Bibliografie tematiche / Alliages à base de zirconium

Letteratura scientifica selezionata sul tema "Alliages à base de zirconium"

Autore: Grafiati

Pubblicato: 8 giugno 2024

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Articoli di riviste sul tema "Alliages à base de zirconium":

Barcelo, F., A. Alamo e J. Bai. "Caractérisation de l ’orientation des hydrures induite par la contrainte dans un alliage base zirconium". Revue de Métallurgie 90, n. 9 (settembre 1993): 1127. http://dx.doi.org/10.1051/metal/199390091127.

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Archambault, P., M. Abrudeanu e 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, n. 2 (aprile 1993): 162–68. http://dx.doi.org/10.1016/0022-3115(93)90326-t.

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Mardon, J. P., P. Barberis e P. B. Hoffmann. "Un demi-siècle de développement des alliages de zirconium". Revue Générale Nucléaire, n. 4 (luglio 2008): 38–47. http://dx.doi.org/10.1051/rgn/20084038.

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Steinmetz, Jean, Michel Vilasi e Bernard Roques. "Oxydation et protection des alliages base niobium". Le Journal de Physique IV 03, n. C9 (dicembre 1993): C9–487—C9–498. http://dx.doi.org/10.1051/jp4:1993952.

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Tricot, Roland. "Le zirconium et ses alliages. Métallurgie et applications au génie nucléaire". Revue Générale Nucléaire, n. 1 (gennaio 1990): 8–20. http://dx.doi.org/10.1051/rgn/19901008.

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Toffolon, C., J. C. Brachet, T. Guilbert, D. Hamon, S. Urvoy, C. Servant, D. Charquet, L. Legras e J. P. Mardon. "Vieillissement thermique des alliages de zirconium-niobium en phase α (570 °C)". Le Journal de Physique IV 11, PR1 (aprile 2001): Pr1–99—Pr1–108. http://dx.doi.org/10.1051/jp4:2001110.

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Godlewski, J., e D. Pêcheur. "Compréhension des cinétiques d'oxydation des alliages de zirconium en milieu aqueux lithié". Le Journal de Physique IV 11, PR1 (aprile 2001): Pr1–119—Pr1–128. http://dx.doi.org/10.1051/jp4:2001112.

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Thomazet, J., D. Charquet, P. Billot e H. Amanrich. "Comportement à la corrosion des alliages de zirconium hors et sous irradiation". Revue de Métallurgie 90, n. 9 (settembre 1993): 1086. http://dx.doi.org/10.1051/metal/199390091086.

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Tricot, Roland. "Le zirconium et ses alliages dans l'industrie nucléaire. Métallurgie extractive, élaboration et propriétés". Revue Générale Nucléaire, n. 1 (gennaio 1986): 46–54. http://dx.doi.org/10.1051/rgn/19861046.

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Halley-Demoulin, I., D. Ciosmak e 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, n. 1-2 (febbraio 1994): 133–43. http://dx.doi.org/10.1016/0925-8388(94)90082-5.

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Più fonti

Tesi sul tema "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.

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Dans cette thèse, nous démontrons que des nanostructures originales peuvent être obtenues en travaillant autour de la transition cristallin/amorphe dans des films minces déposés par pulvérisation cathodique. En particulier, nous étudions deux systèmes, Zr-Mo et Zr-W, dans lesquels une telle transition se produit. Dans ce système, lorsque la teneur en Mo est réduite, une transition structurale d’une solution solide nanocristalline de Zr dans le réseau bbc de Mo à une structure amorphe peut être obtenue autour de 60 at % de Mo. Les films obtenus présentent une dureté H élevée, un faible module de Young E et, par conséquent, un ratio H/E élevé par rapport à celui de Zr et Mo. Par ailleurs, nous démontrons qu'une auto-séparation des phases nanocristalline et amorphe se produit à une composition spécifique. La géométrie particulière dans laquelle la phase nanocristalline se développe en concurrence avec la phase amorphe est exploitée pour contrôler la morphologie de surface et, par conséquence, la réflectance par l’intermédiaire de l’épaisseur. Un modèle a été développé pour décrire la cinétique de la croissance compétitive entre les phases nanocristalline et amorphe. De plus, cela permet de construire un diagramme de phase épaisseur-composition qui montre que la croissance compétitive nanocristalline/amorphe est facilement dissimulée expérimentalement. Finalement, nous démontrons que des grains monocristallins massifs de taille latérale supérieure à 1 µm peuvent être obtenus en travaillant à basse pression d’Ar si la composition des films se rapproche du bord de la transition amorphe. Nos résultats suggèrent que les phénomènes observés pour les systèmes Zr-Mo et Zr-W peuvent être étendus à d'autres systèmes
In 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.

