Academic literature on the topic 'Dépôts de déchets radioactifs – Restauration'
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Dissertations / Theses on the topic "Dépôts de déchets radioactifs – Restauration":
Sakael, Clément. "Modélisation de la microstructure des alliages de Zirconium irradiés : application à un transitoire Accident de Perte de Réfrigérant Primaire et à la restauration en aval du cycle." Electronic Thesis or Diss., Centrale Lille Institut, 2023. http://www.theses.fr/2023CLIL0010.
The subject of this thesis concerns zirconium alloys which are used to manufacture the fuel rod cladding and fuel assemblies of pressurized water nuclear reactors. This type of alloy is chosen in the nuclear field for its low thermal neutron capture cross section. However, under neutron irradiation, changes in shape and volume, an increase in hardness and a significant reduction in the ductility of the material are observed, which means an increase in its embrittlement. This work focuses on the irradiation-induced growth of the cladding that results from an elongation in the basal plane and a contraction along the c ⃗ axis of the hexagonal lattice of the alpha phase of zirconium. This phenomenon amplifies beyond a threshold dose that coincides with the nucleation of dislocation loops and the formation of loop alignments as layers parallel to the basal plane. Nevertheless, the mechanisms of nucleation of defect clusters such as dislocation loops are still to be clarified. In order to have a better understanding of these phenomena, a multi-scale approach was used to model the evolution of the microstructure of zirconium alloys (i) during irradiation, (ii) during the transient phase of a loss-of-coolant accident (LOCA) and (iii) during the downstream restoration of the cycle. First, atomic scale calculations based on density functional theory (DFT) and empirical potentials are performed to determine the properties and characteristics of point defect clusters (self-interstitial clusters, vacancy clusters and dislocation loops).In order to have a better characterization of self-interstitial, the migrationenergies and diffusion coefficients of di- and tri-self-interstitials are calculated in moleculardynamics using DFT. Some of the results obtained by atomistic calculations are used as inputdata for an object kinetic Monte Carlo (OKMC) code, which simulates the evolution of themicrostructure of zirconium under conditions (i) to (iii)
Petit, Jean-Claude. "Le stockage des déchets radioactifs : perspective historique et analyse sociotechnique." Paris, ENMP, 1993. http://www.theses.fr/1993ENMP0419.
Coulon, Hervé. "Propriétés physico-chimiques de sédiments argileux français : contribution au stockage de déchets radioactifs." Lille 1, 1987. http://www.theses.fr/1987LIL10153.
Vinkler, Fabrice. "Couplages hydromécaniques dans les massifs rocheux : du stockage de déchets radioactifs à la stabilité des mines abandonnées." Vandoeuvre-les-Nancy, INPL, 1999. http://www.theses.fr/1999INPL099N.
Mellak, Abderrahmane. "Faisabilité des coulis de ciment saumurés et microsilicés adaptés aux formations salifères : application au domaine pétrolier et au stochage des déchets radioactifs." Université Robert Schuman (Strasbourg) (1971-2008), 1994. http://www.theses.fr/1995STR30004.
Nava, Romain. "Étude du cadre juridique relatif à la gestion des déchets radioactifs." Thesis, Aix-Marseille, 2016. http://www.theses.fr/2016AIXM1034.
Radioactive waste appeared simultaneously with the discovery of artificial radioactivity and saw their output is significantly increased with the development of the civil nuclear industry in the 1960s. Notwithstanding, it is only very recently that’s law has seized the difficult issue of their management through texts devoted to it.In the same way that radioactive waste is managed separately according to their activity and half-life, the legal framework for the management of radioactive waste has naturally led to a temporal dichotomy. Then we distinguish two main corpus of standards. The first-one supervises the radioactive waste whose management modes to immediately ensure the safety of people and the environment while the second-one deals with radioactive waste for which security must be guaranteed on long term, insofar as it does not exist to date definitive management solution for waste.This work aims to show how the specific provisions of each of the two bodies involved in the safety of people and the environment and expose potential persistent difficulties
Lefebvre, Christophe. "Influence de la cristallisation des oxyhydroxydes de fer sur la rétention du radium, du zinc, de l'arsenic et de l'uranium." Paris 11, 2002. http://www.theses.fr/2002PA112298.
