The Oak Ridge Isotope Generation and Depletion – Automatic Rapid Proccessing (ORIGEN-ARP) deterministic code has been extensively utilized for determining nuclide concentrations at various specific burnup values for a variety of nuclear reactor designs. Given nuclide concentrations or ratios, such calculations can be used in nuclear forensics and nuclear non-proliferation applications to reverse-calculate the type of reactor and specific burnup of the fuel from which the nuclides originated. Recently, Los Alamos National Laboratory has released a version of its probabilistic radiation transport code, MCNPX 2.6.0, which incorporates a fuel burnup feature which can also determine, via the probabilistic Monte Carlo method, nuclide concentrations as a function of fuel burnup. This dissertation compares the concentrations of 46 nuclides significant to nuclear forensics analyses for different reactor types using results from the ORIGEN-ARP and the MCNPX 2.6.0 codes. Three reactor types were chosen: the Westinghouse 17x17 Pressurized Water Reactor (PWR), the GE 8x8-4 Boiling Water Reactor (BWR), and the Canadian Deuterium Uranium, CANDU-37, reactor. Additionally, a sensitivity study of the different reactor parameters within the MCNPX Westinghouse 17x17 PWR model was performed. This study analyzed the different nuclide concentrations resulting from minor perturbations of the following parameters: assembly rod pitch, initial moderator boron concentration, fuel pin cladding thickness, moderator density, and fuel temperature. / text

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Ce travail de thèse a porté sur le développement de membranes céramiques pour la filtration de colloïdes issus de la corrosion dans le circuit primaire des REP. La voie des polymères précéramiques a été mise en œuvre par la synthèse d’un polyborocarbosilane (PBC) à partir d’allylhydridopolycarbosilane conduisant à une céramique de type SiBC. Des billes de PMMA mono disperses d’une taille de 1,5 et 0,3 µm ont été préparées pour servir d’agent porogène pour créer une porosité contrôlée. Des objets micro-cellulaires 3D de forme circulaire ont été élaborés par pressage uni-axial avec ajout de billes de PMMA commercial pour servir de support macroporeux. Une étude de cristallinité à haute température (> 1000 °C) a été réalisée, montrant son influence sur la stabilité du matériau. La couche sélective a été préparée par dip-coating à partir de différentes formulations de barbotine contenant du PBC et les billes de PMMA élaborées. La stabilité physico-chimique des supports micro-cellulaires a été étudiée grâce à des essais de vieillissement en micro-autoclave en milieu primaire simulé. La résistance à la filtration a été testée grâce à un essai sur un dispositif de filtration connecté à un moyen d’essai de laboratoire permettant de simuler les conditions des REP. / This work has been focused on the development of ceramic membranes for the filtration of colloids resulting from corrosion in the primary loop of PWR. SiBC ceramics were synthesized by the preceramic polymers route from a polyborocarbosilane (PBC) obtained from allylhydridopolycarbosilane. Single-dispersed PMMA beads with a size of 1.5 and 0.3 μm were prepared to be used as a porogen agent to lead to a controlled porosity of the selective layer. 3D micro-cellular objects with a circular shape were developed by uni-axial pressing with the addition of commercial PMMA beads to serve as a macroporous support. A crystallinity study at high temperature (> 1000 ° C) was carried out showing its influence on the stability of the material. The selective layer was prepared by dip-coating from various slurry formulations containing PBC and the prepared PMMA beads. The chemical and physical stability of the microcellular supports was studied by ageing tests in a simulated primary water chemistry. The filtration resistance was tested by means of tests on a filtration device connected to a laboratory loop which simulates the conditions of the PWRs.

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Made available in DSpace on 2014-10-09T12:26:23Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:04:07Z (GMT). No. of bitstreams: 0 / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP