Auswahl der wissenschaftlichen Literatur zum Thema „Alliages à base de zirconium“
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Zeitschriftenartikel zum Thema "Alliages à base de zirconium"
Barcelo, F., A. Alamo und J. Bai. „Caractérisation de l ’orientation des hydrures induite par la contrainte dans un alliage base zirconium“. Revue de Métallurgie 90, Nr. 9 (September 1993): 1127. http://dx.doi.org/10.1051/metal/199390091127.
Der volle Inhalt der QuelleArchambault, P., M. Abrudeanu und B. Colleret. „Influence de l'oxydation et de l'état structural sur les propriétés thermo-physiques d'un alliage à base de zirconium“. Journal of Nuclear Materials 200, Nr. 2 (April 1993): 162–68. http://dx.doi.org/10.1016/0022-3115(93)90326-t.
Der volle Inhalt der QuelleMardon, J. P., P. Barberis und P. B. Hoffmann. „Un demi-siècle de développement des alliages de zirconium“. Revue Générale Nucléaire, Nr. 4 (Juli 2008): 38–47. http://dx.doi.org/10.1051/rgn/20084038.
Der volle Inhalt der QuelleSteinmetz, Jean, Michel Vilasi und Bernard Roques. „Oxydation et protection des alliages base niobium“. Le Journal de Physique IV 03, Nr. C9 (Dezember 1993): C9–487—C9–498. http://dx.doi.org/10.1051/jp4:1993952.
Der volle Inhalt der QuelleTricot, Roland. „Le zirconium et ses alliages. Métallurgie et applications au génie nucléaire“. Revue Générale Nucléaire, Nr. 1 (Januar 1990): 8–20. http://dx.doi.org/10.1051/rgn/19901008.
Der volle Inhalt der QuelleToffolon, C., J. C. Brachet, T. Guilbert, D. Hamon, S. Urvoy, C. Servant, D. Charquet, L. Legras und J. P. Mardon. „Vieillissement thermique des alliages de zirconium-niobium en phase α (570 °C)“. Le Journal de Physique IV 11, PR1 (April 2001): Pr1–99—Pr1–108. http://dx.doi.org/10.1051/jp4:2001110.
Der volle Inhalt der QuelleGodlewski, J., und D. Pêcheur. „Compréhension des cinétiques d'oxydation des alliages de zirconium en milieu aqueux lithié“. Le Journal de Physique IV 11, PR1 (April 2001): Pr1–119—Pr1–128. http://dx.doi.org/10.1051/jp4:2001112.
Der volle Inhalt der QuelleThomazet, J., D. Charquet, P. Billot und H. Amanrich. „Comportement à la corrosion des alliages de zirconium hors et sous irradiation“. Revue de Métallurgie 90, Nr. 9 (September 1993): 1086. http://dx.doi.org/10.1051/metal/199390091086.
Der volle Inhalt der QuelleTricot, Roland. „Le zirconium et ses alliages dans l'industrie nucléaire. Métallurgie extractive, élaboration et propriétés“. Revue Générale Nucléaire, Nr. 1 (Januar 1986): 46–54. http://dx.doi.org/10.1051/rgn/19861046.
Der volle Inhalt der QuelleHalley-Demoulin, I., D. Ciosmak und M. Lallemant. „Oxydation des alliages TiZr sous air et sous oxygène II. Rôle de la composition des alliages sur l'évolution cinétique et morphologique du titane au zirconium“. Journal of Alloys and Compounds 204, Nr. 1-2 (Februar 1994): 133–43. http://dx.doi.org/10.1016/0925-8388(94)90082-5.
Der volle Inhalt der QuelleDissertationen zum Thema "Alliages à base de zirconium"
Borroto, Ramírez Alejandro. „Synthesis, structure and properties of zirconium-based binary alloy thin films“. Electronic Thesis or Diss., Université de Lorraine, 2019. http://www.theses.fr/2019LORR0057.
