Dans les réacteurs nucléaires à eau pressurisée (REP) encore en service dans le parc nucléaire civil français, certaines pièces en contact avec le milieu du circuit primaire, comme les éléments constitutifs des tubes de générateurs de vapeur (en alliage base nickel A600) ou les internes de cuve (en acier inoxydable 316L), sont sujettes à des phénomènes de corrosion sous contrainte (CSC). La mise en évidence expérimentale de la fissuration par CSC de l'alliage A600, réputé résistant, a conduit à de nombreuses études consacrées à la description et à la compréhension de ce phénomène de CSC en milieu primaire des REP. Dans l'optique d'un allongement de la durée de vie des réacteurs en service, il est rapidement devenu critique et stratégique de pouvoir modéliser ces phénomènes de CSC, afin d'optimiser les matériaux, conditions de fonctionnement etc. et d'appréhender les paramètres critiques pour limiter la CSC des composants. Cette étude s'intéresse au rôle de l'hydrogène dans le phénomène de CSC et plus particulièrement aux interactions H-matériau. En effet, l'hydrogène, venant du milieu primaire (H dissous ou H de l'eau), peut être absorbé par l'alliage pendant le processus d'oxydation au cours du fonctionnement du réacteur. Une fois absorbé, H peut être transporté à travers le matériau, interagissant à la fois avec les sites interstitiels du réseau cristallin et des défauts locaux, comme les dislocations, les précipités, les lacunes, etc. La présence de ces sites peut ralentir le transport de l'hydrogène et provoquer une accumulation locale d'hydrogène dans l'alliage. Cette accumulation pouvant modifier les propriétés mécaniques locales du matériau et favoriser sa rupture prématurée, il est essentiel d'identifier la nature de ces interactions H-matériau, et plus particulièrement la vitesse de diffusion et les cinétiques de piégeage de l'hydrogène sur ces défauts. Concernant ces interactions H-piège, la littérature propose très peu de données cinétiques complètes ; il est donc nécessaire d'étudier et caractériser ces interactions finement. Ce travail est composée de deux parties interdépendantes : (i) le développement d'un code de calcul capable de gérer les interactions H-matériau et (ii) l'extraction les données cinétiques de piégeage et de dépiégeage à partir de résultats expérimentaux afin d'alimenter le code de calcul et créer une base de données fiable. Du fait de la complexité des matériaux industriels (A600 et 316L), des \enquote{matériaux modèles} ont été élaborés en utilisant une série de traitements thermomécaniques permettent d'étudier des systèmes simples et de décorréler les différentes contributions possibles entre hydrogène interstitiel et piégé. Ces échantillons ont été chargés en deutérium (traceur isotopique de l'hydrogène) par polarisation cathodique. Après chargement, les échantillons ont été soumis à un essai de spectroscopie de désorption thermique (TDS) où le flux de désorption de deutérium est enregistré pendant une rampe de température et/ou un isotherme. L'extraction des données de diffusion interstitielle et des constantes cinétiques de piégeage se fait par une démarche d'ajustement des spectres expérimentaux obtenus par TDS acquis sur les \enquote{matériaux modèles} en utilisant un code de calcul basé sur la résolution numérique des équations de McNabb et Foster. Grâce à cette étude, les coefficients de diffusion de l'hydrogène ont pu être déterminés dans deux alliages (A600 et 316L) sur une grande gamme de températures. Les constantes cinétiques relatives au piégeage et au dépiégeage sur deux types de pièges (défauts), les carbures de chrome et les dislocations, ont été déterminées. Ces constantes constituent une base de données qui sera intégrée dans un modèle numérique plus large visant à simuler les phénomènes de CSC dans les REP. / In France all of the nuclear power plant facilities in service today are pressurized water reactors (PWR). Some parts of the PWR in contact with the primary circuit medium, such as the steam generator tubes (fabricated in nickel base alloy A600) and some reactor core internal components (fabricated in stainless steel 316L), can fall victim to environmental degradation phenomena such as stress corrosion cracking (SCC). In the late 1950's, H. Coriou observed experimentally and predicted this type of cracking in alloys traditionally renowned for their SCC resistance (A600). Just some 20 to 30 years later his predictions became a reality. Since then, numerous studies have focused on the description and comprehension of the SCC phenomenon in primary water under reactor operating conditions. In view of reactor lifetime extension, it has become both critical and strategic to be capable