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Literatura académica sobre el tema "Alliage Pb-Bi [Plomb-Bismuth]"
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Tesis sobre el tema "Alliage Pb-Bi [Plomb-Bismuth]"
Martinelli, Laure. "Mécanisme de corrosion de l' acier T91 par l' eutectique Pb-Bi utilisé comme matériau de cible de spallation : importance pour les réacteurs hybrides." Paris 6, 2005. http://www.theses.fr/2005PA066442.
Texto completoRoy, Marion. "Mécanisme de dissolution des aciers austénitiques dans l'eutectique plomb-bismuth à 500° C." Compiègne, 2012. http://www.theses.fr/2012COMP2054.
Texto completoIn the framework of the future nuclear power plants studies, lead-bismuth eutectic (LBE) is foreseen as a coolant in the primary or the secondary circuit in three nuclear systems. The use of this liquid alloy induces corrosion issues for structural steels. In liquid lead alloys, steels can undergo two corrosion phenomena: dissolution or oxidation depending on the temperature and the dissolved oxygen content in LBE. The goal of this study is to identify the dissolution mechanisms of austenitic steels in LBE at 500 °C. Four Fe-Cr-Ni model austenitic steels, the 316L steel and five other industrial steels were corroded in LBE up to, respectively, 3000, 6000 and 200 h. The dissolution mechanism is identical for all steels: it starts by a preferential dissolution of chromium and nickel. This dissolution leads to the formation of a ferritic corrosion layer penetrated by LBE and containing between 5 and 10 % of chromium and almost no nickel. This study demonstrates that dissolutions of nickel and chromium are linked. Otherwise, the corrosion kinetics is linear whatever the tested austenitic steel. The controlling steps of the austenitic steels’ corrosion rates have been identified. Natural convection in the LBE bath leads to the formation of a diffusion boundary layer at the steel surface. Chromium diffusion in this diffusion boundary layer seems to control the corrosion rates of the model and industrial austenitic steels except the 316L steel. Indeed, the corrosion rate of the 316L steel is controlled by an interfacial reaction which is either the simultaneous dissolution of nickel and chromium in NixCr compounds or the nickel and chromium dissolution catalyzed by the dissolved oxygen in LBE. This study has permitted to highlight the major role of chromium on the corrosion mechanisms and the corrosion rates of austenitic steels: the corrosion rate increases when chromium activity increases. Finally, the impact of the dissolved oxygen and the minor alloying elements content on the corrosion rate is discussed. Assuming chromium dissolution catalysis by dissolved oxygen, some recommendations are proposed on the steel composition and the dissolved oxygen content to fix in the liquid alloy in order to limit the corrosion rates of austenitic steels in LBE
Azzaoui, Mouhsine. "Modélisation des liquides métalliques ternaires pour le calcul des diagrammes d'équilibre à partir des mesures thermodynamiques ciblées : systèmes tests : (Pb, Sn, Sb), (Pb, Sn, Bi), (Pb, Sn, Ca)." Nancy 1, 1995. http://www.theses.fr/1995NAN10032.
Texto completoDiop, Ibra Vilasi Michel. "Contribution à l'étude de la résistance chimique et mécanique des matériaux métalliques, (acier T91 9%Cr1%Mo en masse) en environnements complexes dans les réacteurs nucléaires Corrosion et protection en présence de l'eutectique Plomb-Bismuth liquide ; Etude thermodynamique du système Pb-Bi-Hg-Fe-O /." S. l. : Nancy 1, 2008. http://www.scd.uhp-nancy.fr/docnum/SCD_T_2008_0115_DIOP.pdf.
Texto completoDiop, Ibra. "Contribution à l’étude de la résistance chimique et mécanique des matériaux métalliques, (acier T91 9%Cr1%Mo en masse) en environnements complexes dans les réacteurs nucléaires : Corrosion et protection en présence de l’eutectique Plomb-Bismuth liquide ; Etude thermodynamique du système Pb-Bi-Hg-Fe-O." Thesis, Nancy 1, 2008. http://www.theses.fr/2008NAN10115/document.
Texto completoThe development of sub-critical nuclear reactors (Accelerator Driven System - ADS), intrinsically safe to incinerate nuclear waste by transmutation of long-lived actinides to radionuclides with a shorter existence, requires intense sources of neutrons. These sources are produced by the "ejected" spallation technique, i.e. the interaction of a high energy, high intensity proton beam with a target containing heavy metals. Considering the power of the proton beam transferred to the target (of a few MW), only metals in the liquid form can be cooled in a closed cooling system and resist to nuclear reactor induced by the proton beam. In this context, the MEGAPIE project (MEGawatt PIlot Experiment), which works with a window at the spallation target, is pioneer and opens the way for high-power targets. The choice of the alloy for the MEGAPIE spallation target is a lead-bismuth eutectic, which is efficient for producing neutrons. For the window beam and hot parts, the best choice at present is the T91 steel (1%Mo9%Cr in mass), due to its good irradiation resistance. For cold parts, the 316L steel was chosen. However, the contact of the two alloys (eutectic lead-bismuth and T91 steel) presents some inconveniences that need to be investigated in relation to their physico-chemical properties in the MEGAPIE environment, which motivates this study. The contribution of this work to this subject consisted of : - In a part, the development of coatings designed to improve the chemical and mechanical performances of the T91 steel in contact of the lead-bismuth eutectic liquid alloy, - In another part, the investigation of the thermodynamic properties of the Pb-Bi-(Hg)-Fe-Cr-Al-O system for all phase equilibria within the conditions imposed by the operation of the ADS reactor. The second part of this work is justified by the results, which, for the first time, highlight the role played by the mixed oxide phases in the corrosive interaction between the T91 steel and Pb-Bi eutectic, in a poorly oxygenated environment