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Les alliages de zirconium sont utilisés comme matériaux de gainage des combustibles nucléaires dans les réacteurs à eau pressurisée. Ces gaines sont utilisées dans un milieu extrêmement radiatif et corrosif, elles peuvent dans certains cas être le siège de fortes variations de température et doivent répondre à des sollicitations mécaniques importantes, que ce soit en conditions de service ou accidentelles. Dans un tel contexte, il est intéressant de pouvoir prédire les transformations de phases ayant lieu au sein de la gaine en fonction des variations de température et de composition chimique, la précipitation de phases fragiles induites par la présence des éléments d’alliages, mais aussi de tester de nouvelles compositions d’alliages afin de l’optimiser.La méthode la plus adaptée pour la modélisation thermodynamique de systèmes multiconstitués est la méthode Calphad (CALculation of PHAse Diagrams). Il s’agit d’une méthode semi-empirique, consistant à modéliser les enthalpies libres des différentes phases constitutives d’un système par ajustement de certains paramètres, dans le but de reproduire les données expérimentales.Ce mémoire détaille la construction d’une base de données thermodynamiques du système quinaire Cr-Fe-Nb-Sn-Zr selon la méthode Calphad. L’originalité de notre démarche est liée à l’utilisation des calculs DFT de manière systématique et massive. Il s’agit en particulier de calculer par DFT les enthalpies de formation de tous les end-members des phases intermétalliques constitutives du système quinaire. De plus, des calculs sur des mailles « quasi aléatoires » (SQS) sont également effectués de manière systématique afin de déterminer les enthalpies de mélange des solutions solides binaires en structure fcc, bcc et hcp. En outre, une étape importante de ce travail consiste à compléter les données expérimentales de la littérature par de nouvelles mesures sur des systèmes choisis. En particulier, nous nous sommes employés à décrire quelques équilibres de phases des systèmes ternaires Cr-Nb-Sn, Cr-Fe-Sn, Cr-Sn-Zr et Fe-Nb-Sn qui n’avaient jamais été déterminés expérimentalement. Nous avons ensuite utilisé ces calculs et ces nouvelles données expérimentales en complément de données de la littérature comme données d’entrée pour la modélisation thermodynamique des vingt sous-systèmes binaires et ternaires du système quinaire considéré. Enfin, le pouvoir prédictif de notre base de données a pu être vérifié en confrontant ces prédictions à des données expérimentales relatives à des alliages quinaires industriels ou à de nouveaux concepts de gaines
Currently, 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.