Der volle Inhalt der QuelleIn this thesis, we demonstrate that original nanostructures can be obtained by working around the crystalline-to-amorphous transition in sputter-deposited thin films. In particular, we study two systems, Zr-Mo and Zr-W, in which such transition occurs. By decreasing the Mo content in the Zr-Mo system, a structural transition from a nanocrystalline solid solution of Zr in the bcc lattice of Mo to an amorphous structure can be achieved around 60 at% Mo. The films obtained present high hardness H, low Young's modulus E and, consequently, high H/E ratio compared with bulk Zr and Mo. Furthermore, we demonstrate that a self-separation of the nanocrystalline and the amorphous phases occurs at the composition intermediate to those necessary to form single-phased amorphous and nanocrystalline films. The particular geometry in which the nanocrystalline phase grows in competition with the amorphous phase is exploited to achieve a thickness-controlled surface morphology which allows to tune the film reflectance. A model was developed to describe the kinetics of the competitive growth between the nanocrystalline and the amorphous phases. Furthermore, it allows to construct a thickness-composition phase diagram evidencing that the nanocrystalline/amorphous competitive growth is easily hidden experimentally. Finally, we demonstrate that massive monocrystalline grains with lateral size larger than 1 µm can be obtained by working at low Ar pressure if the composition of the films approaches to the edge of the amorphous transition. Our results suggest that the phenomena reported here for Zr-Mo and Zr-W can be extended to other systems
Lafaye, Paul. „Développement d’outils de modélisation thermodynamique pour la prédiction de l’état métallurgique d’alliages à base zirconium“. Thesis, Paris Est, 2017. http://www.theses.fr/2017PESC1125/document.
Der volle Inhalt der QuelleCurrently, zirconium alloys are used as fuel cladding materials in PWR (Pressurized Water Reactors). The claddings stand in a very corrosive and radiative environnement, and can be submitted to temperature variations. In addition, the claddings will be subjected to mechanical stresses in reactor or accidental conditions. Thus, it appears useful to have a better understanding of phase transformations occurring in these alloys, as a function of temperature and chemical composition variations, but also to forecast the precipitation of fragile phases induced by the addition of alloying elements. At last, the ability to test new alloy compositions may allow to optimize it.The most suitable method for the thermodynamic modeling of multicomponent systems is the Calphad method (CALculation of PHAse Diagrams). The Calphad method is a widely used technique of semi-empirical modelling of phase diagrams. It consists in the description of the Gibbs energies of the different phases by fitting parameters allowing to describe the experimental data.This report details the design of a thermodynamic database considering the five following elements Zr, Cr, Fe, Nb, and Sn. The originality of this database lies in a systematic use of DFT calculations. Indeed, DFT calculations are performed to predict the formation enthalpy of the intermetallic phases appearing in these systems. Moreover, the SQS method (Special Quasirandom Structure) is used to predict the mixing enthalpy of the fcc, bcc and hcp binary solid solutions. Besides, experimental investigations are an important step of this thesis. Since no experimental data were available for the Cr-Fe-Sn, Cr-Nb-Sn, Cr-Sn-Zr and Fe-Nb-Sn ternary systems, new experimental data are provided, within this study, on the isothermal sections of these systems at different temperatures. All these calculated data in addition to the experimental data and the data from literature are used as input data for the Calphad modelling of the twenty binary and ternary systems which are then combined in the new database. A last part is dedicated to comparisons between predictions obtained with our new database and experimental results on industrial quinary alloys and a new concept of claddings
Toffolon-Masclet, Caroline. „Etude metallurgique et calculs de diagrammes de phases des alliages base zirconium du systeme : zr-nb-fe-(o,sn)“. Paris 6, 2000. http://www.theses.fr/2000PA066457.
Der volle Inhalt der QuelleOlier, Patrick. „Alliages à mémoire de forme de base TiNi : influence du mode de fabrication, de la teneur en oxygène et de l'ajout de zirconium ou d'hafnium sur les caractéristiques métallurgiques et les propriétés thermomécaniques /“. Gif-sur-Yvette : Direction de l'information scientifique et technique, CEA Saclay, 1996. http://catalogue.bnf.fr/ark:/12148/cb35851337w.
Der volle Inhalt der QuelleWu, Alexia. „Etude du comportement hors et sous irradiation aux ions d'un gainage combustible REP innovant base zirconium revêtu de chrome“. Thesis, Paris 6, 2017. http://www.theses.fr/2017PA066611/document.
