The presented thesis focuses on study of transport and thermoelastic properties of materials under conditions of planetary interiors by means of high-pressure experimental tools and finite element modeling, and their role in the dynamics and states of cores of terrestrial planets. Experiments in laser-heated diamond anvil cell (LHDAC) in combination with numerical simulations of heat transfer in DAC are shown to yield information on thermal conductivity of a pressurized sample. The novel technique consists of one-sided laser heating and double-sided temperature measurements and utilizes a precise determination of several parameters in course of the experiment, including the sample geometry, laser beam power distribution, and optical properties of employed materials. The pressure-temperature conditions at the probed portion of the sample are, however, not uniform. To address this problem, thermal pressure in the laser-heated diamond anvil cell and anisotropic thermal conductivity originating from the texture development upon uniaxial compression have been studied by means of numerical simulations. The method for determination of thermal conductivity is applied to iron at pressures up to 70 GPa and temperatures of 2000 K, meeting the Earth’s lower mantle conditions and covering Mercury’s entire core. The obtained results are extrapolated to the conditions of the Earth’s core-mantle boundary using a theoretical model of the density dependence of thermal conductivity of metals and published values on Grüneisen parameter and bulk modulus. After considering the effect of minor core elements, the obtained value at these conditions supports case for the downward revision of the thermal conductivity in the core. From the point of view of core dynamics and energy budget, the lower thermal conductivity implies more favorable conditions to drive the dynamo. Similar scenario applies for Mercury where, for high values of thermal conductivity, heat flux conducted along the iron-core adiabat exceeds the actual heat flux through the core-mantle boundary. This leads to a negative rate of entropy production in the core that makes it impossible to sustain the dynamo process presumably responsible for the observed magnetic field of Mercury.

abstract: Material extrusion based rapid prototyping systems have been used to produceprototypes for several years. They have been quite important in the additive manufacturing field, and have gained popularity in research, development and manufacturing in a wide field of applications. There has been a lot of interest in using these technologies to produce end use parts, and Fused Deposition Modeling (FDM) has gained traction in leading the transition of rapid prototyping technologies to rapid manufacturing. But parts built with the FDM process exhibit property anisotropy. Many studies have been conducted into process optimization, material properties and even post processing of parts, but were unable to solve the strength anisotropy issue. To address this, an optical heating system has been proposed to achieve localized heating of the pre- deposition surface prior to material deposition over the heated region. This occurs in situ within the build process, and aims to increase the interface temperature to above glass transition (Tg), to trigger an increase in polymer chain diffusion, and in extension, increase the strength of the part. An increase in flexural strength by 95% at the layer interface has been observed when the optical heating method was implemented, thereby improving property isotropy of the FDM part. This approach can be designed to perform real time control of inter-filament and interlayer temperatures across the build volume of a part, and can be tuned to achieve required mechanical properties. / Dissertation/Thesis / Masters Thesis Mechanical Engineering 2016

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Ultra-fast laser heating of nano-films is investigated using 3-D Dual Phase Lag heat transport equation with laser heating at different locations on the metal film. The energy absorption rate, which is used to model femtosecond laser heating, is modified to accommodate for three-dimensional laser heating. A numerical solution based on an explicit finite-difference method is employed to solve the DPL equation. The stability criterion for selecting a time step size is obtained using von Neumann eigenmode analysis, and grid function convergence tests are performed. DPL results are compared with classical diffusion and hyperbolic heat conduction models and significant differences among these three approaches are demonstrated. We also develop an implicit finite-difference scheme of Crank-Nicolson type for solving 1-D and 3-D DPL equations. The proposed numerical technique solves one equation unlike other techniques available in the literature, which split the DPL equation into a system of two equations and then apply discretization. Stability analysis is performed using a von Neumann stability analysis. In 3-D, the discretized equation is solved using delta-form Douglas and Gunn time splitting. The performance of the proposed numerical technique is compared with the numerical techniques available in the literature.

