Submitted by Pedro Silva Filho (pfsilva@ipen.br) on 2017-11-17T16:32:32Z No. of bitstreams: 0 / Made available in DSpace on 2017-11-17T16:32:32Z (GMT). No. of bitstreams: 0 / Os aços inoxidáveis duplex são largamente utilizados na fabricação de equipamentos para a indústria de óleo e gás, utilizados tanto no ambiente onshore quanto offshore. Sua grande limitação é que, com o aumento de temperatura, ocorre precipitação de fases indesejáveis, que reduzem drasticamente a resistência à corrosão e as propriedades mecânicas desses materiais. Considerando o efeito deletério da soldagem a fusão nos aços inoxidáveis duplex, a soldagem por atrito com pino não-consumível (FSW) é amplamente considerada como alternativa aos processos convencionais. Como no FSW a união dos materiais ocorre no estado sólido, muitos dos problemas de soldabilidade associados às técnicas tradicionais de soldagem por fusão são evitados. Neste trabalho, amostras retiradas da zona misturada (ZM), das zonas afetadas pelo calor (ZTA e ZTMA) e do metal de base (MB) de chapas de aço inoxidável lean duplex LDX 2404&reg (UNS S82441) soldadas por atrito com pino não-consumível foram caracterizadas microestruturalmente e tiveram sua resistência à corrosão avaliada por meio de ensaios eletroquímicos. Os resultados obtidos nos ensaios eletroquímicos indicaram que as zonas afetadas pelo calor e a ZM se mantiveram tão resistentes à corrosão localizada quanto o MB. Permitiram concluir também que a excelente resistência à corrosão da liga está associada ao teor elevado de N. / Dissertação (Mestrado em Tecnologia Nuclear) / IPEN/D / Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP

Os aços inoxidáveis duplex são materiais com um excelente desempenho, devido às suas sobressalentes propriedades mecânicas e excelente resistência à corrosão. Uma composição química adequada e microestrutura balanceada são as responsáveis por esta combinação de propriedades. No entanto, são estes mesmos fatores que os fazem especialmente susceptíveis à precipitação de fases intermetálicas, com efeitos maléficos no seu desempenho. Durante os ciclos térmicos de uma soldagem multipasse, a precipitação de intermetálicos é crítica. Foi desenvolvido um método para simular os ciclos térmicos de uma solda multipasse. Usando este método, foi estudada a precipitação de nitreto de cromo e fase sigma na zona afetada pelo calor submetida a temperaturas abaixo de 950°C dos aços inoxidáveis duplex UNS S31803 e S32550. Foram estudadas energias de soldagem na faixa de 0,4 a 1,0 kJ/mm. Foi determinada mediante extração de precipitados, seguida de difração de raios X na câmara de Debye-Scherrer e microscopia eletrônica de transmissão, a precipitação de nitreto de cromo para energias de soldagem de 0,4 a 1,0 kJ/mm e de fase sigma para energias de soldagem de 0,6-1,0 KJ/mm, no UNS S32550. Já o UNS S31803 não apresentou precipitação alguma para as energias de soldagem estudadas. Baseando-se nos resultados verifica-se que durante uma soldagem multipasse o UNS S31803 é menos propenso que o UNS S32550 à precipitação de intermetálicos na zona afetada pelo calor submetida a temperaturas abaixo de 950°C. / Duplex stainless steels belong to a group of high performance stainless steels regarding to corrosion and mechanical properties. These achievements are related to a suitable chemical composition and a balanced microstructure. During welding thermal cycles the microstructure changes and, consequently, corrosion and mechanical properties might be impaired due to a precipitation of intermetallic phases. This precipitation is an issue to be addressed for multipass welding. It was developed a method for simulate the multipass welding thermal cycles. Using this method chromium nitride and sigma phase precipitation was studied in a simulated heat affected zone of multipass welding (three passes) of UNS S31803 and UNS S32550 duplex stainless steels with different heat inputs (0,4 to 1,0 kJ/mm). The HAZ simulated region was below 950°C maximum temperature. Microstructural characterization of simulated samples showed discontinuous films of a precipitated phase at ferrite/ferrite grain boundaries and ferrite/austenite interfaces were observed only in a UNS S32550 duplex grade for all heat inputs simulated. This suggests that sigma phase and chromium nitride precipitation took place during sample thermocycling. X-ray diffraction in a Debye-Scherrer chamber of extracted precipitates and electron diffraction by TEM confirmed the presence of chromium nitrides for all range of heat input studied and sigma phase for heat input above 0,6 kJ/mm. On the other hand, microstructural analysis of UNS S31803 simulated samples did not present precipitation of intermetallic phases in the tested temperature range of HAZ. Based on these results, UNS S31803 is more resistant than UNS S32550 to intermetallic phases precipitation in multipass welding.