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Les alliages base zirconium sont utilises pour les assemblages combustibles des reacteurs a eau pressurisee (r. E. P. ), notamment en raison de leur transparence aux neutrons, de leur resistance a la corrosion et de leurs bonnes proprietes mecaniques. La volonte de prolonger le temps de sejour en reacteur des assemblages combustibles a conduit les industriels (framatome/cezus) a etudier et a optimiser de nouvelles nuances d'alliages parmi lesquelles l'alliage m5 (zr-1%nb) qui apparait aujourd'hui le plus prometteur. Sachant que le comportement du materiau en conditions de service, depend fortement de sa microstructure (nature et repartition des phases precipitees), une etude metallurgique de base des alliages base zirconium du systeme zr-nb-fe (o-sn) a donc ete mise en uvre afin de cerner l'impact des variabilites de composition chimique des principaux elements d'addition et des traitements thermiques sur les microstructures resultantes. Ce travail a consiste en une double demarche calculs thermodynamiques / experiences visant a creer une base de donnees thermodynamiques des alliages de zr. Afin de modeliser le systeme zr-nb-fe-(sn-o), il a ete necessaire de decrire les systemes binaires le constituant, a partir des donnees disponibles dans la litterature. Les diagrammes de phases binaires nb-sn et fe-nb ont, quant a eux, fait l'objet d'une modelisation thermodynamique. Les etudes experimentales ont notamment permis de quantifier l'influence de variabilites nb et o sur l'evolution des temperatures de transus /, en bon accord avec des calculs thermodynamiques realises a partir de la base de donnees developpee. Compte tenu de la faible diffusivite thermique du nb dans la matrice du zirconium (t<600\c), il est apparu necessaire de quantifier la cinetique de precipitation des phases nb et intermetalliques d'equilibre. Nous avons notamment montre que cette cinetique dependait de la microstructure de depart (presence ou non de phases metastables zr). Enfin, la structure cristallographique, la stoechiometrie et le domaine d'existence en temperature des phases intermetalliques zr-nb-fe ont ete etudies a l'aide de differentes techniques experimentales complementaires, telles que la diffraction electronique, la diffraction de r. X. , la calorimetrie et la diffraction de neutrons en temperature. Ces differentes donnees experimentales, plus particulierement les donnees obtenues sur les phases intermetalliques ternaires, ont permis de proposer une premiere modelisation thermodynamique du diagramme pseudo-ternaire zr-nb-fe (o1200ppm).

Olier, 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.

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Wu, 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.

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Dans les Réacteurs à Eau Pressurisée (REP), en conditions hypothétiques accidentelles d'Accident de Perte de Réfrigérant Primaire, les gaines de combustible en alliage de zirconium subissent une oxydation importante à haute température. Pour ralentir ce phénomène, le CEA développe et étudie des gaines innovantes revêtues de chrome. Cependant, l'intégrité du revêtement doit être maintenue en service et notamment sous irradiation aux neutrons. L'objectif principal de la thèse est d'étudier le comportement sous irradiation de ce concept de gainage. On s'intéresse en particulier à la microstructure de l'interface Zr/Cr avant et après irradiation puisque cette dernière régit l'adhérence du dépôt au substrat. Des irradiations aux ions ont été effectuées afin de simuler le dommage causé par les neutrons dans un REP. Une approche multi-échelle est utilisée pour caractériser les échantillons avant et après irradiation. En particulier, la Microscopie Electronique en Transmission (MET) a permis de caractériser finement la microstructure de l'interface Zr/Cr. Un premier type d'interface Zr/Cr est observé et montre la présence de phases nanométriques de types Zr(Fe,Cr)2 C14 et ZrCr2 C15. Après irradiation, la phase C14 serait stabilisée, au détriment de la phase C15, par ségrégation du fer à l'interface. Pour une seconde interface, obtenue dans des conditions de dépôt différentes, seule la phase C15 est observée. Sous irradiation in-situ au MET, une dissolution de cette phase est constatée. Dans tous les cas, la conservation des continuités de plans cristallographiques à travers l'interface avant et après irradiation permet de conclure à une bonne adhérence du revêtement au substrat
In 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.

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Des méthodes électrochimiques classiques, et des caractérisations photoélectrochimiques (PEC), utiliséesex-situ et in-situ, ont permis d’étudier le phénomène de Shadow Corrosion, considéré ici comme une corrosion galvanique entre des alliages de zirconium et de nickel, corrosion influencée par l’environnement chimique et l’irradiation de ces alliages. Une cellule électrochimique simulant les conditions d’un réacteur à eau bouillante (REB), permettant l’illumination UV--Visible des échantillons et le contrôle de la chimie de l’eau, a été conçue, développée et validée. Cette cellule a permis de mesurer pour la première fois des spectres en énergie de photocourant d’un alliage de zirconium, in-situ en milieu REB simulé. Par ailleurs, les résultats expérimentaux obtenus tendent à montrer que les impuretés de type cations métalliques jouent un rôle important dans le mécanisme d’activation du couplage galvanique, donc potentiellement dans le mécanisme d’activation du phénomène de Shadow Corrosion, alors que la présence d’oxygène et/ou de peroxyde d’hydrogène n’induit pas de différences significatives du comportement électrochimique des échantillons. Il est montré également que l’illumination UV--Visible des échantillons, qui amplifie notablement les courants de couplage, est un paramètre important du phénomène de Shadow Corrosion
Conventional 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.

