Doctor of Philosophy / Department of Mechanical and Nuclear Engineering / Douglas S. McGregor / Advancements in nuclear reactor core modeling and computational capability have encouraged further development of in-core neutron sensors. Measurement of the neutron-flux distribution within the reactor core provides a more complete understanding of the operating conditions in the reactor than typical ex-core sensors. Micro-Pocket Fission Detectors (MPFDs) have been developed and tested previously but have been limited to single-node operation and have utilized highly specialized designs. The development of a widely deployable, multi-node MPFD assembly will enhance nuclear research capabilities. In-core neutron flux measurements include many challenges because of the harsh environment within the reactor core. Common methods of in-core neutron measurement are also limited by geometry and other physical constraints. MPFDs are designed to be small and robust while offering a real-time, spatial measurement of neutron flux. Improvements to the MPFD design were developed based on shortcomings of prior research in which many of the theoretical considerations for MPFDs were examined. Fabrication techniques were developed for the preparation of MPFD components and electrodeposition of fissile material. Numerous arrays of MPFDs were constructed for test deployments at the Kansas State University TRIGA Mk. II research nuclear reactor, University of Wisconsin Nuclear Reactor, Transient REActor Test facility at the Idaho National Laboratory (INL), and Advanced Test Reactor at INL. Preliminary testing of a single MPFD sensor at KSU yielded a linear response to reactor power between 10 kWth and 750 kWth and followed both positive and negative reactivity insertions in real-time. A $1.50 reactor pulse was monitored from the Intra-Reflector Irradiation System, located in reflector region of the KSU TRIGA Mk. II core with 1-ms time resolution. Improved multi-node MPFD arrays were then designed, fabricated, and deployed in flux ports between fuel rods and within an iron-wire flux port which was inserted into the central thimble of the KSU TRIGA Mk. II research nuclear reactor. Work continues to develop MPFDs for deployment at research reactors at INL and elsewhere. Results from the MPFD measurements will be useful for future validation of computational modeling and as part of advanced nuclear fuel development efforts.

No description available.

Aujourd’hui les réacteurs d’irradiations technologiques (MTR) ont un rôle de premier plan pour l’industrie du nucléaire. Dans les réacteurs d’irradiation les niveaux de flux neutroniques et photoniques sont très importants. Un des besoins cruciaux des mesures en MTR est la mise en œuvre d’un dispositif de détection de rayonnement, précis, sélectif, fiable et robuste dans les conditions extrêmes de flux neutroniques et photoniques, et de températures élevées. Les semi-conducteurs à grande bande d’énergie interdite tels que le carbure de silicium (SiC) le diamant et le nitrure de gallium (GaN) possèdent des propriétés remarquables en termes de tenue en température et de résistance aux radiations. Cette thèse a pour principal objectif la comparaison des performances des détecteurs de neutrons dont les parties sensibles sont faites de carbure de silicium (SiC) avec celles des détecteurs basés sur le diamant pour la mesure de neutrons en conditions d’irradiation identiques. Pour cela nous avons réalisé les essais d’irradiation dans le réacteur de recherche de type maquette critique MINERVE au CEA Cadarache. Nous avons également testé les capteurs pour la détection des neutrons rapides de 14 MeV afin d’investiguer la future possibilité de mesurer en ligne des flux de neutrons rapides notamment pour les besoins de la fusion nucléaire (projet ITER). L’ensemble de ces travaux contribue à l’amélioration de la fonctionnalité du détecteur de neutrons en SiC, qui peut être augmentée en intégrant le détecteur à une électronique adaptée et aux outils spécifiques pour l’analyse du signal développés dans le cadre de cette thèse. / Nowadays, the material testing reactors (MTR) are playing a crucial role for nuclear industry. The research reactors allow carrying out the research on material damage and nuclear fuel advanced studies. Harsh radiation environment near the nuclear reactor core requires the radiation detectors to be resistant to high radiation level and high temperature. Neutron radiation detector for nuclear reactor applications plays an important role in getting information about the actual neutron flux. Most suitable semiconductors for harsh environment applications are SiC and diamond thanks to their outstanding properties. The aim of this thesis is to compare the ability of these two semi-conductors to detect neutrons. For this purpose, the neutron irradiation tests of detectors were implemented at MINERVE nuclear research reactor at CEA Cadarache. In this work we also studied the response of both materials to 14 MeV neutron beam with the prospect for future applications for fusion facilities. This work helps to improve the SiC-based detector characterization. The functionality of this detector could be enhanced by integrating it with appropriate radiation resistant electronics and tools for the signal analysis which was developed in the frame of this thesis