Au cours d'une irradiation neutronique à long-terme dans les Réacteurs à Eau Pressurisée (REPs), une modification importante du comportement mécanique des matériaux utilisés dans les internes de cuve (composés des aciers inoxydables austénitiques de la série 300) est observée, y compris un durcissement et un adoucissement induit par irradiation, une perte de la ductilité et de la ténacité. Jusqu'à présent, beaucoup efforts ont été contribués pour identifier les effets d'irradiation sur l'évolution microstructurale du matériau (dislocations, boucles de Frank, cavités, ségrégation, etc.). Le gonflement induit par irradiation, considéré comme un facteur limitant la durée de fonctionnement des réacteurs, pourrait modifier les propriétés mécaniques des matériaux (plasticité, ténacité, etc), même conduire à une distorsion des structures du fait des modifications dimensionnelles entre les différentes composantes.L'objectif principal de ce travail de thèse est d'étudier qualitativement l'influence de l'effet du gonflement sur le comportement mécanique des matériaux irradiés. Un modèle micromécanique constitutif en grandes déformations basé sur les évolutions de la densité de dislocations et de défauts d'irradiation (boucles de Frank) est développé et implémenté dans les codes de calcul éléments finis ZéBuLoN et Cast3M. Les simulations numériques sont réalisées pour calculer les propriétés mécaniques d'un agrégat polycristallin. Par ailleurs, la technique d'homogénéisation est appliquée pour développer un modèle de type Gurson. Les simulations d'une cellule poreuse sont utilisés pour étudier le comportement mécanique des monocristaux poreux, en tenant compte des différents effets de la triaxialité, de la porosité et de l'orientation cristallographique, afin d'étudier l'effet de la présence des cavités sur la plasticité et la rugosité du matériau irradié à l'échelle polycristallin. / During long-time neutron irradiation occurred in Pressurized Water Reactors (PWRs), significant changes of the mechanical behavior of materials used in reactor core internals (made of 300 series austenitic stainless steels) are observed, including irradiation-induced hardening and softening, loss of ductility and toughness. So far, much effect has been made to identify radiation effects on material microstructure evolution (dislocations, Frank loops, cavities, segregation, etc.). The irradiation-induced cavity swelling, considered as a potential factor limiting the reactor lifetime, could change the mechanical properties of materials (plasticity, toughness, etc.), even lead to a structure distortion because of the dimensional modifications between different components.The principal aim of the present PhD work is to study qualitatively the influence of cavity swelling on the mechanical behaviors of irradiated materials. A micromechanical constitutive model based on dislocation and irradiation defect (Frank loops) density evolution has been developed and implemented into ZéBuLoN and Cast3M finite element codes to adapt the large deformation framework. 3D FE analysis is performed to compute the mechanical properties of a polycrystalline aggregate. Furthermore, homogenization technique is applied to develop a Gurson-type model. Unit cell simulations are used to study the mechanical behavior of porous single crystals, by accounting for various effects of stress triaxiality, of void volume fraction and of crystallographic orientation, in order to study void effect on the irradiated material plasticity and roughness at polycrystalline scale.