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Le zircaloy-4, materiau de gainage des crayons combustibles utilise dans les rep francais, presente une vitesse d'oxydation plus elevee en reacteur qu'en autoclave. Il est par ailleurs etabli que la vitesse d'oxydation depend de la nature et de la repartition des precipites dans l'alliage. Or, ces conditions evoluent justement sous irradiation: en particulier les precipites s'amorphisent. Dans ce travail, nous etudions le role des precipites sur le processus d'oxydation des alliages de zirconium et l'impact de l'irradiation, notamment celui de l'amorphisation des precipites, sur cette oxydation. Le mode d'incorporation dans la couche d'oxyde, des precipites de reference et des precipites amorphises par irradiation ionique, est caracterise par microscopie electronique a transmission et par analyse edx. Les evolutions de composition chimique et de structure, qu'ils subissent au cours de leur oxydation, sont analysees et leurs consequences sur la cinetique d'oxydation sont discutees. A quelques centaines de nanometres de l'interface metal-oxyde, la remise en solution partielle du fer dans la zircone formee et l'augmentation de volume des precipites, dues a leur oxydation, pourraient retarder la destabilisation de la zircone quadratique et prolonger la formation d'une couche d'oxyde dense protectrice au-dela des premiers stades de l'oxydation. Ainsi, la transition cinetique des alliages de zirconium serait retardee et leur vitesse d'oxydation ralentie. Par ailleurs, les precipites amorphises par irradiation ionique et ceux de reference presentent dans la couche d'oxyde des evolutions semblables. L'amorphisation des precipites ne semble donc pas etre en mesure de modifier la cinetique de croissance de l'oxyde. Cependant, on constate experimentalement que la vitesse d'oxydation des materiaux irradies aux ions est plus elevee que celle des materiaux de reference. L'origine d'un tel effet reste toutefois mal comprise. Enfin, les premiers resultats des tests d'oxydation realises en autoclave blinde, sur des troncons de gaine de crayons combustibles irradies aux neutrons, sont presentes et commentes

Wu, 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.

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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.

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Ce travail porte sur l'etude de l'influence de la concentration de l'oxyde dopant sur les couches minces de zro2 stabilisees mgo, ceo2 et gd2o3 en vue de leur application sur les capteurs de temperature et la passivation des semiconducteurs. Les depots sont obtenus par evaporation thermique reactive au double canon a electron dans une atmosphere d'oxygene. Des etudes morphologiques, microstructurelles, electriques et optiques y ont ete faites. Les couches obtenues sont polycristallines et presentent une microstructure fine. Les contraintes thermiques et residuelles sont en compression ou en tension selon la nature et la concentration de l'oxyde dopant dans la matrice de zro2. Une optimisation des constantes dielectriques est observee pour les certaines concentrations de dopant. L'indice de refraction est assez elevee et depend fortement de la porosite des couches. La zircone ainsi stabilisee a ete utilisee pour la protection des surfaces internes et externes des buses de thermocouples en ir-40% rh. Lors des essais, elle a supporte un choc thermique a 1500c pendant 15 mn. D'autres applications telles les miroirs lasers en optique, la protection contre l'abrasion et la corrosion des dispositifs sont envisageables a partir des proprietes physiques des depots etudies

VERMOYAL, 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.