O estudo do efeito da colimação nos detectores de radiação sobre a qualidade de imagem do tomógrafo industrial de terceira geração desenvolvido no IPEN/CNEN-SP é descrito neste trabalho. Três conjuntos de colimadores de chumbo foram projetados e confeccionados, sendo um com janelas retangulares de 2 x 5 x 50 mm e outro com 4 x 10 x 50 mm (largura x comprimento x profundidade) e um terceiro com orifício circular de 5 mm de diâmetro x 40 mm de profundidade. Os colimadores foram projetados para poderem ser facilmente substituídos entre si nos detectores de radiação. Paralelamente, foram confeccionados e utilizadas a eletrônica associada, constituída de analisadores de sinais tipo multicanal de 8 bits contendo a unidade de alta tensão e o amplificador. Dentre as vantagens deste sistema destaca-se a sua capacidade de análise multicanal rápida e possuir uma eletrônica mais simples. Valores de resolução energética comparável com a da literatura foram encontrados utilizando a eletrônica desenvolvida acoplada ao detector de radiação de NaI(Tl). Os efeitos dos colimadores foram avaliados pelas medidas tomográficas em um fantom de polimetilmetacrilato contendo componentes multifásicos estáticos (ferro, alumínio e ar). Fontes de radiação com energias de das fontes de 75Se (97 keV, 121 keV, 136 keV, 265 keV, 279 keV e 400 keV), de 137Cs (662 keV) e de 192Ir (317 keV, 468 keV e 602 keV) observou-se que a melhor imagem do fantom foi obtida com os colimadores de janelas retangulares (fendas) de 2 x 5 x 50 mm. Na avaliação dinâmica da formação de bolhas em coluna simuladora de processos industriais, a melhor imagem foi obtida com a fonte de 192Ir. / The study of the effect of collimation in radiation detectors on the image quality of the third-generation industrial CT scanner developed at IPEN / CNEN-SP is described in this work. Three sets of lead collimators were designed and manufactured, one with rectangular windows of 2 x 5 x 50 mm and the other with 4 x 10 x 50 mm (width x length x deep) and a third circular hole of 5 mm diameter x 40 mm deep. The collimators were designed to be easily interchanged in radiation detectors. In parallel, were prepared and used the associated electronics, consisting of multi-channel signal analyzers type of 8 bits containing the high voltage unit and the amplifier. Among the advantages of this system stands out for its ability to fast multichannel analysis and possess a simpler electronics. Values in energy resolution comparable with the literature were found using the developed electronics coupled to the radiation detector of NaI (Tl). The effects of collimators were evaluated by tomographic measurements in a multiphase fantom polymethyl methacrylate containing static components (iron, aluminum and air). Radiation sources with energies of the sources of 75Se (97 keV, 121 keV, 136 keV, 265 keV, 279 keV and 400 keV), 137Cs (662 keV) and 192Ir (317 keV, 468 keV and 602 keV) observed that the best image was obtained fantom collimators with rectangular windows (slits) 2 x 5 x 50 mm. In the dynamic evaluation of formation of bubbles column in a simulated industrial processes the best image at was obtained with the 192Ir source.