Les aciers inoxydables austénitiques de type 304L et 316L sont largement employés dans le circuit primaire des centrales nucléaires à Réacteurs à Eau sous Pression (REP). Le retour d'expérience indique la présence d'un nombre limité de fissures intergranulaires dues à la corrosion sous contrainte (CSC) sur des composants en acier inoxydable écroui. Il a été démontré qu'une pré-déformation importante associée à un chargement cyclique favorise la propagation des fissures de CSC. L'objectif de l'étude est d'améliorer la compréhension du rôle de la pré-déformation par traction ou par laminage sur les mécanismes d'amorçage de la CSC pour les aciers inoxydables austénitiques. Le comportement mécanique des matériaux écrouis a été caractérisé et des essais d'amorçage en milieu primaire simulé ont été réalisés sur des éprouvettes entaillées. L'ensemble des essais d'amorçage réalisés a confirmé un fort effet du trajet de chargement sur la sensibilité à l'amorçage des matériaux étudiés, quel que soit le niveau de pré-déformation. Un critère global a été proposé pour réunir les deux aspects de l'amorçage de la fissuration que sont la densité de fissures et leur profondeur. Ce critère est utile pour caractériser l'amorçage tandis que la profondeur maximale de fissure est le paramètre pertinent pour définir la transition entre propagation lente et propagation rapide. Des cartes de sensibilité à l'amorçage vrai ont été établies. Une profondeur critique de fissure de 10 à 20 µm a été déterminée pour les aciers 316L A et B pré-déformés par laminage. Elle est comprise entre 20 µm et 50 µm pour les matériaux pré-déformés par traction. Une ébauche de modèle d'ingénierie applicable aux aciers inoxydables austénitiques a été proposée : l'effet de la température est négligeable dans la gamme 290°C-360°C et l'impact de la contrainte sur le temps pour obtenir la transition varie comme (max/Rp0.2, T°C)11,5. L'effet du trajet de chargement ainsi que de l'écrouissage de surface dû à l'usinage sont intégrés indirectement à l'indice de contrainte, à ce stade du modèle. L'effet « matériau » observé dans cette étude tient principalement à l'effet du trajet de déformation. La puissance élevée de la dépendance à la contrainte traduit l'intégration de différents paramètres favorisant la localisation de la déformation. Pour cette raison, il sera nécessaire de définir le champ des contraintes locales pour parvenir à une modélisation plus physique. / Austenitic stainless steels are widely used in primary circuits of Pressurized Water Reactors (PWR) plants. However, a limited number of cases of Intergranular Stress Corrosion Cracking (IGSCC) has been detected in cold-worked (CW) areas of non-sensitized austenitic stainless steel components in French PWRs. A previous program launched in the early 2000's identified the required conditions for SCC of cold-worked stainless steels. It was found that a high strain hardening coupled with a cyclic loading favoured SCC. The present study aims at better understanding the role of pre-straining on crack initiation and at developing an engineering model for IGSCC initiation of 304L and 316L stainless steels in primary water. Such model will be based on SCC initiation tests on notched (not pre-cracked) specimens under “trapezoidal” cyclic loading. The effects of pre-straining (tensile versus cold rolling), cold-work level and strain path on the SCC mechanisms are investigated. Experimental results demonstrate the dominating effect of strain path on SCC susceptibility for all pre-straining levels. Initiation can be understood as crack density and crack depth. A global criterion has been proposed to integrate both aspects of initiation. Maps of SCC initiation susceptibility have been proposed. A critical crack depth between 10 and 20 µm has been demonstrated to define transition between slow propagation and fast propagation for rolled materials. For tensile pre-straining, the critical crack depth is in the range 20 - 50 µm. Experimental evidences support the notion of a KISCC threshold, whose value depends on materials, pre-straining ant load applied. The initiation time has been found to depend on the applied loading as a function of (max/YV)11,5. The effect of both strain path and surface hardening is indirectly taken into account via the yield stress. In this study, material differences rely on strain path effect on mechanical properties. As a result, a stress high exponent has been identified which includes all micro-scale mechanisms leading to strain localisation at initiation sites.