Der volle Inhalt der QuelleIn Light Water Reactors (LWR) under hypothetical accidental conditions such as LOss of Coolant Accident (LOCA), zirconium alloy fuel claddings undergo significant oxidation at high temperatures. To limit this phenomenon, innovative chromium coated nuclear fuel claddings are studied at CEA. However, the integrity under neutron irradiation of such coating for in-service conditions must be preserved..The main objective of this PhD work is to study the behavior under ion irradiation of this new cladding concept. We especially focus on Zr/Cr interface microstructure evolution under irradiation, since the latter controls the adhesion of the coating to the substrate. Ion irradiations were performed to simulate the damage caused by neutrons in LWR. A multi-scale approach is used to characterize the samples before and after irradiation. In particular, Transmission Electron Microscopy (TEM) was used to characterize, at an atomic scale, the microstructure of the Zr/Cr interface. A first type of Zr/Cr interface is observed and shows the presence of nanometric phases of Zr(Fe,Cr)2 C14 and ZrCr2 C15 types. After irradiation, the C14 phase seems to be stabilized over the C15 phase, by segregation of iron at the interface. For a second interface, obtained using different deposition conditions, only C15 phase is observed. Under in-situ TEM irradiation, dissolution of the C15 phase is observed. Whatever the Zr/Cr interface type, preservation of the continuity of crystallographic planes before and after irradiation throughout the interface is demonstrated and thus induces a good adhesion of the coating to the substrate
Skocic, Milan. „Etude (photo)-électrochimique en réacteur simulé du phénomène de shadow corrosion des alliages de zirconium“. Thesis, Université Grenoble Alpes (ComUE), 2016. http://www.theses.fr/2016GREAI015/document.
Der volle Inhalt der QuelleConventional electrochemical methods as well as photoelectrochemical characterisations (PEC), performedex-situ et in-situ, were used to study the Shadow corrosion phenomenon, considered as a galvanic corrosion between Zr-based and Ni-based alloys. The Shadow corrosion is influenced by the chemical environment and the irradiation of these alloys. An electrochemical cell , simulating the conditions of a boiling water reactor (BWR), allowing the illumination of the samples with UV--Visible as well as monitoring the water chemistry was designed, developed and validated. The cell allowed, for the first time, recording of emph{in-situ} photocurrent energy spectra on a Zr-based alloy in simulated BWR environment. Furthermore, the obtained experimental results pointed out that the metallic cation impurities played an important role in the activation mechanism of the galvanic coupling, thus potentially in the activation mechanism of the Shadow corrosion phenomenon, whereas the presence oxygen and/or hydrogen peroxide did not induce significant differences in terms of electrochemical behavior of the samples. It was also shown that the illumination of the sample with UV--visible light, which significantly amplified the galvanic current, is an important parameter of the Shadow corrosion phenomenon
Pecheur, Dominique. „Evolution des précipités à base de zirconium lors de l'oxydation et de l'irradiation d'alliages de zirconium : impact sur la cinétique d'oxydation d'alliages de zirconium“. Grenoble INPG, 1993. http://www.theses.fr/1993INPG0013.
Der volle Inhalt der QuelleWu, Alexia. „Etude du comportement hors et sous irradiation aux ions d'un gainage combustible REP innovant base zirconium revêtu de chrome“. Electronic Thesis or Diss., Paris 6, 2017. https://accesdistant.sorbonne-universite.fr/login?url=https://theses-intra.sorbonne-universite.fr/2017PA066611.pdf.
Der volle Inhalt der QuelleIn Light Water Reactors (LWR) under hypothetical accidental conditions such as LOss of Coolant Accident (LOCA), zirconium alloy fuel claddings undergo significant oxidation at high temperatures. To limit this phenomenon, innovative chromium coated nuclear fuel claddings are studied at CEA. However, the integrity under neutron irradiation of such coating for in-service conditions must be preserved..The main objective of this PhD work is to study the behavior under ion irradiation of this new cladding concept. We especially focus on Zr/Cr interface microstructure evolution under irradiation, since the latter controls the adhesion of the coating to the substrate. Ion irradiations were performed to simulate the damage caused by neutrons in LWR. A multi-scale approach is used to characterize the samples before and after irradiation. In particular, Transmission Electron Microscopy (TEM) was used to characterize, at an atomic scale, the microstructure of the Zr/Cr interface. A first type of Zr/Cr interface is observed and shows the presence of nanometric phases of Zr(Fe,Cr)2 C14 and ZrCr2 C15 types. After irradiation, the C14 phase seems to be stabilized over the C15 phase, by segregation of iron at the interface. For a second interface, obtained using different deposition conditions, only C15 phase is observed. Under in-situ TEM irradiation, dissolution of the C15 phase is observed. Whatever the Zr/Cr interface type, preservation of the continuity of crystallographic planes before and after irradiation throughout the interface is demonstrated and thus induces a good adhesion of the coating to the substrate
Tcheliebou, Frederic. „Etude des alliages d'oxydes à base de ZrO2 obtenus par évaporation thermique réactive au double canon à électrons“. Montpellier 2, 1995. http://www.theses.fr/1995MON20037.
Der volle Inhalt der QuelleVERMOYAL, JEAN-JEROME. „Contribution a l'identification des processus cinetiquement limitants de l'oxydation des alliages de zirconium caracterisation en electrochimie des solides des films d'oxyde formes a haute temperature“. Université Joseph Fourier (Grenoble), 2000. http://www.theses.fr/2000GRE10077.