Lors d’un accident grave dans un réacteur nucléaire à eau pressurisée, le combustible nucléaire va réagir avec le gaines en Zircaloy, les absorbants neutroniques et les structures métalliques environnantes pour former un mélange partiellement ou complètement fondu. Ce cœur fondu peut ensuite interagir avec la cuve en acier du réacteur pour former un mélange appelé corium en cuve. Par la suite, le corium peut percer la cuve et venir se déverser sur le radier en béton en-dessous du réacteur. En fonction du scénario considéré, le corium qui va réagir avec le béton peut être constitué soit d’une seule phase liquide oxyde ou de deux liquides, métallique et oxyde. L’objectif de la thèse est l’étude de la thermodynamique du corium en cuve, prototypique U-Pu-Zr-Fe-O. L’approche utilisée est basée sur la méthode CALPHAD, qui permet de développer un modèle thermodynamique sur ce système complexe à partir de données expérimentales thermodynamiques et de diagramme de phases. Des traitements thermiques sur le système O-U-Zr ont permis de mesurer deux conodes dans la lacune de miscibilité à l’état liquide à 2567 K. De plus, des températures de liquidus ont été mesurées sur trois échantillons riches en Zr, en utilisant le montage de chauffage laser de l’ITU. Par la même méthode, des températures de solidus ont été obtenues sur le système UO2-PuO2-ZrO2. L’influence de l’atmosphère réductrice ou oxydante sur le comportement à la fusion de ce système a été étudiée pour la première fois. Les résultats montrent que la stœchiométrie en oxygène de ces oxydes dépend fortement du potentiel d’oxygène et de la composition en métal des échantillons. La lacune de miscibilité à l’état liquide a également été mise en évidence dans un échantillon U-O-Zr-Fe. L’ensemble de ces nouvelles données expérimentales avec celles de la littérature a permis de développer le modèle sur le système U-Pu-Zr-Fe-O. Pour tous les échantillons, des calculs de chemin de solidification avec ce modèle ont servi à interpréter les microstructures de solidification observées. Un bon accord est obtenu entre les calculs et les résultats expérimentaux. Des traitements thermiques sur deux échantillons de corium hors cuve ont permis de montrer l’influence de la composition du béton sur la nature des phases liquides formées à haute température. Les microstructures de solidification ont été interprétées à l’aide de calculs avec la base de données TAF-ID. En parallèle, un nouveau montage expérimental appelé ATTILHA, utilisant la lévitation aérodynamique et le chauffage laser, a été conçu et développé pour mesurer des données de diagramme de phase à haute température. Ce montage a été validé avec des systèmes oxydes bien connus. De plus, cette méthode a permis d’observer in-situ à l’aide de la caméra infra-rouge la formation de la lacune de miscibilité à l’état liquide dans le système O-Fe-Zr lors de l’oxydation d’une bille d’alliage Fe-Zr. La prochaine étape du développement est la nucléarisation du montage pour effectuer des mesures sur des échantillons contenant de l’uranium. La mise en place d’une caméra ultra rapide (5000 Hz) pour l’étude de propriétés thermo-physiques de mélanges de corium en cuve et hors cuve est également envisagée. La synergie entre le développement de ces outils expérimentaux et de calcul devrait permettre d’améliorer la description thermodynamique du corium et des codes de calcul sur les accidents graves utilisant ces données thermodynamiques. / During a severe accident in a pressurised water reactor, the nuclear fuel can interact with the Zircaloy cladding, the neutronic absorber and the surrounding metallic structure forming a partially or completely molten mixture. The molten core can then interact with the reactor steel vessel forming a mixture called in-vessel corium. In the worst case, this mixture can pierce the vessel and pour onto the concrete underneath the reactor, leading the formation of the ex-vessel corium. Furthermore, depending on the considered scenario, the corium can be formed by a liquid phase or by two liquids, one metallic the other oxide. The objective of this thesis is the investigation of the thermodynamics of the prototypic in-vessel corium U-Pu-Zr-Fe-O. The approach used during the thesis is based on the CALPHAD method, which allows to obtain a thermodynamic model for this complex system starting from phase diagram and thermodynamic data. Heat treatments performed on the O-U-Zr system allowed to measure two tie-lines in the miscibility gap in the liquid phase at 2567 K. Furthermore, the liquidus temperatures of three Zr-enriched samples have been obtained by laser heating in collaboration with ITU. With the same laser heating technique, solidus temperatures have been obtained on the UO2-PuO2-ZrO2 system. The influence of the reducing or oxidising on the melting behaviour of this system has been studied for the first time. The results show that the oxygen stoichiometry of these oxides strongly depends on the oxygen potential and on the metal composition of the samples. The miscibility gap in the liquid phase of the U-Zr-Fe-O system has been also observed. The whole set of experimental results with the literature data allowed to develop the thermodynamic model of the U-Pu-Zr-Fe-O system. Solidification path calculations have been performed for all the investigated samples to interpret the microstructures of the solidified samples. A good accordance has been obtained between calculation and experimental results. Heat treatments on two ex-vessel corium samples showed the influence of the concrete composition on the nature of the liquid phases formed at high temperature. The observed microstructures have been interpreted by means of calculation performed with the TAF-ID database. In parallel, a novel experimental setup named ATTILHA based on aerodynamic levitation and laser heating has been conceived and developed to obtain high temperature phase diagram data. This setup has been validated on well-known oxide systems. Furthermore, this technique allowed to observe in-situ, by using an infrared camera, the formation of a miscibility gap in the liquid phase of the O-Fe-Zr system by oxidation of a Fe-Zr sample. The next step of the development will be the nuclearization of the apparatus to investigate U-containing samples. The implementation of a very fast visible camera (5000 Hz) to investigate the thermo-physical properties of in-vessel and ex-vessel corium mixtures is also underway. The synergy between the development of experimental and calculation tools will allow to improve the thermodynamic description of the corium and the severe accident code using thermodynamic input data.