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Les mecanismes de corrosion des alliages de zr, utilises comme tubes de gainage du combustible nucleaire, ne sont actuellement pas totalement elucides du fait, notamment, de la complexite des materiaux et de l'environnement de corrosion. La cinetique est generalement consideree comme pilotee par la diffusion des ions oxydes a travers une couche barriere dont les caracteristiques evoluent dans le temps. Cependant, certaines constatations experimentales, comme l'effet du couplage sur la croissance du film d'oxyde, motivent fortement l'introduction de processus electrochimiques dans la description des etapes-cles de l'oxydation. La finalite de la presente etude est de contribuer a lever l'indetermination quant a la nature des etapes cinetiquement limitantes de la corrosion de deux alliages de zirconium, le zircaloy-4 (zy-4) et le zr-nb(1%)o(0,13%). La complementarite des caracterisations in situ de l'oxydation sous air sec a 500\c sur des criteres cinetiques (analyses thermogravimetriques), electrochimiques (spectroscopie d'impedance) et microstructuraux (meb), et de l'influence de la polarisation des gaines sur l'oxydation et l'hydruration en milieu rep a 360\c, a permis de mettre en evidence le contraste entre les deux alliages en termes de processus limitants. Alors que les resultats obtenus pour le zy-4 satisfont a l'hypothese de la diffusion de l'oxygene a travers le film de zircone, l'acceleration de l'oxydation du zr-nb(1%)o(0,13%) sous polarisation anodique en milieu liquide, et en presence d'un metal noble catalyseur de la reduction de l'oxygene en milieu gazeux, est incompatible avec un tel mecanisme. Les essais menes en milieu rep peuvent s'expliquer a la fois par un mecanisme pilote par la conductivite electronique de l'oxyde mais egalement par un controle de type interfacial. En complement, les caracterisations electriques des films de zircone formes en eau et etudies en environnement gazeux confirment la difference entre les deux alliages. La prise en compte du caractere mixte (diffusion-interface) de l'oxydation du zr-nb(1%)o(0,13%) a conduit a un essai de modelisation base sur une approche propre a la cinetique heterogene ainsi qu'a une description electrochimique.

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Libri sul tema "Alliages à base de zirconium":

P, Sabol George, Bradley E. R e International Symposium on Zirconium in the Nuclear Industry (11th : 1995 : Garmisch-Partenkirchen, Germany), a cura di. Zirconium in the nuclear industry: Eleventh international symposium. West Conshohocken, PA: ASTM, 1996.

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Neff, David. Casting defects handbook: Copper & copper-base alloys. Schaumburg, IL: American Foundry Society, 2010.

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Tuthill, 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.

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(Editor), E. Ross Bradley, e George P. Sabol (Editor), a cura di. Zirconium in the Nuclear Industry (Astm Special Technical Publication// Stp). American Society for Testing & Materials, 1997.

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Garde, Anand M. Zirconium in the Nuclear Industry: Tenth International Symposium (Astm Special Technical Publication// Stp). American Society for Testing & Materials, 1995.

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Castings: Stainless steel and nickel-base. Toronto, Ont: Nickel Institute, 2000.

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Capitoli di libri sul tema "Alliages à base de zirconium":

Choudhuri, Gargi, Sibasis Chakraborty, B. K. Shah, D. Srivastava e 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.

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Doriot, Sylvie, Bénédicte Verhaeghe, Annie Soniak-Defresne, Philippe Bossis, Didier Gilbon, Valérie Chabretou, Jean-Paul Mardon, Marc Ton-That e 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.

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Markelov, 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.

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Legry, 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.

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Houlle, 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.

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COLIN, 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.

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Abstract (sommario):

Ce chapitre traite des microstructures induites par FA en se concentrant sur les quatre principales familles d’alliages métalliques : aciers, alliages base titane, base nickel ou base aluminium, et en commençant par des notions de base sur la solidification. L’origine des microstructures et leur spécificité en fonction des procédés d’élaboration y sont présentées.

PEYRE, 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.

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Abstract (sommario):

Ce chapitre présente les quatre grands procédés de fabrication additive métallique actuels (L-PBF, DED-LMD, E-PBF, DED-WAAM) et trois procédés alternatifs en cours de maturation. Y sont décrits: les principes de base et les paramètres clés de chaque procédé, les types d’application visés, et certains éléments sur les propriétés des matériaux fabriqués.

DEBEAUFORT, 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.

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Abstract (sommario):

Ce chapitre décrit les différents métaux et alliages utilisés pour fabriquer des matériaux d’emballage, et leur mise en forme. Une attention particulière est portée sur la fabrication des boites de conserves et cannettes de boissons à base de fer ou d’aluminium, dont l’usage dépend beaucoup de la qualité des soudures, des sertis et des revêtements intérieurs et extérieurs.

