This survey has shown, using the Monte Carlo N-Particle(MCNP) code to model a detection system, to demonstrate that it is possible to design a system to measure hazard elements in polluted water. At first, the measurement method needs to be determined. For measuring the specimen component without knowing the accuracy concentration in a short time, when compared with other methods, the Energy-dispersive X-ray fluorescence (ED-XRF) is a good choice for solving this problem. Then, a basic part of this method and actual experiment setting is using the simulation to find the suitable parameters such as the input X-ray energy level, the detector thickness, etc. At last, the polluted water has been measured for evaluating the system function.

Submitted by Rafael Santana (rafael.silvasantana@ufpe.br) on 2017-05-11T18:10:34Z No. of bitstreams: 2 license_rdf: 1232 bytes, checksum: 66e71c371cc565284e70f40736c94386 (MD5) Versão Atualizada Tese Eric Ferreira de Oliveira.pdf: 1865683 bytes, checksum: 517608a245f6372afd45b3bba78733d6 (MD5) / Made available in DSpace on 2017-05-11T18:10:34Z (GMT). No. of bitstreams: 2 license_rdf: 1232 bytes, checksum: 66e71c371cc565284e70f40736c94386 (MD5) Versão Atualizada Tese Eric Ferreira de Oliveira.pdf: 1865683 bytes, checksum: 517608a245f6372afd45b3bba78733d6 (MD5) Previous issue date: 2016-02-29 / CNEN / O estado da arte dos métodos aplicados para processos industriais é atualmente baseado em princípios de reconstruções tomográficas clássicas desenvolvidos para padrões tomográficos de distribuições estáticas, ou seja, são limitados a processos de pouca variabilidade. Ruídos e artefatos de movimento são os principais problemas causados pela incompatibilidade nos dados gerada pelo movimento. Além disso, em processos tomográficos industriais é comum um número limitado de dados podendo produzir ruído, artefatos e não concordância com a distribuição em estudo. Um dos objetivos do presente trabalho é discutir as dificuldades que surgem da implementação de algoritmos de reconstrução em tomografia dinâmica que foram originalmente desenvolvidos para distribuições estáticas. Outro objetivo é propor soluções que visam reduzir a perda de informação temporal devido a utilização de técnicas estáticas em processos dinâmicos. No que diz respeito à reconstrução de imagem dinâmica foi realizada uma comparação entre diferentes métodos de reconstrução estáticos, como MART e FBP, quando usado para cenários dinâmicos. Esta comparação foi baseada em simulações por MCNPX, e também analiticamente, de um cilindro de alumínio que se move durante o processo de aquisição, e também com base em imagens de cortes transversais de técnicas de CFD. Outra contribuição foi aproveitar o canal triplo de cores necessário para exibir imagens coloridas na maioria dos monitores, de modo que, dimensionando adequadamente os valores adquiridos de cada vista no sistema linear de reconstrução, foi possível imprimir traços temporais na imagem tradicionalmente reconstruída. Finalmente, uma técnica de correção de movimento usado no campo da medicina foi proposto para aplicações industriais, considerando-se que a distribuição de densidade nestes cenários pode apresentar variações compatíveis com movimentos rígidos ou alterações na escala de certos objetos. A ideia é usar dados conhecidos a priori ou durante o processo, como vetor deslocamento, e então usar essas informações para melhorar a qualidade da reconstrução. Isto é feito através da manipulação adequada da matriz peso no método algébrico, isto é, ajustando-se os valores para refletir o movimento objeto do previsto ou deformação. Os resultados de todas essas técnicas aplicadas em vários experimentos e simulações são discutidos neste trabalho. / The state of the art methods applied to industrial processes is currently based on the principles of classical tomographic reconstructions developed for tomographic patterns of static distributions, or is limited to cases of low variability of the density distribution function of the tomographed object. Noise and motion artifacts are the main problems caused by a mismatch in the data from views acquired in different instants. All of these add to the known fact that using a limited amount of data can result in the presence of noise, artifacts and some inconsistencies with the distribution under study. One of the objectives of the present work is to discuss the difficulties that arise from implementing reconstruction algorithms in dynamic tomography that were originally developed for static distributions. Another objective is to propose solutions that aim at reducing a temporal type of information loss caused by employing regular acquisition systems to dynamic processes. With respect to dynamic image reconstruction it was conducted a comparison between different static reconstruction methods, like MART and FBP, when used for dynamic scenarios. This comparison was based on a MCNPx simulation as well as an analytical setup of an aluminum cylinder that moves along the section of a riser during the process of acquisition, and also based on cross section images from CFD techniques. As for the adaptation of current tomographic acquisition systems for dynamic processes, this work established a sequence of tomographic views in a just-in-time fashion for visualization purposes, a form of visually disposing density information as soon as it becomes amenable to image reconstruction. A third contribution was to take advantage of the triple color channel necessary to display colored images in most displays, so that, by appropriately scaling the acquired values of each view in the linear system of the reconstruction, it was possible to imprint a temporal trace into the regularly reconstructed image, where the temporal trace utilizes a channel and the regular reconstruction utilizes a different one. Finally, a motion correction technique used in the medical field was proposed for industrial applications, considering that the density distribution in these scenarios may present variations compatible with rigid motions or changes in scale of certain objects. The idea is to identify in some configurations of the temporarily distributed data clues of the type of motion or deformation suffered by the object during the data acquisition, and then use this information to improve the quality of the reconstruction. This is done by appropriately manipulating the weight matrix in the algebraic method, i.e., by adjusting the values to reflect the predicted object motion or deformation. The results of all these techniques applied in several experiments and simulations are discussed in this work.