of simulating SCC phenomenon in order to optimize construction materials, operating conditions, etc. and to understand the critical parameters in order to limit the damage done by SCC. This study focuses on the role hydrogen plays in SCC phenomenon and in particular H-material interactions. Hydrogen, from primary medium in the form of dissolved H gas or H from the water, can be absorbed by the alloy during the oxidation process taking place under reactor operating conditions. Once absorbed, hydrogen may be transported across the material, diffusing in the interstitial sites of the crystallographic structure and interacting with local defects, such as dislocations, precipitates, vacancies, etc. The presence of these [local defect] sites can slow the hydrogen transport and may provoke local H accumulation in the alloy. This accumulation could modify the local mechanical properties of the material and favor premature rupture. It is therefore essential to identify the nature of these H-material interactions, specifically the rate of H diffusion and hydrogen trapping kinetics at these defects. Concerning these H-trap site interactions, literature presents very few complete sets of kinetic data; it is therefore necessary to study and characterize these interactions in-depth. This work is composed of two interdependent parts: (i) the development of a calculation code capable to manage these H-material interactions and (ii) to extract the kinetic constants for trapping and detrapping from experimental results in order to fuel the simulation code and create a solid database. Due to the complexity of industrial materials (A600 and SS316L), \enquote{model materials} were elaborated using a series of thermomechanical treatments allowing for the study of simplified systems and the deconvolution of the different possible trapped and interstitial hydrogen contributions. These \enquote{model} specimens were charged with deuterium (an isotopic hydrogen tracer) by cathodic polarization. After charging, specimens were subjected to thermal desorption mass spectroscopy (TDS) analysis where the deuterium desorption flux is monitored during a temperature ramp or at an isotherm. Interstitial diffusion and kinetic trapping and detrapping constants were extracted from experimental TDS spectra using a numerical fitting routine based upon the numerical resolution of the McNabb and Foster equations. This study allowed for the determination of the hydrogen diffusion coefficient in two alloys, Ni base alloy 600 and stainless steel 316L, and the kinetic trapping and detrapping constants at two trap site types, chromium carbides and dislocations. These constants will be used to construct a kinetic database which will serve as input parameters for a numerical model for the prediction and simulation of SCC in PWRs

En rampe de puissance, le combustible nucléaire est soumis à d'importantes contraintes thermiques et mécaniques, et subit une modification profonde de son environnement chimique. Le combustible contraint fortement la gaine, notamment au niveau des zones inter-pastilles, ce qui, associé au relâchement de produits de fission corrosifs, peut conduire à sa rupture par corrosion sous contraintes. Les évolutions simultanées de la mécanique, de la thermique et de la chimie du combustible sont liées, et participent au bon ou mauvais comportement de l'UO2 en rampe de puissance. L'objectif de ce travail est de modéliser à l'échelle d'une pastille de combustible, l'évolution couplée de la chimie, de la thermique et de la mécanique, et de préciser l'impact de ces couplages sur le comportement de l'UO2 en rampe de puissance. La finalité est d'évaluer un terme source en relâchement d'iode pour alimenter les modèles de corrosion sous contraintes dédiés aux études d'Interaction Pastille-Gaine. / Nuclear fuels under power transient undergo high thermal and mechanical stresses, as well as deep chemical modifications. Stresses on the cladding at the inter-pellet plane due to the pellet thermal expansion, associated to the corrosive fission product release, can lead to clad failures, resulting from a stress corrosion cracking mechanism. The thermal, mechanical and chemical properties of the UO2 irradiated fuel are closely dependent and play a major role on the behavior of the material during a power transient. The aim of this work is to model at the pellet scale the chemical, thermal and mechanical coupled changes of the UO2 fuel during a power transient scenario and to evaluate the consequences on the fuel behavior. The final objective is to obtain an evaluation of the iodine release source term to be used in I-SCC modelling codes dedicated to Pellet-Clad-Interaction studies.

