 TeV collisions at the center of mass, with a luminosity of 1034 cm^2*s^1, the number of particle detected by MPX01 and MPX14 respectively will be about 5.1x10^8 ± 1.5x10^7 and 1.6x10^9 ± 6.3x10^7.