The extraction of uranium leads to the creation of mill tailings containing numerous elements such as radium, zinc, arsenic and residual uranium. Those residues are disposed at the surface and shall be a long-term efficient protection barrier against the pollution of the elements that they contain. It was demonstrated that those elements are mostly contained in amorphous iron oxy-hydroxydes that precipitate during the treatment of the residues. Those iron oxy-hydroxydes (OHF) naturally crystallise to goethite and hematite : their retention properties can thus change and may have consequences on the immobilization of the elements that are still unknown. The objective of this work is therefore to understand the behavior of radium, zinc, arsenic and uranium during the crystallization of the amorphous OHF to goethite and hematite. The first part of the work consisted in defining a method that allows to reproduce the long-term crystallization of the OHF but on a reduced period of time in laboratory. Geothite was the only ultimate phase created by this method. Some hematite was obtained in presence of calcium. During the first steps of the OHF precipitation, radium was completely sorbed but the analysis demonstrated that radium was leached in the solution while the OHF crystallized in goethite. This phenomena was also observed in presence of calcium, although it was slower due to the fact that the crystallisation into goethite was slower too. This behavior could not be reproduced on the OHF coming from the Ecarpière site : radium was still contained in the solid as the OHF were still amorphous. Zinc, arsenic and uranium were entirely contained in the OHF, as soon as it was precipitating. No leaching could be observed, suggested that zinc and arsenic were integrated in the OHF structure
Bertrand, Nathalie. "Prévision de la corrosion sèche des conteneurs de déchets radioactifs en condition d'entreposage : étude des mécanismes d'oxydation du fer à basse température et simulation numérique de la croissance d'une couche d'oxyde." Phd thesis, Toulouse, INPT, 2006. https://hal.science/tel-04576177.
In the framework of research on long term behaviour of radioactive waste containers, this work consists on the one hand in the study of low temperature oxidation of iron and on the other hand in the development of a numerical model of oxide scale growth. Isothermal oxidation experiments are performed on pure iron at 300 and 400°C in dry and humid air at atmospheric pressure. Oxide scales formed in these conditions are characterized. They are composed of a duplex magnetite scale under a thin hematite scale. The inner layer of the duplex scale is thinner than the outer one. Both are composed of columnar grains, that are smaller in the inner part. The outer hematite layer is made of very small equiaxed grains. Markers and tracers experiments show that a part of the scale grows at metal/oxide interface thanks to short-circuits diffusion of oxygen. A model for iron oxide scale growth at low temperature is then deduced. Besides this experimental study, the numerical model EKINOX (Estimation KINetics OXidation) is developed. It allows to simulate the growth of an oxide scale controlled by mixed mechanisms, such as anionic and cationic vacancies diffusion through the scale, as well as metal transfer at metal/oxide interface. It is based on the calculation of concentration profiles of chemical species and also point defects in the oxide scale and in the substrate. This numerical model does not use the classical quasi-steady-state approximation and calculates the future of cationic vacancies at metal/oxide interface. Indeed, these point defects can either be eliminated by interface motion or injected in the substrate, where they can be annihilated, considering sinks as the climb of dislocations. Hence, the influence of substrate cold-work can be investigated. The EKINOX model is validated in the conditions of Wagner's theory and is confronted with experimental results by its application to the case of high temperature oxidation of nickel
Nguyen, Minh Thu. "Modélisation hydromécanique des ouvrages de stockage des déchets radioactifs avec prise en compte de l'endommagement et du transfert de l'hydrogène." Rennes, INSA, 2008. http://www.theses.fr/2008ISAR0006.