Fe-Cr based steels, i.e. stainless steels, possessing a combination of excellent corrosion resistance and good mechanical properties, have indispensable applications ranging from low-end cooking utensils, to sophisticated components for nuclear power plants. However, the bcc/bct phase containing stainless steels which have a miscibility gap (MG) suffer from the so-called “475 oC embrittlement” leading to hardness increase and toughness deterioration. It occurs due to demixing of Fe and Cr leading to the formation of Fe-rich (α) and Cr-rich (α′) regions in bcc/bct phases. The demixing is referred to as phase separation (PS). The goal of this work was to study PS in ferrite containing stainless steels mainly by small-angle neutron scattering (SANS). Firstly, the application of different experimental techniques for the study of phase separation in Fe-Cr based steels was reviewed and supplemented by new measurements. SANS was shown to be very sensitive to the nanostructure change caused by PS and capable of characterizing the early stages of PS in Fe-Cr alloys. However, atom probe tomography and transmission electron microscopy are complementary to SANS. Therefore, in order to have a more complete view of the microstructure, the combination of these techniques should be pursued. Secondly, the factors affecting the initial microstructure prior to aging treatment and the effect of the resulted initial microstructure on PS were systematically investigated using binary Fe-Cr model alloys. The critical temperature of the MG was determined to be located between 560 and 580 oC in binary Fe-Cr. The results indicate that the solution treatment temperature above the MG and the cooling rate after solution treatment have significant effects on the initial microstructure and thus on PS during subsequent aging. The mechanisms responsible for the changed aging behavior are Cr clustering, quenched-in vacancy and decomposition during cooling. Therefore, computational simulations should take into account these factors and the initial microstructure to make predictions that are more accurate. Thirdly, the study was extended to PS in commercial duplex stainless steels (DSSs) which are of practical importance in various industries, e.g., nuclear power. It is found that alloying elements have an important effect on PS in DSSs. The grade 2507 (25 %Cr, 7 %Ni) experiences stronger PS than grade 2205 (22 %Cr, 5 % Ni) for the same heat treatment. Moreover, the fracture mechanisms as well as the mechanical properties depend on the extent of PS.  Finally, the fundamental aspects regarding the neutron scattering behavior for Fe-Cr alloys were examined. The results show that the nuclear and magnetic scattering of neutrons depend on the evolution of the nanoscale compositional fluctuation in Fe-Cr alloys. The ratio of the magnitude of nuclear scattering versus magnetic scattering varies with the extent of PS. / Stål baserade på Fe-Cr systemet, det vill säga rostfria stål, som har en kombination av utmärkta korrosionsegenskaper och bra mekaniska egenskaper, har många tillämpningar; allt från köksredskap, till sofistikerade komponenter för kärnkraftverk. Rostfria stål som innehåller Bcc / bct-fasen och som således har en blandningslucka, är känsliga för den så kallade "475 °C försprödningen" som leder till en hårdhetsökning men kraftigt försämrad slagseghet. Detta uppstår på grund av en uppdelning av Fe och Cr som leder till bildandet av Fe-rika (a) och Cr-rika (a’) regioner i bcc / bct-fasen. Denna uppdelning brukar kallas fasseparation. Målet med detta arbete var att studera fasseparationen i ferrit-innehållande rostfria stål främst genom lågvinkel-spridning av neutroner (SANS). Till att börja med studerades och jämfördes olika experimentella tekniker för undersökning av fasseparation i Fe-Cr-baserade stål med nya SANS- mätningar. SANS visade sig vara mycket känslig för förändringar på nano-skala orsakad av fasseparation och tekniken visade sig även kapabel att karakterisera de tidiga stadierna av fasseparation i Fe-Cr-legeringar. För att få en mer fullständig bild av mikrostrukturen efter fasseparation, bör emellertid en kombination av SANS och komplementära tekniker, såsom atomsond och transmissions-elektronmikroskopi, användas. Vidare undersöktes de faktorer som påverkar den ursprungliga mikrostrukturen