O estudo do efeito da colimação nos detectores de radiação sobre a qualidade de imagem do tomógrafo industrial de terceira geração desenvolvido no IPEN/CNEN-SP é descrito neste trabalho. Três conjuntos de colimadores de chumbo foram projetados e confeccionados, sendo um com janelas retangulares de 2 x 5 x 50 mm e outro com 4 x 10 x 50 mm (largura x comprimento x profundidade) e um terceiro com orifício circular de 5 mm de diâmetro x 40 mm de profundidade. Os colimadores foram projetados para poderem ser facilmente substituídos entre si nos detectores de radiação. Paralelamente, foram confeccionados e utilizadas a eletrônica associada, constituída de analisadores de sinais tipo multicanal de 8 bits contendo a unidade de alta tensão e o amplificador. Dentre as vantagens deste sistema destaca-se a sua capacidade de análise multicanal rápida e possuir uma eletrônica mais simples. Valores de resolução energética comparável com a da literatura foram encontrados utilizando a eletrônica desenvolvida acoplada ao detector de radiação de NaI(Tl). Os efeitos dos colimadores foram avaliados pelas medidas tomográficas em um fantom de polimetilmetacrilato contendo componentes multifásicos estáticos (ferro, alumínio e ar). Fontes de radiação com energias de das fontes de 75Se (97 keV, 121 keV, 136 keV, 265 keV, 279 keV e 400 keV), de 137Cs (662 keV) e de 192Ir (317 keV, 468 keV e 602 keV) observou-se que a melhor imagem do fantom foi obtida com os colimadores de janelas retangulares (fendas) de 2 x 5 x 50 mm. Na avaliação dinâmica da formação de bolhas em coluna simuladora de processos industriais, a melhor imagem foi obtida com a fonte de 192Ir. / The study of the effect of collimation in radiation detectors on the image quality of the third-generation industrial CT scanner developed at IPEN / CNEN-SP is described in this work. Three sets of lead collimators were designed and manufactured, one with rectangular windows of 2 x 5 x 50 mm and the other with 4 x 10 x 50 mm (width x length x deep) and a third circular hole of 5 mm diameter x 40 mm deep. The collimators were designed to be easily interchanged in radiation detectors. In parallel, were prepared and used the associated electronics, consisting of multi-channel signal analyzers type of 8 bits containing the high voltage unit and the amplifier. Among the advantages of this system stands out for its ability to fast multichannel analysis and possess a simpler electronics. Values in energy resolution comparable with the literature were found using the developed electronics coupled to the radiation detector of NaI (Tl). The effects of collimators were evaluated by tomographic measurements in a multiphase fantom polymethyl methacrylate containing static components (iron, aluminum and air). Radiation sources with energies of the sources of 75Se (97 keV, 121 keV, 136 keV, 265 keV, 279 keV and 400 keV), 137Cs (662 keV) and 192Ir (317 keV, 468 keV and 602 keV) observed that the best image was obtained fantom collimators with rectangular windows (slits) 2 x 5 x 50 mm. In the dynamic evaluation of formation of bubbles column in a simulated industrial processes the best image at was obtained with the 192Ir source.

Foi projetado e construído um espectrômetro Mini-Orange (MO) para eléctrons, utilizando imãs planos permanentes e um detector de barreira de superfície. Foram determinadas as funções de transmissão de diferentes configurações do sistema, para energias entre 200-1100 keV. Foi desenvolvido um modelo matemático do sistema, a partir de solução analítica para o campo de um imã plano e da integração numérica da equação de movimento dos eléctrons no campo de MO. As funções de transmissão assim obtidas foram comparadas aos resultados experimentais e mostraram um bom acordo para energias baixas e intermediárias. / A Mini-Orange spectrometer for electrons was designed and built, using plane permanent magnets and a surface barrier detector. Transmission functions were obtained for various system configurations and for energies between 200-1100 keV. A mathematical model of the system was developed, using the analytical solution for the field of a plane magnet and the numerical integration of the equation of motion of the electrons in the MO magnetic field. The calculated transmission functions were compared to the experimental data, showing a good agreement for low and intermediate energies.

