The requirements for the next generation of nuclear reactors call for more radiation tolerant materials. One such material, nanostructured ferritic alloys (NFA) are a candidate material for use in cladding. The radiation tolerance of NFAs comes from the high number density of small oxide nanofeatures composed of Y, Ti, and O. These oxide nanofeatures or nano-oxides act as alternative nucleation sites for bubbles of transmutation He, thus preventing the accumulation of He atoms at the grain boundaries which would embrittle the metal. To further study the material, a mean-field rate theory model (MF-RTM) was created to simulate the radiation-induced segregation (RIS) of the alloy components Y, Ti, and O to the grain boundaries. Later, a kinetic Monte Carlo model (KMC) was made that replicated the results from the rate theory for the radiation induced segregation. Then the KMC model was modified to study the nano-oxide behavior in a range of different behaviors; the nano-oxide precipitation kinetics during heat treatment, resistance to dissolution under irradiation regimes similar to reactor conditions, and ability to trap He bubbles on the nano-oxide surfaces rather than the grain boundary. This KMC model is more complex than others as it includes 5 different atomic species (Fe, Y, Ti, O, and He) which migrate through three different mechanisms. Findings from the precipitation heat treatments were able to replicate the size, number density, and composition of nano-oxides from experiments and determined vacancy trapping at oxide interfaces was a significant for the NFA's coarsening resistance as opposed to interference from dislocations. In the irradiation simulations, the resistance of the nano-oxides to dissolution was confirmed and found the excess vacancy population plays an important role in healing the nano-oxides. He bubbles formed in the KMC simulations were found to preferentially form at the oxide interfaces, particularly the <111> interface, rather than the grain boundary and the characteristics of the He bubbles match expectations from literature. In the development of the KMC model, new insights into steady-state detection concepts were also found. A new type of steady-state detection (SSD) algorithm is described. Additionally, a method of forecasting the number of data points needed to make an accurate determination of steady-state, a 'predicting the pre-requisite to steady state detection' (ppSSD), is explored. / Doctor of Philosophy / Nuclear reactors need more radiation tolerant materials in the future, such as nanostructured ferritic alloys (NFA), used for nuclear fuel rod cladding, whose large amount of nanometer sized oxide particles contribute substantially to the radiation resistance of the metal overall. A mean-field rate theory method(MF-RTM) and a Kinetic Monte Carlo (KMC) computer model were made to study radiation induced segregation in the material. A more complex 5 element (Fe, Y, Ti, O, and He) KMC code was later developed to study the influence of the oxides at high temperatures and dose rates to gain insight into the causes the oxides remarkable thermal stability and resistance to irradiation. At all stages, the KMC model was able to replicate material behavior under high temperature heat treatment and irradiation. The model was used to simulate the formation of these oxides under different temperatures during their initial processing to gain more knowledge on how the oxide characteristics (size and number density) are influenced by temperature so we can tailor the processing method to achieve an ideal distribution of oxides in the material. Additionally, a mechanism for the oxides resistance to high temperature coarsening unrelated to the expected one caused by dislocations. The irradiation resistance of oxides to dissolution from irradiation was also investigated. While experimental measurements give a before and after picture of a material that underwent irradiation, the KMC can show the time evolution of the oxide size with increasing irradiation damage so the mechanisms behind the radiation resistance can be understood. The oxides remained stable at all temperatures and dose rates. Excess vacancies were found to play an important role in stabilizing the oxides against radiation damage. The KMC model also confirmed the ability of the oxides to trap transmutation He at the interfaces rather than the grain boundary and observed the process of He bubble nucleation. The He bubble form at the <111> oxide interface and they possess similar characteristics of He bubbles expected from literature. Additionally, a novel steady-state detection (SSD) algorithm was developed that can be used for long-term simulations and a method to determine how many data points the algorithm needs to accurately detect steady state is described here.