före åldringsbehandling, och effekten av den initiala mikrostrukturen på fasseparation studerades systematiskt med användning av binära modell-legeringar av Fe-Cr. Den kritiska temperaturen för blandningsluckan i Fe-Cr bestämdes vara belägen mellan 560 och 580 °C. Resultaten indikerar att temperaturen för upplösningsbehandling ovanför blandningsluckan och kylhastigheten har en signifikant inverkan på den initiala mikrostrukturen och därmed på fasseparationen under efterföljande åldring. Mekanismerna som är ansvariga för det förändrade åldringsbeteendet är: Cr-klustring, insläckta vakanser och fasseparation under kylning. Simuleringar av fasseparationen bör därför ta hänsyn till dessa faktorer och den ursprungliga mikrostrukturen för att göra mer exakta förutsägelser av hur mikrostrukturen utvecklar sig med åldringstiden. Fasseparationen i kommersiella duplexa rostfria stål (DSS), som är av stor praktisk betydelse i olika branscher, t ex kärnkraft, studerades också med SANS. Det visade sig att mängden av olika legeringselement har en viktig effekt på graden av fasseparation i DSS. Legeringen 2507 uppvisade en tydligare fasseparation jämfört med legering 2205 för samma värmebehandling. Brottmekanismerna såväl som de mekaniska egenskaperna visade sig bero på omfattningen av fasseparationen. Slutligen undersöktes de grundläggande aspekterna hos neutronspridnings-beteendet för binära Fe-Cr-legeringar. Resultaten visade att kärn- och magnetisk spridning av neutroner beror på utvecklingen av sammansättningsfluktuationerna på en nanoskala i Fe-Cr-legeringar. Förhållandet mellan magnetisk- och kärnspridning varierar med omfattningen av fasseparationen. / <p>QC 20171117</p>

A corrosão seletiva de fases de dois tipos de aços inoxidáveis fundidos foi analisada, ao serem submetidos a vários valores constantes de potencial, a partir da região catódica para a anódica da curva de polarização. Os aços estudados foram: austenítico (ACI CF-3M) solubilizado e martensítico (ACI CA-6NM) normalizado e revenido. As curvas de polarização foram traçadas potenciodinamicamente, a uma velocidade de varredura de 0,16 m.V.s-1 em solução aerada contendo H2SO4 1M e NaCl 1M, pH 0,35, à temperatura ambiente. Vários valores de potencial foram selecionados, previamente localizados nas regiões catódica, ativa, passiva e transpassiva da curva de polarização. Potenciostaticamente, foram atingidos os valores de potencial selecionados, sendo eles mantidos fixos por 1800 s. Após o ataque potenciostático, as aparências metalográficas dos aços foram verificadas, desde a região catódica até a anódica. Por microssonda eletrônica, foram quantificados os elementos químicos presentes nas fases dos aços. Para melhor avaliar o início de propagação de pite, foi determinada a porcentagem de íons liberados para o eletrólito, após a imposição de valores de potencial críticos de pite predeterminados pelas curvas de polarização, pelas aparências metalográficas e pelas curvas de densidade de corrente em função do tempo. / The selective corrosion of phases present in two types of cast stainless steels was analyzed, when submitled to several constant values of potential, starting from the cathodic to the anodic regions of the polarization curve. The cast stainless steels were: austenitic (ACI CF-3M) solubilized and martensitic (ACI CA-6NM) normalized and tempered. The polarization curves were obtained at a scanning rate of 0.16 mV.s-1 in 1M H2S04 and 1M NaCI solution, pH 0.35 and at room temperature. Several potential values were selected, previously located in the cathodic, active, passive and transpassive regions of the polarization curve. The values of the selected potential were maintained fixed for 1800 s. After the potentiostatic etching, the metallographic appearances of the steels were verified, from the cathodic to the anodic region. Through electronic microprobe analysis, the present chemical elements were quantified in the phases of the steels. For betler evaluating the beginning of pitling propagation in the studied steels, liberated ion percentage for the solution was determined, after the imposition of critic pitting potential values predetermined from the polarization curves, through the metallographic appearances obtained after potentiostatic etching of the samples and the current density curves as a function of time.