Segawa, K., N. Kihara e 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.

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Matsuhashi, Hiromi, Kazuyoshi Kato e 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.

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Atti di convegni sul tema "Alliages à base de zirconium":

Feaugas, X., e 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.

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Sonoya, K., C. J. Li e S. Tobe. "Thermal Fatigue Characteristics of the Membrane Formed by the Plasma Spraying of ZrO2-NiCrAIY". In ITSC 1999, a cura di E. Lugscheider e P. A. Kammer. Verlag für Schweißen und verwandte Verfahren DVS-Verlag GmbH, 1999. http://dx.doi.org/10.31399/asm.cp.itsc1999p0571.

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Abstract This paper focuses on the mechanism responsible for crack expansion and contraction: the behavior of cracks in the ceramic bed of zirconium dioxide membranes formed by plasma spraying, and the thermal stresses caused by differences in thermal expansion factors between the base material and sprayed bed, under a thermally cyclic environment. The test sample was prepared by spraying NiCrAlY on a stainless-steel base material to form a substrate membrane, then covering it with sprayed 8YSZ (zirconium dioxide-type ceramic). To clarify the self-recoverability of fatigue cracks caused during the thermal cycle, membrane cracking and crack expansion/contraction is studied. Paper includes a German-language abstract.

Srivastava, D., K. V. Mani Krishna, S. Neogy, G. K. Dey, I. Samajdar e 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.

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Microstructure and texture of Zr alloys plays a significant role in deciding the material properties and its performance in nuclear reactor. In order to understand the development of microstructure, it is important to know the phase transformations mechanism in these alloys. Dilute Zr-Nb alloys exhibit a range of diffusional, diffusion less and hybrid phase transformations which includes martensitic omega and hydride transformation. With these points in view detail studies on the physical metallurgy aspects of the binary, ternary and quaternary Zirconium base alloys has been carried out in this study. Electron Diffraction and X-ray diffraction techniques have been used to determine the phases, defects and their crystallographic features. Hydriding is most important corrosion problem in the Zirconium cladding alloys. The mechanism of hydride phase transformation and their crystallographic and microstructural aspects has been presented in detail in some Zirconium alloys. Zirconium alloys being crystallographically asymmetric it shows deformation and annealing texture. Result of the studies on bulk and micro texture in some zirconium alloys and some micro-textural aspects on hydride formation is presented in this paper.

Mohsin, Qabas Nawfal, e 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.

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Zeng, Qifeng, Libing Zhu, Gaihuan Yuan, Lian Wang, Guocheng Sun e 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.

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Two Zr-Sn-Nb alloys with minor Germanium or silicon additions were prepared by traditional manufacturing process to meet the design requirements. Transmission electron microscope (TEM) and scanning electron microscope (SEM) were utilized to characterize the detail microstructure of base alloys. Corrosion resistance was examined by the weight gain in static autoclave with different water chemistry environments. The mechanical properties at room temperature and elevated temperature were evaluated by conventional tensile testing. Thermal creep resistance was evaluated by an internally-pressurized creep test at 385 °C with hoop stresses of about 108 MPa and 150 MPa (during 24 h). It was found that SZA-6 and SZA-4 alloys consisted of partially recrystallized grain structures with uniformly distributed fine second phase particles (SPPs) located within grain interior and at grain boundaries. Both SZA-4 and SZA-6 alloys exhibited excellent corrosion resistance in two water chemistry conditions. The corrosion resistance of SZA-6 was better than the reference commercial alloy, and SZA-4 was slightly better than SZA-6. The mechanical properties of two new zirconium alloys were comparable, and both of them can meet the design criterion. Moreover, the thermal creep resistance of SZA-4 and SZA-6 alloys was equivalent to existing commercial alloy. Considering the outstanding corrosion resistance, satisfied mechanical properties and thermal creep resistance, SZA-4 and SZA-6 alloys were suggested as promising alloys used for CAP1400 fuel assembly in the future.