no abstract provided by author / Master of Science

In this work the infrared absorption of neutron irradiated silicon was compared to that of non-irradiated silicon at room and liquid nitrogen temperatures. It was found that instead of the 1.75 micron absorption band that has been mentioned in numerous papers transmission was completely cut off below about 2.5 microns at room temperature and about 1.8 microns at liquid nitrogen temperature. A weak absorption band was noted at 4.4 microns for all three samples at liquid nitrogen temperature and for the two irradiated samples at room temperature. Absorption due to free carriers decreased at the longer wavelengths (10-15 microns) with irradiation and cooling as was expected from past experiments. The resistivity of Si₄ increased from an assumed initial value of 10³ ohm-om to 1.89 X 10⁵ ohm-om. / Master of Science

This thesis examines the developmental neurotoxic effects of exposure to low-dose ionizing radiation (IR), alone or together with xenobiotics, during a critical period of neonatal brain development in mice. During mammalian brain development there is a period called the brain growth spurt (BGS), which involves extensive growth and maturation of the brain. It is known that neonatal exposure during the BGS to xenobiotics can have a negative impact on neonatal brain development, resulting in impaired cognitive function in the adult mouse. In humans, the BGS starts during the third trimester of pregnancy and continues for approximately 2 years in the child.   The present thesis has identified a defined critical period, during the BGS, when IR can induce developmental neurotoxicity in mice. The observed neurotoxicity was not dependent on sex or strain and manifested as altered neurobehaviour in the adult mouse. Furthermore, fractionated dose exposures appear to be as potent as a higher acute dose. The cholinergic system can be a target system for developmental neurotoxicity of IR, since alterations in adult mouse cholinergic system susceptibility were observed. Co-exposure to IR and nicotine exacerbated the behavioural disturbances and cholinergic system dysfunction. Furthermore, co-exposure with the environmental agent paraquat has indicated that the dopaminergic system can be a potential target.   In this thesis, clinically relevant doses of IR and a sedative/anesthetic agent (ketamine) were shown to interact and exacerbate defects in adult mouse neurobehaviour, learning and memory, following neonatal exposure, at doses where the single agents did not have any impact on the measured variables. This indicates a shift in the dose-response curve for IR, towards lower doses, if exposure occurs during the neonatal brain development. In addition, co-exposed mice, showing cognitive defects, expressed elevated levels of tau protein in the cerebral cortex. Furthermore, exacerbation of neurochemical deviations were observed following co-exposure compared to irradiation alone. Further investigations of neurotoxic effects following fractionated or acute low-dose IR, modelling the clinical situation during repeated CT scans or levels of radiation deposited in non-target tissue during radiotherapy, and possible interaction effects with xenobiotics, is of great importance in the field of radioprotection.

The overall purpose of this dissertation is to develop a multi-scale framework that can simulate radiation defect accumulation across a broad range of time and length scales in metals. In order to accurately describe defect accumulation in heterogeneous microstructures and under complex irradiation conditions, simulation methods are needed that can explicitly account for the effect of non-homogeneous microstructures on damage accumulation. In this dissertation, an advanced simulation tool called spatially resolved stochastic cluster dynamics (SRSCD) is developed for this purpose. The proposed approach relies on solving spatially resolved coupled rate equations of standard cluster dynamics methods in a kinetic Monte Carlo scheme. Large-scale simulations of radiation damage in polycrystalline materials are enabled through several improvements made to this method, including a pseudo-adaptive meshing scheme for cascade implantation and implementation of this method in a synchronous parallel kinetic Monte Carlo framework. The performance of the SRSCD framework developed in this dissertation is assessed by comparison to other simulation methods such as cluster dynamics and object kinetic Monte Carlo and experimental results including helium desorption from thin films and defect accumulation in neutron-irradiated bulk iron. The computational scaling of the parallel framework is also investigated for several test cases of irradiation conditions. SRSCD is next used to investigate radiation damage in three main types of microstructures, using α-iron as a test material: iron thin films, coarse-grained bulk iron, and nanocrystalline iron. SRSCD is used to investigate the mechanisms involved with defect accumulation in irradiated materials, such as effective diffusivity of helium in thin films and the effect of grain boundary sink strength on defect accumulation in nano-grained metals, and to predict defect populations in irradiated materials for comparison with experiments. Particular emphasis is placed on the role of microstructural features such as free surfaces and grain boundaries in influencing damage accumulation. Finally, the methodology developed in this dissertation is applied in the context of multiscale modeling and experimental design. To complete the multi-scale transition between defect-level behavior and macroscopic material property changes caused by irradiation, the relationship between mechanical loading and radiation damage is investigated. The impact of radiation damage on hardening of irradiated materials is investigated by using the results of SRSCD as inputs into polycrystalline crystal plasticity simulations. This is carried out in bulk iron by fitting hardening models to experimental data from neutron irradiation of iron and then used to predict hardening under irradiation conditions beyond what has already been accomplished in experimental studies. In addition, SRSCD is used to demonstrate the temperature shift required to achieve equivalent damage accumulation in irradiation conditions with significantly differing dose rates, such as in the case of using ion irradiation to simulate damage from neutron irradiation. In this dissertation, the development of SRSCD and its application in a multi-scale framework to predict macroscopic material property changes in metals represents a significant improvement over the state of the art due to improved simulations of defect accumulation and direct upscaling of results into polycrystalline plasticity models. The tools and understanding of defect behavior developed here will allow predictive modeling of metal degradation in reactor-relevant damage environments, including the defected microstructure and macroscopic material property changes due to irradiation.

