Academic literature on the topic 'Combustibles nucléaires – Gaines – Matériaux'
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Journal articles on the topic "Combustibles nucléaires – Gaines – Matériaux"
REBAK, Raul B. "Matériaux avancés pour les combustibles des réacteurs à eau légère - Matériaux nucléaires évolutifs et révolutionnaires." Génie nucléaire, May 2024. http://dx.doi.org/10.51257/a-v1-bn3768.
Full textDissertations / Theses on the topic "Combustibles nucléaires – Gaines – Matériaux"
Yang, Hongyue. "Approche thermomécanique du phénomène d'interaction pastille-gaine dans un crayon combustible." Lyon, INSA, 1995. http://www.theses.fr/1995ISAL0015.
Full textThe objective of this study is to investing ate the thermo-mechanical behaviour of a fuel rod which is composed of a tube containing cylindrical uranium dioxide fuel pellets. A lot of work has been particularly devoted to the design and the set up of an original experimental device which allows the simulation of the pellet-cladding mechanical interaction during the uprating of water pressurised reactors. The mode) is a two-dimensional plane stress one which has not taken the effects of irradiation and chemical transformation into account. Both experimental and numerical analyses on the cladding stresses concentration have been carried out. Different effects have been studied including the presence of cracks in the pellets, the coefficient of friction between pellet-cladding, the initial gap at the pellet-cladding interface, the cladding external pressure and the variation of power, The comparison of experimental and numerical results, for a particular case, enables a better understanding of pellet-cladding mechanical interaction et demonstrates that the modelisation of the joint element used in the pellet-cladding interface is appropriate. It should be pointed out that a simple elastic approach had been carried out before the thermoplastic experiment was done, aiming at analysing the stress concentrations due to the presence of cracks in the pellet
Ougier, Michaël. "Etude de l’élaboration de revêtements autocicatrisants pour le développement de matériaux robustes en condition nucléaire." Thesis, Université Paris-Saclay (ComUE), 2019. http://www.theses.fr/2019SACLE028/document.
Full textThis study aims to improve oxidation resistance of nuclear fuel claddings in accident conditions. In this context, Cr-Al-C and Cr2AlC coatings deposition and their behavior were studied. Firstly, we investigated the influence of HiPIMS process parameters on the properties of the plasma and the deposited films. Despite more intense ionic fluxes due to the HiPIMS process, coatings do not crystallize without an additional energy supply. Partially crystallized Cr2AlC thin films were obtained by a 500°C annealing of as-deposited Cr-Al-C coatings. This two-step process is a viable solution to protect nuclear claddings with Cr2AlC coating while maintaining the metallurgical properties of the zirconium-based substrates. Secondly, the assessment of the oxidation resistance of as-deposited and annealed coatings revealed significant protective effect against rapid oxidation under dry and wet air at high temperatures (up to 1200°C) owing to the formation of a continuous oxide layer. During the first stages of oxidation, this layer is made of α Al2O3 and Cr2O3 for as-deposited coating while only α-Al2O3 is present for the annealed one. Because of Al depletion, coatings later deteriorate and form a residual and porous intermediate chromium carbide (Cr7C3) layer which further fully oxidizes. It was shown that the inward diffusion of Al with Zr also accelerates the coating deterioration. To improve the oxidation resistance of these coatings, multilayered architectures were developed. Adding a molybdenum interlayer as diffusion barrier globally decreased the oxidation resistance of the coating. In contrast, topping Cr-Al-C and Cr2AlC with a Cr layer improved oxidation behavior over single-layer coatings
Pantera, Laurent. "Application d'une méthodologie statistique à la compréhension du phénomène de corrosion du surgénérateur Phénix." Compiègne, 1992. http://www.theses.fr/1992COMPD509.
Full textZouari, Ahmed. "Comportement des gaines en alliages de zirconium en conditions thermo-mécaniques représentatives d’un accident RIA." Thesis, Université Paris sciences et lettres, 2020. http://www.theses.fr/2020UPSLM058.
Full textThe aim of this work is to enhance the understanding of the thermomechanical behavior at rupture of the fuel rod cladding during an accidental transient of the RIA type. A new mechanical test has been developed in order to apply a strain biaxiality ratio ɛzz/ɛ00 between -0,2 et 1. It allows reproducing loading conditions close to the ones occurring during a RIA accident. An experimental campaign at room temperature carried out with this device made it possible to study the effects of strain biaxiality ratios and strain rate on the fracture of the cladding. The tests carried out show a significant effect of the biaxiality on the hoop strain at failure which has a minimum of a plane strain state where the strain biaxiality is close to 0. A slight decrease in ductility was also recorded during the increase in the strain rate for all biaxiality levels. The damage mechanisms and failure modes of specimens are identified from the surfaces and failure profiles depending on the stress conditions. Numerical finite element simulations were performed with the CAST3M code to model the test and simulate the failure of cladding with biaxial loading. A second experimental device has been developed to couple the effects of biaxial mechanical loading and rapid thermal loading. The objective is to heat the cladding with temperature rise rates greater than 100 °C.s-1 in order to avoid the restoration of the defects linked to the hydriding and to the irradiation during the test. The method was used to perform thermomechanical tests at high heating rates, high strain rates, and high biaxiality levels to reproduce full loadings in a reactivity accident. The first results show, for a virgin cladding, that the strain at the break was not affected by temperature or by the rate of heating. Finite element simulations were undertaken to model the different heating methods tested and to optimise the chosen method. These simulations made it possible in particular to model the passage of electric current and heat flow through solid-solid interfaces
Khelifi, Nour-Eddine. "Modélisation de la croissance sous irradiation de feuillards de zircaloy-4 détendus en fonction de leur texture." Metz, 1991. http://docnum.univ-lorraine.fr/public/UPV-M/Theses/1991/Khelifi.Nour_eddine.SMZ9124.pdf.