This thesis demonstrates the advantages of using the Energy-dispersive X-ray fluorescence (ED-XRF) system to quantify the mercury content in fiber banks at first. The Monte Carlo N-Particle (MCNP) code was then used to simulate the XRF system model with suitable parameters such as the input X-ray energy level, the detector material, and the environmental factor (water depth). The SNR results of the mercury spectrum when applying different parameters were obtained. Then, the limit of detection (LOD) and limit of quantification (LOQ) based on the SNR approach are considered. Finally, system parameters were determined in order to obtain more accurate qualitative and quantitative analysis results for future environmental measurements.

Cette thèse consiste en une étude préparatoire de la mesure du rapport alpha de l'233U entre 1eV et 10keV, facteur nécessaire pour calculer le pouvoir de régénération de réacteurs basés sur le cycle 232Th/233U. Cette mesure peut être effectuée au LPSC, sur la plateforme PEREN qui est composée d'un spectromètre à temps de ralentissement au plomb couplé à un GEnérateur de NEutrons Pulsé Intense (GENEPI). Les taux de capture et de fission sont mesurés grâce à 8 scintillateurs YAP utilisés en coïncidence et entourant une chambre à fission. Des mesures préliminaires sur l'235U ont présenté un rapport signal sur bruit très faible malgré les améliorations successives apportées. Les contributions du bruit de fond ont été comprises et quantifiées expérimentalement et via des simulations (MCNP et GEANT4). Il est cependant indispensable d'améliorer le rapport signal sur bruit d'au moins un ordre de grandeur pour obtenir la capture d'un élément fissile sur un tel dispositif expérimental.

Le Réacteur à Sels Fondus (RSF) en cycle Th/U est un des concepts de nouvelle génération pour la production d'énergie nucléaire. Un RSF type se compose d'une structure en graphite, servant de modérateur, percé de canaux dans lesquels circule le sel fondu (^{7}LiF+ThF_{4}+UF_{4}). Les données neutroniques fondamentales pour les simulations numériques sont les sections efficaces de diffusion élastique d'un neutron sur des noyaux de carbone (\sigma_{C}), de fluor (\sigma_{F}) et de lithium 7 (\sigma_{Li}) dans le domaine épithermique. <br /><br />Le but de ce travail est de déterminer précisément \sigma_{C} et \sigma_{F} entre 1 eV et 100 keV. Ces mesures ont été réalisées auprès de la plate-forme d'Etude et de Recherche sur l'Electro-Nucléaire (PEREN) du Laboratoire de Physique Subatomique et de Cosmologie de Grenoble. Elle comprend un GEnérateur de NEutrons Pulsé Intense (GENEPI) produisant des neutrons de 2.5 MeV au centre de massifs ralentisseurs (C et CF_{2}). Des taux de capture sont obtenus, pour des échantillons composés de matériaux de référence (Au, Ag, Mo et In) placés dans les massifs, à l'aide d'un scintillateur YAP couplé à un photo-multiplicateur.<br /><br />Des simulations précises des expériences, avec le code MCNP, ont été réalisées et la comparaison entre la simulation et l'expérience a permis de déterminer \sigma_{C} et \sigma_{F} avec des précisions de 1% et 2% respectivement, mettant en évidence des écarts avec les données nucléaires évaluées (ENDF).<br /><br />Des mesures complémentaires des sections efficaces totales \sigma_{C} et \sigma_{F} à plus haute énergie (200 - 600keV) ont été effectuées au Centre d'Etudes Nucléaires de Bordeaux par une méthode de transmission. Un faisceau de neutrons mono-énergétique est produit par des protons accélérés, dans un accélérateur Van De Graaff, sur une cible de LiF. Les neutrons transmis sont comptés par un détecteur proportionnel à hydrogène. Des écarts de 5% (C) et de 9% (F) par rapport à ENDF ont été mis en évidence.