In this study, the possibility of using low pressure hydrogenated steam to simulate primary water reactor conditions is examined. The oxides formed on Alloy 600 (WF675) between 350 Celsius and 500 Celsius in low pressure hydrogenated steam (with a ratio of oxygen at the Ni/NiO to oxygen in the system of 20) have been characterised using analytical electron microscopy (AEM) and compared to oxide that formed in a high pressure water in a autoclave at 350 Celsius with 30 cc/kg of hydrogen. Preferential oxidation of grain boundaries and bulk internal oxidation were observed on samples prepared by oxide polishing suspension (OPS). Conversely, samples mechanically ground to 600 grit produced a continuous, protective oxide film which suppressed the preferential and internal oxidation. The surface preparation changed the form of the oxides in both steam and autoclave tests. The preferential oxidation rate has been determined to be K_{oxide} = Aexp{-Q/RT}with A = 2.27×10^(−3) m^(2)s^(−1) and Q = 221 kJ.mol^(−1) (activation energy) for WF675 and A = 5.04 × 10^(−7) m^(2)s^(−1) and Q = 171 kJ.mol^(−1) for 15% cold worked WF675. These values are consistent with the activation energy of primary water stress corrosion cracking (PWSCC) initiation. Bulk oxygen diffusivities were calculated from the internal oxidation after 500 h exposures. At 500 Celsius the oxygen diffusivity was determined to be 1.79×10^(−20) m^(2)s^(−1) for WF675 and 1.21×10^(−20) m^(2)s^(−1) for 15% cold worked WF675, the oxygen diffusivity at 400 Celsius in 15% cold worked WF675 was calculated to be 1.49×10^(−22) m^(2)s^(−1).The Cr-depletion associated with preferential oxidation has been assessed by AEM. The Cr-depletion was asymmetric and it could not be accounted for by local variations in the diffusion rate. Chemically induced grain boundary migration is suggested as a possible explanation. Constant load SCC tests conducted in hydrogenated steam at 400 Celsius have shown a similar trend to the classical dependency of PWSCC as a function of potential. The SCC samples were also prepared with two surface finishes, OPS and 600 grit. In all SCC tests, significantly more cracking was observed on the OPS surface and all failures initiated from this surface.

Bei dem Prozess einer Wasserstoffinduzierten Spannungsrisskorrosion (H-SpRK) handelt es sich um einen zeitabhängigen Vorgang, der zu einer Reduzierung der Duktilität und Widerstandskraft des Spannstahls führt und daraus resultierend ein sprödes und schlagartiges Versagen eines Spannbetonbauwerkes zur Folge haben kann. Der Prozess selbst und insbesondere auch die ihn beeinflussenden Parameter sind für die im Bauwesen verwendeten hochfesten Spannstähle älterer Produktion weitestgehend unerforscht. Die Relevanz für bestehende Bauwerke ist jedoch nicht zuletzt durch einzelne dokumentierte und untersuchte Schadensfälle nachgewiesen. Ziel der vorliegenden Arbeit war es, die zur Verfügung stehenden Bauwerksuntersuchungen aus den zurückliegenden ca. 10 Jahren statistisch zu analysieren und auszuwerten. Auf dieser Basis war ein Berechnungsmodell wahrscheinlichkeitstheoretischer Basis zu entwickeln, mit dem die Gefahr eines spröden Bauwerksversagens für das Gesamttragwerk beurteilt und hinsichtlich der Auswirkungen auf das einzuhaltende Sicherheitsniveau bewertet werden kann. Es wurden insgesamt 31 Bauwerksuntersuchungen statistisch ausgewertet und beurteilt. Die zur Verfügung stehenden Daten wurden analysiert und hinsichtlich der Prüfqualität sowie der Quantität der Proben bewertet. Dabei war festzustellen, dass aufgrund fehlender konkreter Vorgaben im Regelwerk eine sehr heterogene Datenbasis vorliegt. Nicht alle Untersuchungsergebnisse konnten in die weitere Auswertung einbezogen werden. Die in ausreichender Datenqualität und Datenumfang geeigneten Untersuchungen wurden hinsichtlich ihrer Relevanz für den Prozess einer H-SpRK analysiert und die Auswirkungen einzelner Parameter bewertet. Im Ergebnis der materialtechnischen Untersuchungen und statistischen Auswertung der Bauwerksuntersuchungen wurde ein Berechnungsmodell vorgestellt, das den gleichzeitigen Ausfall von Spannstahl in allen Bereichen des Bauwerkes berücksichtigt. Zusätzlich zum Standardverfahren des beschriebenen Vorgehens wird das Modell um den Ansatz eines korrelierten Spannstahlausfalls erweitert. Außerdem wird für Bauwerke mit einem statisch unbestimmten Anteil der Vorspannung sowie für Konstruktionen mit gestaffelter Spannstahlbewehrung die Anwendung des Verfahrens konkretisiert. Neben der Erstellung des Berechnungsmodells wurden Vorschläge zu Vorgaben für die Bauwerksprüfung vorgestellt. Dazu zählen insbesondere die Festlegung von Prüfintervallen sowie einheitliche Vorgaben zu den verwendeten Prüfmethoden und -verfahren. Bezüglich der Festlegung von Mindestumfängen von Proben wird zwischen bestehenden und auch weiter zu nutzenden Bauwerken einerseits sowie Probennahmen im Rahmen von Rückbaumaßnahmen unterschieden.