The solid acid catalyst of the Keggin-type 12-tungstophosphoric acid (H3PW12O40, HPW) is supported on partially reduced graphene oxide (PRGO) nanosheets for acid-catalyzed reactions. HPW is a new class of catalyst with a good thermal stability and high Bronsted acidity in order to replace common mineral acids. However, it has low specific surface area (1-5 m2/g). Therefore, the possibility of PRGO as a catalytic support for HPW is investigated due to its high surface area (2630 m2/g) and good thermal stability. The synthesis of HPW-GO catalyst is prepared using microwave and laser irradiation without using any chemical reducing agents. The HPW-GO catalysts are characterized by Ultraviolet-visible spectroscopy (UV-Vis), Fourier Transform Infrared Spectroscopy (FT-IR), Raman Spectroscopy, X-ray Photoelectron Spectroscopy (XPS), X-ray Diffraction (XRD) techniques, and Transmission Electron Microscopy (TEM). Also, the surface acidity is measured by a non-aqueous titration of n-butyl amine. Furthermore, the application for catalysts is tested by three acid-catalyzed reactions: Esterification, Friedel-Crafts acylation, and Pechmann condensation. The greatest acidity for the microwave irradiation method is with the loading of 85 wt% HPW-GO and 60wt% HPW-GO for laser irradiation. The results observed provide an excellent opportunity for PRGO as a catalytic support for HPW for acid-catalyzed reactions.

Les matériaux de structure utilisés dans le cœur des REP, comme par exemple les aciers austénitiques ou bien les alliages de zirconium, sont soumis à la fois à une forte irradiation neutronique ainsi qu’à divers chargements mécaniques. A l’échelle macroscopique, le comportement mécanique sous irradiation de ces matériaux est bien caractérisé. Cependant, à l’échelle microscopique, les mécanismes de déformation sous irradiation restent encore mal connus. De nombreux mécanismes de fluage d’irradiation ont été envisagés du point de vue théorique mais les données expérimentales existantes n’ont pu, pour l’heure, permettre de déterminer le mécanisme pertinent contrôlant la déformation.L'objectif de ce travail de thèse est justement d’apporter une contribution à la compréhension des mécanismes de fluage d’irradiation des métaux et alliages par la mise en œuvre d’une méthode expérimentale originale. Les irradiations sont reproduites par des irradiations aux ions lourds. Ces irradiations ont l’avantage de créer un dommage rapide sans activer la matière. Cependant l’épaisseur irradiée n’est que de plusieurs centaines de nanomètres. De telles épaisseurs nécessitent un dispositif expérimental spécifique pour l’application d’une charge sur l’échantillon. Le dispositif utilisé est basé sur l’utilisation de contraintes internes dans un film mince de nitrure de silicium pour déformer des films minces métalliques. Cette méthode a été conçue et développée par les équipes de Thomas Pardoen et Jean-Pierre Raskin à l’université catholique de Louvain, en Belgique.Après une démonstration de la faisabilité de l’étude et une adaptation du dispositif aux conditions d’irradiation, cette méthode a pu être utilisée avec succès pour reproduire une expérience de fluage d’irradiation à température ambiante sur un matériau modèle, le cuivre. Une loi de fluage en puissance 5 selon la contrainte a été trouvée sous irradiation sur des films de 200 et 500 nm d’épaisseur. Les observations au microscope électronique à balayage et en transmission suggèrent que les mécanismes de déformation reposent sur le glissement assisté par la montée.Cette loi apparait indépendante de la microstructure et de l’historique de chargement des éprouvettes. La montée, si elle intervient, ne semble pas contrôlée par des mécanismes de diffusion à longue distance mais par des interactions directes entre la cascade déplacements et les dislocations.Hors irradiation et après irradiation, le comportement mécanique des films a également pu être évalué. Les mécanismes de déformation semblent identiques dans les deux conditions. A vitesse de déformation modérée, la déformation est contrôlée par le glissement intragrannulaire des dislocations tandis qu’à basse vitesse un changement de mécanisme se produit. Le nouveau mécanisme reste toujours basé sur les dislocations mais une composante de glissement aux joints de grains semble apparaitre. Un durcissement post irradiation est observé du fait d’une densité importante de SFT dans les éprouvettes irradiées qui agissent comme des obstacles au glissement des dislocations / Structural materials used in the PWR cores, such as austenitic stainless steels or zirconium alloys, are exposed to a significant neutron flux and, at the same time, a stress from various mechanical