The argilite of Callovo Oxfordien is a sedimentary rock formed in sea water which is made up mainly of quartz, carbonates, argillaceous minerals and various minerals. This heterogeneity of constitution associated with a very low porosity of about 12% confers on argillite a specific behaviour. Indeed this specific behaviour is induced by: (i) of the mechanisms on a microscopic scale of type forces contact with friction for solid minerals quartz and calcite, of repulsion and viscosity for argillaceous minerals and (ii) of the strong interactions between the solid and fluid phases. Thus the conceptual model of the short-term behaviour is proposed while being based on five hydraulic characteristics: (1) two surfaces of loads of the type Drescher & Mroz, associated a pressure of consolidation of 200MPa and a cohesion on healthy argillite, (2) the creation of an anisotropic damage induced by the strains in extension under states of stresses deviators, (3) a distribution of the stress between the solid phases and fluids which uses the coefficient of Biot depend on the maximum damage, (4) a concept of the effective stress for the partially saturated states by calling upon an equivalent pore pressure which depends on the capillary pressure and an average value of the damage and (5) the absence of volumic strains of swelling on healthy argillite. The plastic strain-rates are specified by the non_associative flow rule with the plastic loading surface F and the plastic potential G. On the other hand the behaviour differed from argillite utilizes many mechanisms, chemical, physicochemical and a slip on the scale of the argillaceous layers inducing of the phenomena of viscosity. In the absence of a consensus related mainly to the experimental difficulties and being the subject of current research of the geotechnical grouping of research, one thus proposed a simplified macroscopic model. The introduction of a phase gas into the computer code of finite elements CLEO allowing simulating the transfer of hydrogen. The dealt with problems relate to a standard work cell in direct contact with argillite (without bentonite barrier) with a production of H2 variable in time. These modelling are proposed without heating effect. Lastly, simulations of the saturation of an embanked gallery have the aim of studying the basic phenomena brought into play at the time of the resaturation of a gallery. One proposed a hierarchisation in the processes of simulation by adopting the development of the two conceptual models, one bearing on physics and the other on the numerical aspects. The numerical conceptual model milked space-time introduction of the constituent voluminal elements
Hoteit, Hussein. "Simulation d'écoulements et de transports de polluants en milieu poreux : application à la modélisation de la sûreté des dépôts de déchets radioactifs." Rennes 1, 2002. http://www.theses.fr/2002REN10060.
Books on the topic "Dépôts de déchets radioactifs – Restauration":
Énergie atomique du Canada, limitée. Bureau de gestion des déchets radioactifs de faible activité. and Canada Ressources naturelles Canada, eds. Inventaire des déchets radioactifs au Canada. Ottawa: Bureau de gestion des déchets radioactifs de faible activité, 2004.
Canada. Commission de contrôle de l'énergie atomique. La réglementation des déchets de combustible nucléaire. Ottawa, Ont: Commission de contrôle de l'énergie atomique, 1995.
Canada, Atomic Energy of. Low-level radioactive waste management office: Annual report 2004-2005 = Bureau de gestion des déchets radioactifs de faible activité : rapport annuel 204-2005. Ottawa, Ont: Atomic Energy of Canada, 2005.
Agency, OECD Nuclear Energy, ed. Regulatory reviews of assessments of deep geologic repositories: Lessons learnt = Évaluation des dépôts géologiques profonds dans un contexte réglementaire : enseignements tirés. Paris: Organisation for Economic Co-operation and Development, 2000.
logement, Ontario Ministère des affaires municipales et du. Les friches contaminées en vedette: Prendre conscience des avantages environnementaux, économiques et communautaires du réaménagement des friches contaminées. Toronto, Ont: Ministère des affaires municipales et du logement, 2000.
National Council on Radiation Protection and Measurements., ed. Approaches to risk management in remediation of radioactively contaminated sites. Bethesda, MD: National Council on Radiation Protection and Measurement, 2004.
Sellers, Kathleen. Fundamentals of hazardous waste site remediation. Boca Raton: Lewis Publishers, 1999.
Russell, Boulding, and United States. Environmental Protection Agency., eds. EPA environmental engineering sourcebook. Chelsea, Mich: Ann Arbor Press, 1996.
Cochran, Thomas B. Making the Russian bomb: From Stalin to Yeltsin. Boulder, Colo: Westview Press, 1995.
Table ronde nationale sur l'environnement et l'économie (Canada), ed. L' état du débat sur l'environnement et l'économie: Les terrains abandonnés au Canada--retour au vert. Ottawa, Ont: Table ronde nationale sur l'environnement et l'économie, 1998.