Der volle Inhalt der QuelleBücher zum Thema "Alliages à base de zirconium"
P, Sabol George, Bradley E. R und International Symposium on Zirconium in the Nuclear Industry (11th : 1995 : Garmisch-Partenkirchen, Germany), Hrsg. Zirconium in the nuclear industry: Eleventh international symposium. West Conshohocken, PA: ASTM, 1996.
Den vollen Inhalt der Quelle findenCasting defects handbook: Copper & copper-base alloys. Schaumburg, IL: American Foundry Society, 2010.
Den vollen Inhalt der Quelle findenTuthill, Arthur H. Corrosion behaviour of stainless steel, nickel base alloy and titanium weldments in chlorination and chlorine dioxide bleaching. Toronto, Ont: Nickel Development Institute, 1992.
Den vollen Inhalt der Quelle finden(Editor), E. Ross Bradley, und George P. Sabol (Editor), Hrsg. Zirconium in the Nuclear Industry (Astm Special Technical Publication// Stp). American Society for Testing & Materials, 1997.
Den vollen Inhalt der Quelle findenGarde, Anand M. Zirconium in the Nuclear Industry: Tenth International Symposium (Astm Special Technical Publication// Stp). American Society for Testing & Materials, 1995.
Den vollen Inhalt der Quelle findenCastings: Stainless steel and nickel-base. Toronto, Ont: Nickel Institute, 2000.
Den vollen Inhalt der Quelle findenBuchteile zum Thema "Alliages à base de zirconium"
Choudhuri, Gargi, Sibasis Chakraborty, B. K. Shah, D. Srivastava und G. K. Dey. „Phase Field Modeling of Microstructure Evolution in Zirconium Base Alloys“. In Zirconium in the Nuclear Industry: 17th Volume, 95–117. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2014. http://dx.doi.org/10.1520/stp154320130045.
Der volle Inhalt der QuelleDoriot, Sylvie, Bénédicte Verhaeghe, Annie Soniak-Defresne, Philippe Bossis, Didier Gilbon, Valérie Chabretou, Jean-Paul Mardon, Marc Ton-That und Antoine Ambard. „Microstructural Evolution of Q12TMAlloy Irradiated in PWRs and Comparison with Other Zr Base Alloys“. In Zirconium in the Nuclear Industry: 18th International Symposium, 823–56. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2018. http://dx.doi.org/10.1520/stp159720160061.
Der volle Inhalt der QuelleMarkelov, Vladimir A., Andrey G. Malgin, Nadezhda K. Filatova, Vladimir V. Novikov, Alexandr Yu Shevyakov, Anatoly Yu Gusev, Ivan A. Shelepov et al. „Fabrication of E110 Alloy Fuel Rod Claddings from Electrolytic Zirconium Base with Removing Fluorine Impurity for Providing Resistance to Breakaway Oxidation in High-Temperature Steam“. In Zirconium in the Nuclear Industry: 19th International Symposium, 123–48. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2021. http://dx.doi.org/10.1520/stp162220190022.
Der volle Inhalt der QuelleLegry, G. Pinard. „Alliages de titane et alliages de zirconium“. In Corrosion localisée, 637–50. EDP Sciences, 1994. http://dx.doi.org/10.1051/978-2-7598-0238-8.c030.
Der volle Inhalt der QuelleHoulle, P. „Alliages base nickel et base cobalt“. In Corrosion localisée, 621–36. EDP Sciences, 1994. http://dx.doi.org/10.1051/978-2-7598-0238-8.c029.
Der volle Inhalt der QuelleCOLIN, Christophe. „Les microstructures des matériaux métalliques issus de fabrication additive“. In La fabrication additive des alliages métalliques 2, 5–103. ISTE Group, 2022. http://dx.doi.org/10.51926/iste.9055.ch1.
Der volle Inhalt der QuellePEYRE, Patrice. „Les procédés de fabrication additive métallique“. In La fabrication additive des alliages métalliques 1, 5–102. ISTE Group, 2022. http://dx.doi.org/10.51926/iste.9054.ch1.
Der volle Inhalt der QuelleDEBEAUFORT, Frédéric. „Emballages métalliques“. In Matériaux et procédés d’emballage pour les industries alimentaires, cosmétiques et pharmaceutiques, 95–126. ISTE Group, 2022. http://dx.doi.org/10.51926/iste.9039.ch4.