Hasebe, Yusaku, Eiji Maeda e Koichi Takasawa. "Effects of Trace Elements on Creep Properties of Nickel-Iron Base Superalloy". In AM-EPRI 2016, a cura di J. Parker, J. Shingledecker e J. Siefert. ASM International, 2016. http://dx.doi.org/10.31399/asm.cp.am-epri-2016p0181.

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Abstract The aim of this work was to reveal the effects of trace elements on the creep properties of nickel-iron base superalloys, which are the candidate material for the large components of the advanced-ultrasupercritical (A-USC) power generation plants. High temperature tensile and creep properties of forged samples with seven different compositions were examined. No significant differences were observed in the creep rate versus time curves of the samples, of which contents of magnesium, zirconium, manganese and sulfur were varied. In contrast, the curves of phosphorus-added samples showed very small minimum creep rates compared to the other samples. The creep rupture lives of phosphorus-added samples were obviously longer than those of the other samples. Microstructure observation in the vicinity of grain boundaries of phosphorus-added samples after aging heat treatment revealed that there were fine precipitates consisting of phosphorus and niobium at the grain boundaries. The significant suppression of the creep deformation of phosphorus-added sample may be attributed to the grain boundary strengthening caused by the fine grain boundary precipitates.

Chaput, Heather, Brian W. Leitch e 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.

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Surface scratches and flaws encountered in CANDU nuclear pressure tubes must be evaluated to ensure that a cracking mechanism, called delayed hydride cracking (DHC), is not initiated. The stress concentration due to a flaw can cause diffusion of hydrogen and precipitation of zirconium hydride at the flaw tip. The presence of a hydride results in reduced fracture resistance in a local region where high stress prevails. In many cases, flaws exist for an extended period of time before the hydrogen content in the base material is sufficient to form a hydride. In this situation high stress creep can significantly relax the local stress at the flaw tip. The assessment of flaws on the basis of local stress distribution not considering creep is expected to be overly conservative, and may result in unnecessary remedial action in reactor operation and maintenance procedures. An experimental program has been developed to isolate and quantify the effect of creep on DHC in irradiated Zr-2.5%Nb pressure tube material. As part of this program, the thermal and load histories relevant to reactor operating conditions have been considered, and initial experimental results indicate that the action of creep increases the threshold load for crack initiation. Finite element analysis of creep relaxation around a hydride also supports the experimental results, and a fracture initiation model is applied to the experimental conditions in order to establish an analytical trend for the effect of creep. The quantitative effect predicted by the model is in reasonable agreement with the experimental results, and an improved, less conservative assessment procedure that accounts for creep is deemed to be practical.

Narayanan, Badri K., Lisa McFadden, M. J. Mills e 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.

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Pipeline girth welds deposited with a self-shielded flux cored electrode process (FCAW-S) have been characterized to assess the effect of micro-alloying elements on microstructure and precipitate evolution and correlate it to strength and toughness. A 2.0 mm diameter electrode was used to deposit weld metal in a 12.7 mm thick API grade X-70 pipe joint. The weld metal properties were characterized and shown to overmatch the pipe. The DBTT of the weld metal has been determined through Charpy V-Notch toughness measurements. The effect of heat input and welding procedure has been assessed over a range of heat inputs (1–1.5 kJ/mm.). The effect of dilution from the base plate on toughness has been assessed by measuring the sensitivity of weld metal toughness to changes in carbon content. The as-welded region of the weld has been characterized using different characterization techniques. Ferritic weld metal deposited with a self-shielded arc welding process has intentional additions of aluminum, magnesium, titanium and zirconium. This results in a complex precipitation process that has been characterized with a combination of electron microscopy techniques. The effect of micro-alloying additions on the variant selection during the austenite to ferrite transformation and microstructure evolution has been studied with electron back scattered diffraction (EBSD) in conjunction with orientation imaging microscopy (OIM). Transmission electron microscopy (TEM) was used to characterize the precipitate evolution in these welds. The evidence shows that the formation of a spinel oxide is critical for the nucleation of nitrides of zirconium and titanium and prevents the agglomeration of aluminum rich oxides and the formation of large aluminum nitrides. The evolution of precipitate formation is critical to limit large inclusions and improve weld metal toughness. The presence of titanium and zirconium increases the fraction of high angle grain boundaries within the microstructure resulting in increased resistance to crack propagation. The characterization of the microstructures at two different carbon contents indicates the greater propensity to form twin related variants with increase in carbon content. This suggests a lower transformation temperature of austenite and may be the reason for poor toughness.