loadings. At the macroscopic scale, the mechanical behavior under irradiation is well characterized. However, at a microscopic scale, the deformation mechanisms under irradiation still remain unknown. Many irradiation creep mechanisms have been proposed from a theoretical point of view but the available experimental data have not, for now, permitted to identify the relevant mechanism leading to the deformation.The objective of this thesis is precisely to improve our understanding of the irradiation creep mechanisms of metals and alloys by the development of a novel experimental method. In this method, the irradiation is produced by the use of heavy ions. This kind of irradiation has the advantage of a fast damage rate without an activation of the material. However the irradiated area is confined in a few hundreds of nanometers. Such thickness requires a specific experimental device to apply a stress on the specimen. This device is based on the release of internal stress in a silicon nitride film to deform a metallic thin film. This method was designed and developed at the Université Catholique de Louvain in Belgium by the teams of Thomas Pardoen and Jean-Pierre Raskin.After proving the feasibility of the study and adapting the device to the irradiation environment, the method has been used with success to reproduce an irradiation creep experiment at room temperature on a model material : copper. A single creep power law with a stress exponent of 5 has been found under irradiation on 200 and 500 nm thick films. The SEM and TEM observations suggest that the deformation mechanism rely on the glide of dislocations assisted by climb.This law seems to be independent of the microstructure and the loading history. The dislocation climb, if it occurs, would not be controlled by diffusion process at long distance but by direct interaction between displacement cascades and dislocations.The mechanical behavior of unirradiated and irradiated copper films have also been assessed. The deformation mechanisms seem to be the same in both cases. At a moderate strain rate, the deformation is controlled by the intragrannular glide of dislocations whereas at slow strain rate a change of mechanism takes place. The new mechanism still remains based on dislocations but a component of grain boundary sliding may appear. A post irradiation hardening has been observed on a 200 nm thick film due to the presence, in the irradiated samples, of a high density of SFT which act as obstacles against dislocation glide

Les dommages de l’ADN interfèrent avec sa réplication et sa transcription. Ils sont en général éliminés par des mécanismes de réparation, en particulier par la réparation par excision de nucléotides (NER). Ils peuvent également être tolérés grâce à la synthèse translésionnelle (TLS). Au cours de mon travail de thèse, nous avons étudié l’implication de la voie NER et de l’ADN polymérase η (Polη) associée à la TLS dans la réponse aux lésions de l’ADN induites par les rayons ultraviolet (UV) et par une drogue chimiothérapeutique, la doxorubicine. Les principales lésions induites par les rayons UV sont les dimères de pyrimidine cyclobutane (CPDs) et les pyrimidines (6-4) pyrimidones (6-4PPs) qui sont éliminées par la NER. Les données obtenues sur la formation de régions d’ADN simple brin et celles du cycle cellulaire suggèrent que les lésions 6-4PPs sont tolérées par un mécanisme de réparation post-réplicative dans des cellules XP-C déficientes en NER (xeroderma pigmentosum du groupe C). Dans un second temps, mon objectif a été de déterminer la contribution de Polη dans la prise en charge des lésions induites par les rayons UV dans les cellules XP-C. En effet, il est connu que Polη est responsable de la réplication des CPDs, mais l’absence de Polη dans des cellules proficientes en NER ne les rend pas hypersensibles aux rayons UV. De plus, il a été suggéré que Polη soit impliquée dans la TLS des 6-4PPs. En réprimant par shARN l’expression du gène codant Polη dans les cellules XP-C, j’ai réussi à établir la première lignée stable de fibroblastes humains déficients à la fois en NER et en Polη (XP-C/PolηKD). Cette réduction fonctionnelle de l’expression de Polη dans les cellules XP-C irradiées à faible dose d’UV a entraîné un arrêt irréversible du cycle cellulaire, la génération de cassures simple- et double-brin de l’ADN et une mortalité cellulaire significative. Ces résultats montrent un rôle crucial de Polη dans la survie des cellules déficientes en NER après irradiation UV et suggèrent que Polη puisse participer aussi à la TLS des 6-4PPs.Par ailleurs, nous avons montré que les cellules déficientes en NER ou en Polη ont été sensibilisées par un traitement à la