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The damage development and strength of ply-level scaled carbon/epoxy composite laminates having stacking sequence of [+Tn/-Tn/902n]s where constraint ply angle, T, was 0, 15, 30, 45, 60, and 75 degrees, and size was scaled as n=1,2,3, and 4, is reported in Part I. X-radiography was used to monitor damage developments. First-ply failure stress, and tensile strength were recorded. First-ply failure of the midplane 90 deg. plies depended on the stiffness of constraint plies, and size. All 24 cases were predicted using Zhang's shear-lag model and data generated from cross-ply tests. Laminate strength was controlled by the initiation of a triangular-shaped local delamination of the surface angle plies. This delamination was predicted using O'Brien's strain energy release rate model for delamination of surface angle plies. For each ply angle, the smallest laminate was used to predict delamination (and strength) of the other sizes. The in-situ tensile strength of the 0 deg. plies within different cross-ply, and quasi-isotropic laminates of varying size and stacking sequence is reported in Part II. No size effect was observed in the strength of 0 deg. plies for those lay-ups having failure confined to the gauge section. Laminates exhibiting a size-strength relationship, had grip region failures for the larger sizes. A statistically significant set of 3-point bend tests of unidirectional beams were used to provide parameters for a Weibull model, to re-examine relationship between ultimate strength of 0 deg. plies and specimen volume. The maximum stress in the 0 deg. plies in bending, and the tensile strength of the 0 deg. plies (from valid tests only) was the same. Weibull theory predicted loss of strength which was not observed in the experiments. An effort to model the durability and life of quasi-isotropic E-glass/913 epoxy composite laminates under steady load and in an acidic environment is reported in Part III. Stress-rupture tests of unidirectional coupons immersed in a weak hydrochloric acid solution was conducted to determine their stress-life response. Creep tests were conducted on unidirectional coupons parallel and transverse to the fibers, and on ±45°. layups to characterize the lamina stress- and time-dependent compliances. These data were used in a composite stress-rupture life model, based on the critical element modeling philosophy of Reifsnider, to predict the life of two ply-level thickness-scaled quasi-isotropic laminates. / Ph. D.

Main extrinsic and intrinsic modifiers factors of crack growth rate in AA7050-T7451 were assessed in order to provide tools for aeronautical structures designers. These tools cover most necessary information to project aircraft\'s structures using the studied alloy, under damage tolerance philosophy. The experimental methodology consisted of use CT specimens, on TL and LT rolling direction to test its behavior under different conditions of stress ratio, force waveform, and the environment. The stress ratio values were 0.1 and 0.5, the force waveform used were sine and trapezoidal or Dwell under normal air laboratory conditions and salt fog 3.5%NaCl weight in order to simulate the marine environment. In Dwell tests, results were checked with the electrical potential drop technique (DCPD) in addition to the crack opening displacement (COD) method. Using the Walker coefficients, calculated on the present research, could be projected accurately the crack propagation behavior on Paris region and do fatigue life predictions using da/dN and S-N diagrams for different stress ratio values. The corrosion environment increases both crack growth rate and ΔKth due to oxides formation on the crack path that generates a crack closure effect. Dwell carrying makes decrease the crack growth rate by decreasing the slope of the Paris line on log (da/dN) versus log (ΔK) curve, instead of shifting down the line as occurs on titanium alloys. Rolling direction change from LT to TL increase the FCG rate in both threshold and Paris region, where the rate change use to be small. / Os principais fatores modificadores extrínsecos e intrínsecos da taxa de propagação de trincas na liga AA7050-T7451 foram avaliados para fornecer subsídios para projetistas de estruturas aeronáuticas, com base na filosofía de tolerância ao dano. A metodologia experimental consistiu em ensaiar corpos de prova do tipo compact tension (CT) da liga nas direções de laminação TL e LT, para verificar seu comportamento sob diferentes razões de tensões, forma de onda e condição ambiente. Os valores de razão de tensão estudados foram 0,1 e 0,5, as formas de onda foram senoidal e trapezoidal ou de Dwell, em condições normais de laboratório, ao ar, e névoa salina 3,5% NaCl, em massa, para simular um ambiente marinho. No caso dos ensaios Dwell, os resultados foram conferidos pelo método de queda de potencial eléctrico (QPE), além do método de flexibilidade elástica. Usando os coeficientes de Walker calculados a partir dos resultados obtidos, pôde-se projetar com precisão o comportamento da propagação de trinca na região de Paris e prever a vida em fadiga usando os diagramas da/dN e S-N para diferentes valores da razão de tensões. O ambiente corrosivo aumenta tanto a taxa de propagação de trinca, quanto o valor de ΔKth por causa da formação de óxidos na trajetória da trinca, que geram um efeito de fechamento sobre a mesma. Quanto à forma de onda, verificou-se que o carregamento Dwell diminui a taxa de propagação de trinca, diminuindo a inclinação das curvas log (da/dN) versus log (ΔK) na região de Paris, ao invés de deslocá-la paralelamente como ocorre com ligas de titânio. A mudança da direção de laminação de LT para TL aumenta a taxa de propagação de trinca por fadiga (PTF) tanto na região de threshold, quanto na região de Paris, onde a mudança de taxa é pequena.