Der volle Inhalt der QuelleSegawa, K., N. Kihara und S. Nakata. „3.11 Preparation and Catalytic Properties of Composite Zirconium Phosphonates“. In Acid-Base Catalysis II, Proceedings of the International Symposium on Acid-Base Catalysis II, 303–10. Elsevier, 1994. http://dx.doi.org/10.1016/s0167-2991(08)61837-6.
Der volle Inhalt der QuelleMatsuhashi, Hiromi, Kazuyoshi Kato und Kazushi Arata. „3.1 Synthesis of Solid Superacid of Borate Supported on Zirconium Oxides“. In Acid-Base Catalysis II, Proceedings of the International Symposium on Acid-Base Catalysis II, 251–56. Elsevier, 1994. http://dx.doi.org/10.1016/s0167-2991(08)61827-3.
Der volle Inhalt der QuelleKonferenzberichte zum Thema "Alliages à base de zirconium"
Feaugas, X., und E. Conforto. „Influence de l'hydrogène sur les mécanismes de déformation et d'endommagement des alliages de titane et de zirconium“. In PlastOx 2007 - Mécanismes et Mécanique des Interactions Plasticité - Environnement. Les Ulis, France: EDP Sciences, 2009. http://dx.doi.org/10.1051/ptox/2009012.
Der volle Inhalt der QuelleSonoya, K., C. J. Li und S. Tobe. „Thermal Fatigue Characteristics of the Membrane Formed by the Plasma Spraying of ZrO2-NiCrAIY“. In ITSC 1999, herausgegeben von E. Lugscheider und P. A. Kammer. Verlag für Schweißen und verwandte Verfahren DVS-Verlag GmbH, 1999. http://dx.doi.org/10.31399/asm.cp.itsc1999p0571.
Der volle Inhalt der QuelleSrivastava, D., K. V. Mani Krishna, S. Neogy, G. K. Dey, I. Samajdar und S. Banerjee. „Evolution of Microstructure, Microtexture and Texture in Dilute Zirconium Based Structural Components of Pressurised Heavy Water Reactors“. In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75274.
Der volle Inhalt der QuelleMohsin, Qabas Nawfal, und Asmaa Shawky Khaleel. „Mechanical and thermal properties of poly (methyl methacrylate) supported with Zirconium oxide as a base material for dentures“. In PROCEEDINGS OF THE III INTERNATIONAL CONFERENCE ON ADVANCED TECHNOLOGIES IN MATERIALS SCIENCE, MECHANICAL AND AUTOMATION ENGINEERING: MIP: Engineering-III – 2021. AIP Publishing, 2021. http://dx.doi.org/10.1063/5.0066222.
Der volle Inhalt der QuelleZeng, Qifeng, Libing Zhu, Gaihuan Yuan, Lian Wang, Guocheng Sun und Junqiang Lu. „Microstructure and Properties of New Zirconium Alloys for CAP1400 Fuel Assembly“. In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66951.
Der volle Inhalt der QuelleHasebe, Yusaku, Eiji Maeda und Koichi Takasawa. „Effects of Trace Elements on Creep Properties of Nickel-Iron Base Superalloy“. In AM-EPRI 2016, herausgegeben von J. Parker, J. Shingledecker und J. Siefert. ASM International, 2016. http://dx.doi.org/10.31399/asm.cp.am-epri-2016p0181.
Der volle Inhalt der QuelleChaput, Heather, Brian W. Leitch und Don R. Metzger. „Effect of Creep Relaxation on the Delayed Hydride Cracking Behavior of Irradiated Zirconium 2.5%Wt Niobium Pressure Tube Material“. In ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference. ASMEDC, 2006. http://dx.doi.org/10.1115/pvp2006-icpvt-11-93392.
Der volle Inhalt der QuelleNarayanan, Badri K., Lisa McFadden, M. J. Mills und Marie A. Quintana. „Characterization of Weld Metal Deposited With a Self Shielded Flux Cored Electrode for Pipeline Girth Welds and Offshore Structures“. In 2010 8th International Pipeline Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/ipc2010-31406.
Der volle Inhalt der QuelleOzaltun, Hakan, Hee Seok Roh und Walid Mohamed. „Overview of the Base Model for the Parametric Sensitivity Studies Specific to Performance Assessments of U-Mo Fuel Plates“. In ASME 2022 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/imece2022-93718.
Der volle Inhalt der QuelleRashid, Joseph Y. R., Timothy Hardin, Mark M. Rashid, Robert S. Dunham und Keith Kubischta. „Damage-Based Modeling and Analysis of Reactor Vessels With Numerous Base Metal Ultrasonic Indications“. In ASME 2013 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/pvp2013-97116.
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