Full textAutones, Lucas. "Élaboration d’aciers ODS (Oxide Dispersion Strengthened) par fabrication additive laser et cold spray : compréhension des relations procédés - microstructures." Electronic Thesis or Diss., Université de Lille (2022-....), 2022. http://www.theses.fr/2022ULILR004.
Full textODS (Oxide Dispersion Strengthened) steels are materials that exhibit very good resistance to creep and swelling under irradiation. These properties make them good candidates for cladding materials in Generation IV reactors, or for structural materials in thermonuclear fusion reactors. The dispersion of the nano-oxides, which reinforce the material, is obtained by powder metallurgy. Mechanical-alloying of an atomized steel powder with an oxide powder (Y2O3) results in the oxide dissolution in the matrix. During hot consolidation (hot isostatic pression or hot extrusion), the precipitation of the nano-oxides takes place. Designs of component with these materials and their final geometry could be improved using additive manufacturing.Since the 2010s, recent developments in additive manufacturing technologies could enable to reduce lead times and costs, while increasing the geometric, hierarchical and functional complexity of parts. They pave the way to new freedom of design compared to conventional subtractive manufacturing processes.The objective of this thesis work was to assess the potentials of different additive manufacturing techniques (SLM, DMD, and Cold Spray) for ODS steels.Thus, three types of ODS powder (mechanically-alloyed, composite and STARS) were obtained to determine the most interesting powder-process combinations. The materials produced from these different combinations have been characterized at several scales. The amount of macroscopic defects (porosities, cracks) was analyzed in order to optimize the manufacturing parameters. Their granular microstructure was observed before and after annealing at 1100 °C by optical and electron microscopy (SEM, EBSD). The nano-precipitation was analyzed by SEM, TEM and by small angle X-rays scattering. An image analysis method combining high definition electron microscopy images and a machine learning software was implemented. Finally, the high temperature tensile properties of these different materials were evaluated and are in good agreement with their microstructural characteristics. The comparison of the whole characterization results enabled to select the relevant manufacturing paths.The results obtained indicate that laser additive manufacturing processes (SLM, DMD) lead to ODS steels with low performance, regardless the type of powder used. The yttrium content can greatly decrease after consolidation. It also forms fragile Y-rich coarse phases, and the density of the nano-precipitates population appears very low. These microstructural characteristics induce tensile properties equivalent to those of an unreinforced steel. Nevertheless, the composite powder elaboration method implemented in this work makes it very easy to adapt the nature and content of the reinforcements added to the base powder. Using TiC nano-particles, very fine microstructures composed of equiaxed grains were obtained. These unusual microstructures in laser additive manufacturing offer interesting prospects.ODS steels obtained by cold spray from a mechanically-alloyed powder have characteristics similar to conventional ODS steels. After annealing, these materials have a microstructure similar to the ODS steels obtained by HIP. However, the coarse grains take up a much larger fraction of the microstructure and attest to a more advanced recrystallization. The lower hardness and elastic limit of this material compared to its HIP equivalent confirm this result, which is very encouraging if further shaping should be aimed. The very high density of Y-Ti-O nano-oxides in the Cold Sprayed ODS steel enables to achieve a mechanical resistance at 700 °C which is 50 MPa higher than the HIPed ODS. However, this material exhibits a loss of ductility which will have to be resolved. The analyzes carried out enabled to suggest two mechanisms to explain this damage, which would be caused by the presence of microcracks and porosities in the part
Bakkali, Amin El. "Conception et mise au point d'un essai de courbe R sur des gaines d'éléments combustibles nucléaires." Châtenay-Malabry, Ecole centrale de Paris, 1987. http://www.theses.fr/1987ECAP0056.
Full textRoussette, Sophie. "Analyse par champs de transformation de matériaux élastoviscoplastiques multiphases : application aux combustibles MOX." Aix-Marseille 2, 2005. http://www.theses.fr/2005AIX22054.