Ozaltun, Hakan, Hee Seok Roh e 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.

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Abstract This paper provides an overview of the base model specifically developed to perform parametric sensitivity studies on the U-10Mo monolithic fuel system. U-Mo monolithic fuels are being considered for the conversion of test reactors into high-performance research reactors that operate using proliferation-resistant, low-enriched uranium (LEU) fuels. These plate-type fuels contain a high-density, low-enrichment fuel sandwiched between zirconium diffusion barriers and encapsulated in aluminum claddings. All U.S. high-performance research reactors have released the designs of their LEU monolithic fuel reactor cores. These designs include nearly 50 distinct fuel plate geometries with different operational parameters. Consequently, a single generic plate geometry representing all the extreme points in this design matrix is unrealistic. To evaluate the performance for various parameters, a set of sensitivity studies was performed. These studies considered various input parameters (i.e., geometric, operational, and material property-related). The results revealed valuable information about plate performance and the sensitivity of this performance to various modeling inputs. To establish a reference state for comparing these result, base model featuring representative irradiation conditions was developed. To capture in-reactor behavior accurately, incorporation of representative constitutive models capable of evolving properties with respect to temperature, irradiation time, and burnup was needed. The behavioral models considered burnup-dependent properties, swelling, creep, and degradation. This paper introduces the base model created for the parametric sensitivity studies. The detailed description of the procedure includes the model geometry, model discretization, thermo-mechanical coupling, material properties and behavioral models. This paper also provides selected results and assesses the performance of the base model.

Rashid, Joseph Y. R., Timothy Hardin, Mark M. Rashid, Robert S. Dunham e 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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The numerous indications recently found by UT-inspection in the reactor pressure vessel shell forgings at two Belgian nuclear power plants have raised some concerns about the effects of such indications on the vessel integrity and fitness for continued service. The UT indications have been attributed to hydrogen flaking, and preliminary estimates give a density of ∼40 indications per liter, with diameter of about 10–14 mm, oriented at a shallow ∼10° angle to the vessel inner surface. This type of high-density indications would not be characterized as geometric flaws with well defined crack-tip geometry that permits high-fidelity application of traditional fracture mechanics methods. An alternative analysis approach, with higher fidelity simulation of this type of “distributed discontinuities”, is proposed, as described in this paper. From a behavioral standpoint, the UT indications at Doel 3 and Tihange 2 represent material discontinuities whose mechanical effect can be evaluated using a damage-mechanics-based constitutive model. Previously, a special multiphase damage model was developed for cladding with zirconium hydrides, of similar morphology to the Doel 3 indications, in which the metal matrix and the hydride platelets are treated as separate material phases interacting at their interfaces with appropriate constraint conditions between them to ensure strain and stress compatibility. The hydride precipitates are represented as a brittle material and the metal matrix is modeled as a ductile elastic-plastic material. This damage model was implemented in a finite element computer program, and was validated using ring-tension and ring-compression tests of cladding specimens with various hydride morphologies. The model was able to predict specimens complete stress-strain curves and failure states with very high accuracy. The above described damage model is adapted to the high-density UT indications, morphology and distribution similar to the conditions of the Doel 3 vessel. The “hydrogen flakes” are characterized in the model as distributed damage of known orientation and volume fraction. A vessel of typical geometry and radiation-dependent mechanical properties is analyzed for various values of volume fraction of hydrogen flakes, and considering a transient loading scenario that conservatively simulates pressurized thermal shock. Interlinking of the “hydrogen flakes” and propagation of damage through the wall under the specified loading condition are part of the model’s capability of directly predicting whether or not vessel failure will occur. Thus, vessel susceptibility to failure and failure margin are judged by the degree of damage propagation through the wall.