A reação 18O+110Pd foi estudada utilizando o espectrômetro Y Saci-Perere do laboratório do acelerador Pelletron (LAFN-IFUSP-DFN) numa faixa de energia de 2; 5 a 3; 3 MeV por núcleon. O objetivo foi o estudo do mecanismo de reações nucleares por meio de coincidências Y-partícula, implantando essa técnica e vericando como os efeitos de integração da energia perdida no alvo, integração no ângulo sólido do detector de partículas, tamanho finito do detector HPGe e o efeito de decaimento em vácuo afetavam as medidas. Observa-se que as correções dos dados devidas a esses efeitos são pequenas e bem controladas, com exceção do efeito de decaimento em vácuo que necessita de um estudo mais aprofundado. Concluiu-se que a distribuiçao angular do espalhamento elástico para o primeiro estado excitado do 110Pd pode ser razoavelmente bem representada utilizando-se o Potencial de São Paulo (PSP) na forma U(R) = (0; 6 + 0; 6i)V SP EL (R).No entanto a descrição da transferência para o primeiro estado excitado do 112Pd não foi tão bem sucedida. / The 18O+110Pd reaction has been studied in the range from 2; 5 to 3; 3 MeV per nucleon using the Saci-Perere y-ray spectrometer at the Pelletron accelerator Laboratory (LAFN-IFUSP-DFN). The objective was the study of nuclear reaction mechanisms by the use of y-particle coincidence, establishing this technique, and verifying how the eects of energy loss in the target, the nite solid angle of the particle detector, the nite size of HPGe detector, and the vacuum de-alignment aect the measurements. It was observed that the corrections to the data due to these eects are small and well controlled, with exception of the vacuum de-alignment, which has to be studied more deeply. It was concluded that the inelastic scattering to the rst excited state of 110Pd can be reasonably well described using the São Paulo Potencial (PSP) in the form U(R) = (0; 6 + 0; 6i)V SP LE . However the description of the transfer to the rst excited state of 112Pd was not so well succeeded.

A reação 18O+110Pd foi estudada utilizando o espectrômetro Y Saci-Perere do laboratório do acelerador Pelletron (LAFN-IFUSP-DFN) numa faixa de energia de 2; 5 a 3; 3 MeV por núcleon. O objetivo foi o estudo do mecanismo de reações nucleares por meio de coincidências Y-partícula, implantando essa técnica e vericando como os efeitos de integração da energia perdida no alvo, integração no ângulo sólido do detector de partículas, tamanho finito do detector HPGe e o efeito de decaimento em vácuo afetavam as medidas. Observa-se que as correções dos dados devidas a esses efeitos são pequenas e bem controladas, com exceção do efeito de decaimento em vácuo que necessita de um estudo mais aprofundado. Concluiu-se que a distribuiçao angular do espalhamento elástico para o primeiro estado excitado do 110Pd pode ser razoavelmente bem representada utilizando-se o Potencial de São Paulo (PSP) na forma U(R) = (0; 6 + 0; 6i)V SP EL (R).No entanto a descrição da transferência para o primeiro estado excitado do 112Pd não foi tão bem sucedida. / The 18O+110Pd reaction has been studied in the range from 2; 5 to 3; 3 MeV per nucleon using the Saci-Perere y-ray spectrometer at the Pelletron accelerator Laboratory (LAFN-IFUSP-DFN). The objective was the study of nuclear reaction mechanisms by the use of y-particle coincidence, establishing this technique, and verifying how the eects of energy loss in the target, the nite solid angle of the particle detector, the nite size of HPGe detector, and the vacuum de-alignment aect the measurements. It was observed that the corrections to the data due to these eects are small and well controlled, with exception of the vacuum de-alignment, which has to be studied more deeply. It was concluded that the inelastic scattering to the rst excited state of 110Pd can be reasonably well described using the São Paulo Potencial (PSP) in the form U(R) = (0; 6 + 0; 6i)V SP LE . However the description of the transfer to the rst excited state of 112Pd was not so well succeeded.