Le recours à l'énergie électronucléaire pour diminuer les émissions anthropiques de CO2 nécessite des avancées technologiques majeures. Les réacteurs nucléaires de IVe génération doivent répondre à plusieurs contraintes, telles qu'une sûreté améliorée, la régénération du combustible et la minimisation de la production de déchets radioactifs. De ce point de vue, l'utilisation du Cycle Thorium en Réacteurs à Sel Fondu semble prometteuse. Cet axe de recherche, étudié dans le passé, avait cependant débouché sur un concept dont les défauts ont empêché la réalisation. Une nouvelle réflexion est menée afin de trouver des solutions et d'aboutir au concept de Thorium Molten Salt Reactor. Le couplage d'un code de transport de neutrons avec un code d'évolution des matériaux permet de simuler le comportement d'un coeur nucléaire, et de suivre son évolution tout au long de sa vie. Par cette méthode, nous avons étudié un large éventail de configurations de réacteurs. Les performances de ces systèmes ont été évaluées, grâce à un jeu de contraintes qu'ils doivent satisfaire au mieux. Ce travail a permis de comprendre bon nombre de phénomènes physiques régissant le comportement de ces réacteurs. Grâce à cette nouvelle compréhension, la recherche de configurations acceptables a pu aboutir à des solutions satisfaisantes, apportant un souffle nouveau dans le domaine des Réacteurs à Sel Fondu.

Dans l'éventualité d'une contribution significative du nucléaire aux besoins énergétiques mondiaux, le problème de la gestion des déchets actuels remet en question la pérennité de la liere REP. En complément des recherches sur le stockage et l'incinération de ces déchets, il convient donc d'envisager des systemes innovants dédiés à une production d'énergie nucléaire durable, aussi sobre, propre et sûre que possible. Nous nous intéressons ici au concept de réacteur à sels fondus, dont le combustible est liquide. Cette particularité autorise un retraitement en ligne pyrochimique, qui peut permettre de s'affranchir de certaines limites neutroniques. Le projet MSBR (Molten Salt Breeder Reactor) d'un réacteur à sels fluorures et à modérateur graphite a ainsi montré à la fin des années 1960 que la surgénération en cycle thorium et en spectre thermique est accessible avec un retraitement en ligne approprié.<br> A l'aide d'outils de simulation développés autour du code Monte Carlo MCNP, nous réévaluons dans un premier temps les performances d'un système de référence inspiré du projet MSBR. L'étude complète de la phase de mise à l'équilibre de ce réacteur d'une puissance de 2500 MWth, démarré en 232Th/233U, nous permet de valider nos choix de référence. L'équilibre obtenu montre une réduction importante des inventaires et des radiotoxicités induites par rapport aux autres cycles possibles. Le retraitement en ligne associé est suffisamment efficace pour rendre le systeme surgénérateur, avec un temps de doublement d'une trentaine d'années à l'équilibre.<br> A partir du système de référence, nous testons ensuite différentes options en termes d'économie de neutrons, de transmutation et de contrôle de la réactivité. Il en ressort que c'est le retraitement en ligne qui apporte le plus de flexibilité à ce système particulièrement bien adapté à la production d'énergie en cycle thorium. L'étude de scenarios de transition à cette filière quantifie les limites d'un éventuel déploiement à partir du parc français actuel, et montre enfin qu'une gestion raisonnée du plutonium disponible serait nécessaire dans tous les cas.