doxorubicine indiquant que la NER et Polη participent également de la prise en charge des lésions induites par cet agent. Donc au cours de mon travail de thèse, j’ai mis en évidence des interconnexions complexes entre Polη et la voie NER en réponses à différents agents génotoxiques. / DNA damages interfere with replication and transcription. They are normally eliminated by repair mechanisms, such as nucleotide excision repair (NER). They can also be tolerated by translesion DNA synthesis (TLS). During my PhD work, we studied the involvement of NER pathway and DNA polymerase η (Polη) associated with TLS in response to DNA damages induced by ultraviolet (UV) and a chemotherapeutic drug, doxorubicin.The main lesions induced by UV irradiation are cyclobutane pyrimidine dimers (CPDs) and pyrimidine (6-4) pyrimidones (6-4PPs) which are removed by NER. Data on the formation of single-stranded DNA regions and those of the cell cycle suggest that 6-4PPs lesions are tolerated by a post-replication repair mechanism in XP-C cells (xeroderma pigmentosum group C, deficient in NER). In a second time, my goal was to determine the contribution of Polη in the tolerance of lesions induced by UV in XP-C cells. Indeed, it is known that Polη is responsible for the replication of CPDs, but in the absence of Polη, NER-proficient cells are not hypersensitive to UV rays. In addition, it was suggested that Polη is also involved in the TLS of 6-4PPs. By knocking down (KD) the expression of the gene encoding Polη in XP-C cells with a shRNA, we established the first stable line of human fibroblasts deficient in both NER and Polη (XP-C/PolηKD). This functional reduction in the expression of Polη in XP-C cells irradiated with low UVC dose resulted in an irreversible cell cycle arrest, the generation of single- and double-strand DNA breaks and significant cell death. These data demonstrate a crucial role for Polη in the survival of NER-deficient cells after UV irradiation and suggest that Polη can also participate in the TLS of 6-4PPs.In addition, we showed that cells deficient in NER or Polη are sensitized by treatment with doxorubicin indicating that NER and Polη also participate in the response of DNA damages induced by this agent.In conclusion, during my PhD work, we highlighted the complex interconnections between Polη and NER pathway in response to different genotoxic agents. / Os danos do DNA interferem com a sua replicação e transcrição. Eles são normalmente removidos por mecanismos de reparo, como o reparo por excisão de nucleotídeos (NER). Lesões não removidas também podem ser toleradas por processos específicos de síntese de translesão (TLS). Durante este trabalho de tese, estudamos a implicação da via NER e da DNA polimerase η (Polη), associada à TLS, na resposta aos danos no DNA provocados pela irradiação ultravioleta (UV) e por um agente quimioterápico, a doxorrubicina.As principais lesões provocadas pela luz UV são os dímeros de pirimidina ciclobutano (CPDs) e as pirimidinas (6-4) pirimidonas (6-4PPs) que são removidas pelo NER. Os resultados obtidos sobre a formação de regiões de DNA simples fita e os dados de ciclo celular indicam que as lesões 6-4PPs são toleradas por un mecanismo de reparo pós-replicativo em células XP-C deficientes em NER (xeroderma pigmentosum do grupo C). Em seguida, buscamos determinar a contribuição da Polη na tolerância de lesões UV em células XP-C. De fato, é conhecido que a Polη é responsável pela replicação dos CPDs, porém a ausência dessa em células proficientes em NER não as torna hypersensíveis à irradiação UV. Além disso, foi sugerido que Polη poderia estar envolvida na TLS dos 6-4PPs. A expressão do gene POLH, que codifica Polη, foi silenciada através de shRNA em células XP-C, sendo assim estabelecida a primeira linhagem estável de fibroblastos humanos deficientes em ambas proteínas XPC e Polη. Essa redução funcional da expressão de Polη em células XP-C provocou, em células irradiadas com doses baixas de luz UV, uma parada irreversível no ciclo celular, a formação de quebras no DNA (incluindo quebras simples e dupla fita) e morte celular. Esses resultados revelam um papel crucial da Polη na sobrevida das células deficientes em NER após irradiação UV e sugerem que Polη possa também participar da TLS de lesões tipo 6-4PP.Por outro lado, participei de trabalho no qual demonstramos que células deficientes em NER ou em Polη são sensibilizadas pelo tratamento com doxorrubicina, o que indica que o NER e a Polη participam da resposta aos danos induzidos por esse agente.Em conclusão, ao longo do meu trabalho de tese, eu coloquei em evidência interconexões complexas entre a Polη e o NER em resposta a diferentes agentes genotóxicos.