Foi projetado e construído um espectrômetro Mini-Orange (MO) para eléctrons, utilizando imãs planos permanentes e um detector de barreira de superfície. Foram determinadas as funções de transmissão de diferentes configurações do sistema, para energias entre 200-1100 keV. Foi desenvolvido um modelo matemático do sistema, a partir de solução analítica para o campo de um imã plano e da integração numérica da equação de movimento dos eléctrons no campo de MO. As funções de transmissão assim obtidas foram comparadas aos resultados experimentais e mostraram um bom acordo para energias baixas e intermediárias. / A Mini-Orange spectrometer for electrons was designed and built, using plane permanent magnets and a surface barrier detector. Transmission functions were obtained for various system configurations and for energies between 200-1100 keV. A mathematical model of the system was developed, using the analytical solution for the field of a plane magnet and the numerical integration of the equation of motion of the electrons in the MO magnetic field. The calculated transmission functions were compared to the experimental data, showing a good agreement for low and intermediate energies.

Pour augmenter les performances des barres de combustible nucléaire, les mécanismes de relâchement des produits de fission (H2, He, Kr, Xe) doivent être étudiés. Ainsi, le département d’étude du combustible du CEA Cadarache a décidé d’améliorer son dispositif expérimental consacré au recuit thermique des combustibles irradiés (MERARG II). La première partie de ce mémoire s'adresse à la mesure du relâchement de gaz de fission de combustibles irradiés et soumis à des transitoire thermiques. Le choix de l'appareil s'est porté sur un analyseur de type filtre quadripolaire du fait des performances requises par le cahier des charges, une identification isotopique du Kr et Xe et des masses 4 et 2 u à la ppm. C'est un spectromètre commercial de type Residual Gaz Analyser, monté dans une enceinte à vide de très faible volume qui a nécessité des adaptations à la ligne de l'expérience MERARG II. Les performances (résolution, sensibilité, vitesse de balayage) du spectromètre ont été évaluées. Le spectromètre calibré est en cours d’installation sur une réplique en zone « froide » de MERARG II.La seconde partie de la thèse concerne des travaux de recherche sur l’adaptation à l’analyse des faibles masses d’un mode opératoire appliqué à un piège à ions RF 3D utilisant un mode par Transformé de Fourier. Nous étudions plus précisément un dispositif d’injection des ions et son mode opératoire afin d’obtenir les distributions en positions et vitesses des ions confinables. La connaissance de ces conditions initiales et de leur dispersion est importante car elles conditionnent la dynamique du signal détecté (la hauteur de la raie) et sa fluctuation, respectivement. / In order to increase fuel rod performances, the basic mechanisms that promote gas (i.e. He, H2, Kr and Xe) release from irradiated nuclear fuels must be studied. In this context, the CEA fuel study department at Cadarache decided to improve its experimental facility devoted to fuel behaviour under thermal transient by modifying the existing annealing device, called MERARG-II.The first part of this dissertation adresses the fuel gas release monitoring from irradiated fuel during thermal transient. The device choice leads to a quadrupole mass filter as mass analyser according to the specification requirement, i.e. isotopic identification of Xe, Kr and masses at 4 and 2 u. It is commercialized Residual Gas Analyser, mounted in a small-volume vacuum chamber requiring adaptations to be connected to the MERARG II line. The resolution and sensitivity of the mass spectrometer have been evaluated. The calibrated device is being installed in MERARG II replica.The second part of this dissertation relates adaptation to low-mass analysis of an RF 3D ion trap operated a Fourier Transform mode. Theoretically, using this operating mode, the lower the mass, the higher the resolution. More particularly, an ion injection device and its operating mode are studied in order to gain position and velocity distributions of confinable ions. The knowledge of these initial conditions is of a great concern as they fix the signal dynamic (peak height) and the signal fluctuation, respectively. This feasibility study, using simulation, allows us to obtain the optimal values of trap operating condition for 1-6 u mass injection and confinement with high resolution.