Main extrinsic and intrinsic modifiers factors of crack growth rate in AA7050-T7451 were assessed in order to provide tools for aeronautical structures designers. These tools cover most necessary information to project aircraft\'s structures using the studied alloy, under damage tolerance philosophy. The experimental methodology consisted of use CT specimens, on TL and LT rolling direction to test its behavior under different conditions of stress ratio, force waveform, and the environment. The stress ratio values were 0.1 and 0.5, the force waveform used were sine and trapezoidal or Dwell under normal air laboratory conditions and salt fog 3.5%NaCl weight in order to simulate the marine environment. In Dwell tests, results were checked with the electrical potential drop technique (DCPD) in addition to the crack opening displacement (COD) method. Using the Walker coefficients, calculated on the present research, could be projected accurately the crack propagation behavior on Paris region and do fatigue life predictions using da/dN and S-N diagrams for different stress ratio values. The corrosion environment increases both crack growth rate and ΔKth due to oxides formation on the crack path that generates a crack closure effect. Dwell carrying makes decrease the crack growth rate by decreasing the slope of the Paris line on log (da/dN) versus log (ΔK) curve, instead of shifting down the line as occurs on titanium alloys. Rolling direction change from LT to TL increase the FCG rate in both threshold and Paris region, where the rate change use to be small. / Os principais fatores modificadores extrínsecos e intrínsecos da taxa de propagação de trincas na liga AA7050-T7451 foram avaliados para fornecer subsídios para projetistas de estruturas aeronáuticas, com base na filosofía de tolerância ao dano. A metodologia experimental consistiu em ensaiar corpos de prova do tipo compact tension (CT) da liga nas direções de laminação TL e LT, para verificar seu comportamento sob diferentes razões de tensões, forma de onda e condição ambiente. Os valores de razão de tensão estudados foram 0,1 e 0,5, as formas de onda foram senoidal e trapezoidal ou de Dwell, em condições normais de laboratório, ao ar, e névoa salina 3,5% NaCl, em massa, para simular um ambiente marinho. No caso dos ensaios Dwell, os resultados foram conferidos pelo método de queda de potencial eléctrico (QPE), além do método de flexibilidade elástica. Usando os coeficientes de Walker calculados a partir dos resultados obtidos, pôde-se projetar com precisão o comportamento da propagação de trinca na região de Paris e prever a vida em fadiga usando os diagramas da/dN e S-N para diferentes valores da razão de tensões. O ambiente corrosivo aumenta tanto a taxa de propagação de trinca, quanto o valor de ΔKth por causa da formação de óxidos na trajetória da trinca, que geram um efeito de fechamento sobre a mesma. Quanto à forma de onda, verificou-se que o carregamento Dwell diminui a taxa de propagação de trinca, diminuindo a inclinação das curvas log (da/dN) versus log (ΔK) na região de Paris, ao invés de deslocá-la paralelamente como ocorre com ligas de titânio. A mudança da direção de laminação de LT para TL aumenta a taxa de propagação de trinca por fadiga (PTF) tanto na região de threshold, quanto na região de Paris, onde a mudança de taxa é pequena.