Full textThe description of the overall behavior of nonlinear materials with nonlinear dissipative phases requires an infinity of internal variables. An approximate model involving only a finite number of internal variables, Nonuniform Transformation Field Analysis, is obtained by considering a decomposition of these variables on a finite set of nonuniform transformation fields, called plastic modes. The method is initially developed for incompressible elastoviscoplastic materials. Karhunen-Loève expansion is proposed to optimize the plastic modes. Then the method is extended to porous elastoviscoplastic materials. Finally the transformation field analysis, developed by Dvorak, is applied to nuclear fuels MOX. This method enables to make sensitivity studies to determine the role of some microstructural parameters on the fuel behaviour. Moreover the adequacy of the nonuniform method for fuels MOX is shown, the final objective being to be able to apply the model to the MOX in 3D
Robert-Berat, Laurence. "Influence d'une couche de zircone sur le comportement mécanique des tubes en zircaloy-4." Clermond-Ferrand 2, 2001. http://www.theses.fr/2001CLF2A001.
Full textQuaranta, Delphine. "Étude de voies potentielles pour le recyclage du zirconium des gaines en Zircaloy des combustibles nucléaires usés." Thesis, Toulouse 3, 2019. http://www.theses.fr/2019TOU30038.
Full textZircaloy-4 is an alloy mainly composed of zirconium (~ 98%wt.) constituting the cladding of nuclear assemblies. Currently, used Zircaloy claddings are intended for deep geological storage due to their contamination by radioelements from the nuclear reaction and the reprocessing process. They are classified as long-lived intermediate-level waste according to ANDRA recommendations (radioactivity: 10 6 - 10 9 Bq/g, periods > 31 years), as they represent 25%wt. of the assembly inventory. Zirconium recycling thus could present an economic interest, either to upgrade the zirconium by remanufacturing sheaths (with the constraint imposed by the residual presence of 93Zr), or to downgrade the cladding wastes into low activity waste. This thesis aims to study the potential routes for the recycling of zirconium contained in spent Zircaloy sheaths, and more precisely electrorefining in molten fluorides. The study of Zircaloy sheath composition of spent nuclear fuel was first carried out to identify the radioelements present in used claddings. These elements are either activation products (Cr, Fe, Ni, Co, Sn, etc.), or fission products (H, Sr (+ Y), Cs (+ Ba), Eu, etc.), or actinides (U, Pu, Am and Cm). An electrochemical study of the zirconium (IV) ions was carried out in LiF-NaF at 750 °C to determine its reduction mechanisms into metallic zirconium. Then, a nucleation / growth study was performed to optimize the operating conditions (ie nature of the cathode, concentration of ZrF4, current density applied, etc.), to obtain an adherent metal zirconium deposit on inert solid cathode. The last part of this work was focused on the electrorefining of "fresh" Zircaloy sections, i.e. before its stay in the reactor. Particular attention was paid to the behavior of the alloy constituents (Fe, Cr and Sn), during the electrolysis process. This work proposes a first scenario for the reprocessing of spent fuel claddings
Books on the topic "Combustibles nucléaires – Gaines – Matériaux"
P, Sabol George, Bradley E. R, and International Symposium on Zirconium in the Nuclear Industry (11th : 1995 : Garmisch-Partenkirchen, Germany), eds. Zirconium in the nuclear industry: Eleventh international symposium. West Conshohocken, PA: ASTM, 1996.
Find full textNuclear materials. Weinheim: VCH, 1994.
Find full textFrost, Brian R. T. Nuclear Materials, Part II (Materials Science and Technology : a Comprehensive Treatment, Vol 10b). John Wiley & Sons Inc, 1994.
Find full textGarde, Anand M. Zirconium in the Nuclear Industry: Tenth International Symposium (Astm Special Technical Publication// Stp). American Society for Testing & Materials, 1995.
Find full text(Editor), E. Ross Bradley, and George P. Sabol (Editor), eds. Zirconium in the Nuclear Industry (Astm Special Technical Publication// Stp). American Society for Testing & Materials, 1997.
Find full textPeterson, Reid. Engineering Separations Unit Operations for Nuclear Processing. Taylor & Francis Group, 2019.
Find full textPeterson, Reid. Engineering Separations Unit Operations for Nuclear Processing. Taylor & Francis Group, 2019.
Find full textPeterson, Reid. Engineering Separations Unit Operations for Nuclear Processing. Taylor & Francis Group, 2019.
Find full textPeterson, Reid. Engineering Separations Unit Operations for Nuclear Processing. Taylor & Francis Group, 2019.
Find full textPeterson, Reid. Engineering Separations Unit Operations for Nuclear Processing. Taylor & Francis Group, 2019.
Find full textBook chapters on the topic "Combustibles nucléaires – Gaines – Matériaux"
PAREIGE, Philippe, and Christophe DOMAIN. "Les alliages métalliques." In Les matériaux du nucléaire sous irradiation, 51–90. ISTE Group, 2024. http://dx.doi.org/10.51926/iste.9148.ch2.
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