No description available.

Heat exchanger tubes are commonly made from stainless steel.In a heat exchanger both the process fluid and the cooling orheating media can be corrosive. It is therefore important to beable to select materials that do not suffer from corrosion.Current methods in this area, however, suffer from limitationsand shortcomings. This thesis concerns corrosion tests forgeneral corrosion, dewpoint corrosion and stress corrosioncracking, respectively. For evaluation of general corrosion ofsuperduplex stainless steels in hydrochloric acid and sulphuricacid the importance of activation was studied. The results showthat activation has a great influence on the test result.Further the results indicate that experimental differences canbe the explanation for previously reported differences incorrosion resistance of superduplex stainless steel that havebeen attributed to the alloying with Cu and W. Furthermore, asimple test loop for testing stainless steels under dew formingconditions with a formed condensate of 1 % hydrochloric acidhas been developed. In the work constant strain and constantload test result have been compared and the observationsindicate that the differences can be explained by differencesin the relaxation properties of the materials. <b>Key words:</b>corrosion testing, heat exchanger, stainlesssteel, general corrosion, immersion tests, activation, stresscorrosion cracking, constant load, u-bends, relaxation,dewpoint corrosion / NR 20140805

No description available.

L’acier 316L(N) est le matériau de référence pour les structures du circuit primaire des réacteurs nucléaires de quatrième génération, en raison de leur résistance mécanique à la température de fonctionnement, de l’ordre de 550°C. La thèse a permis de développer un modèle polycristallin, capable de prédire le comportement de ces aciers, basé sur la description du glissement viscoplastique des dislocation à haute température, de mise en œuvre simple et avec l’identification d’un nombre de paramètres matériau limité. La démarche de modélisation a été progressive. Lors de la première étape, nous avons proposé et validé une loi d'homogénéisation élasto-viscoplastique à champs moyens, grâce à de nombreux calculs par éléments finis, en considérant des durcissements plastique et des viscosités cristallines. Ensuite, un modèle de viscoplasticité cristalline, reposant sur les lois d’évolution des densités de différents types de dislocations, a été implémenté et les prédictions ont été validés en considérant un très grand nombre de résultats expérimentaux à faible. Le modèle a ensuite été enrichi afin de prendre en compte les mécanismes physiques supplémentaires observés à température élevée, comme la montée des dislocations, le vieillissement dynamique et l’apparition d’une structure de dislocation très hétérogène. Le modèle proposé nécessite uniquement l’ajustement de trois paramètres par identification inverse, utilisant seulement des essais de traction monotone avec saut de vitesse. Les prédictions du comportement mécanique en chargement uniaxial et cyclique sont également en bon accord avec les mesures expérimentales aux températures élevées. / The 316L(N) stainless steels is the reference material for the primary circuit structures of fourth-generation nuclear reactors. This alloy present high mechanical resistance at the operation temperature range of these reactors, of the order of 550 °C. This PhD allowed to develop a polycrystalline model based on the description of the viscoplastic dislocation slip at high temperatures, with straightforward implementation and with identification of a limited number of material parameters. The modeling process was progressive. In a first step, we proposed and validated a mean-field elastic-viscoplastic homogenization law, in comparison to numerous finite element calculations, considering crystalline plastic hardening and crystalline viscosity. Then, a model of crystalline viscoplasticity, based on the evolution laws of the different dislocations densities was implemented and the predictions were validated considering a very large number of experimental results at low temperature. The model was then enhanced to take into account the additional physical mechanisms observed at high temperature, such as dislocation climb, dynamic strain aging and the appearance of a very heterogeneous dislocation structure. The proposed model requires the adjustment of only three parameters by inverse identification, using only monotonic tensile tests at different strain rates. The mechanical behavior predictions in uniaxial and cyclic loading are also in good agreement with experimental measurements at high temperature.