<p>Two aspects of applied nuclear physics have been studied in this thesis; Monte Carlo simulations for high-sensitivity monitoring of radioactive xenon and high-accuracy neutron-proton scattering measurements for neutron physics applications and fundamental physics.</p><p>The Monte Carlo simulations have been performed for two systems for detection of radioactive xenon, using the MCNP code. These systems, designed for monitoring of violations of the Comprehensive Nuclear-Test-Ban Treaty, are based on coincident detection of electrons and gamma rays, emitted in beta decay of xenon nuclides produced in nuclear weapons explosions. In general, the simulations describe test data well, and the deviations from experimental data are understood. </p><p>The neutron-proton scattering measurements have been performed by measuring the differential <i>np</i> scattering cross section at 96 MeV in the angular range θ_c.m.= 20° – 76°. Together with an earlier data set at the same energy, covering the angles θ_c.m.= 74° – 180°, a new data set has been formed in the angular range θ_c.m.= 20° – 180°. This extended data set has been normalised to the experimental total <i>np</i> cross section, resulting in a renormalisation of the earlier data of 0.7 %, which is well within the stated normalisation uncertainty for that experiment. The results on forward <i>np</i> scattering are in reasonable agreement with theory models and partial wave analyses and have been compared with data from the literature.</p>

Two aspects of applied nuclear physics have been studied in this thesis; Monte Carlo simulations for high-sensitivity monitoring of radioactive xenon and high-accuracy neutron-proton scattering measurements for neutron physics applications and fundamental physics. The Monte Carlo simulations have been performed for two systems for detection of radioactive xenon, using the MCNP code. These systems, designed for monitoring of violations of the Comprehensive Nuclear-Test-Ban Treaty, are based on coincident detection of electrons and gamma rays, emitted in beta decay of xenon nuclides produced in nuclear weapons explosions. In general, the simulations describe test data well, and the deviations from experimental data are understood. The neutron-proton scattering measurements have been performed by measuring the differential np scattering cross section at 96 MeV in the angular range θc.m.= 20° – 76°. Together with an earlier data set at the same energy, covering the angles θc.m.= 74° – 180°, a new data set has been formed in the angular range θc.m.= 20° – 180°. This extended data set has been normalised to the experimental total np cross section, resulting in a renormalisation of the earlier data of 0.7 %, which is well within the stated normalisation uncertainty for that experiment. The results on forward np scattering are in reasonable agreement with theory models and partial wave analyses and have been compared with data from the literature.

This research investigates the use of G-M counters to triage the individuals who have been exposed to a Radiological Dispersal Device (RDD). Upon being exposed to an RDD, inhalation of the airborne radionuclide is a method which someone can receive a considerable amount of dose. Bioassay via analysis of excreta is a commonly used method of determining the dose received, yet it would be cumbersome if there are a large number of people needing to be screened. An in vivo method must be considered so that a non-intrusive and more efficient triaging method can be implemented. Whole body counters are commonly used in counting facilities as an in vivo bioassay method, yet they are limited in number and not easily portable. Therefore, a more portable and more common detection device should be considered. G-M survey meters are common devices that are highly portable, making them ideal candidates to fulfill this necessity. The ease of use contributes to the viability of the device as a portable, in vivo screening device. To analyze this detector, a Monte Carlo model of the detector was created to be used in simulations with the Medical Internal Radiation Dose phantoms. The detector was placed in a few locations on the phantoms. Four locations were strategically chosen for detector placement: the posterior upper right torso, the anterior upper right torso, the lateral upper thigh, and the anterior of the neck. Six phantoms were considered: Reference Male, Female, Adipose Male, Adipose Female, Post Menopausal Adipose Female, and a Child. Six radionuclides were investigated: Am-241, Co-60, Cs-137, I-131, Ir-192, and Sr-90. The nuclides were distributed throughout the phantoms according to Dose and Risk Calculation Software, a code that determines how a radionuclide is distributed over time upon inhalation, ingestion, or injection. A set of time dependent guidelines were developed, determining the count rate per unit dose inhaled for each detector location and phantom type.