L’irradiation cérébrale thérapeutique comporte un risque de neurotoxicité tardive irréversible en partie lié à l’effet de l’irradiation sur le compartiment vasculaire cérébrale. Les péricytes et les communications entre les péricytes et les cellules endothéliales jouent un rôle majeur dans la stabilisation des vaisseaux, dans la formation et la régulation de la barrière hématoencéphalique et dans le contrôle du flux sanguin cérébral. Nous montrons, dans un modèle murin d’irradiation cérébrale, que les péricytes sont une cible précoce de l’irradiation cérébrale. Après irradiation, la morphologie des péricytes est modifiée et des marqueurs d’activations du péricytes sont surexprimés. En conséquence, la communication entre péricyte et cellule endothéliale est rompue, ce qui se traduit par une diminution de la capacité du péricyte à induire une constriction vasculaire après stimulation électrique. De façon concomitante, la perméabilité de la barrière hémato-encéphalique est anormalement augmentée après irradiation. Un traitement par thalidomide, administré dans la semaine précédant et suivant l’irradiation, prévient les conséquences de l’irradiation sur les péricytes. Les communications entre péricytes et cellules endothéliales sont maintenues ainsi que les fonctions contractiles des péricytes. L’imperméabilité de la barrière hématoencéphalique est également préservée. La voie de signalisation PDGF-β/PDGFR-β essentielle au recrutement des péricytes par les cellules endothéliales, est, au moins partiellement, impliquée dans l’effet protecteur de la thalidomide. Des études supplémentaires sont nécessaires pour définir les mécanismes sous tendant l’effet de l’irradiation sur les péricytes ainsi que l’effet protecteur de la thalidomide. Nous avons en parallèle mis au point un modèle murin de lymphome cérébral luciférase positif pour vérifier, dans un premier temps, l’innocuité de l’association de la radiothérapie et de la thalidomide et de ses dérivés de la classe des immunomodulateurs (iMids), le lénalidomide et le pomalidomide. Ces trois molécules ne diminuent pas l’effet antitumoral de la radiothérapie, mais l’association de radiothérapie et de pomalidomide est synergique sur la décroissance tumorale mesurée par l’évolution des courbes de bioluminescence. Le concept de normalisation de la vascularisation tumorale fait référence aux molécules capables, non pas de faire régresser les vaisseaux tumoraux anormaux, mais de les « normaliser » pour améliorer, d’une part, la disponibilité des chimiothérapies au sein de la tumeur, et d’autre part, l’oxygénation tumorale pour accroitre l’efficacité de la radiothérapie. Nos résultats sont en faveur d’un tel effet exercé par le pomalidomide dans notre modèle murin de lymphome cérébral, caractérisé par une infiltration tumorale périvasculaire, une fuite capillaire mais sans néo angiogenèse. Nos travaux fournissent un rationnel biologique à de futurs essais cliniques avec les iMids dans le traitement des lymphomes cérébraux primitifs voire des tumeurs malignes cérébrales. / Therapeutic brain irradiation carries a risk of irreversible delayed neurotoxicity partly due to the effect of irradiation on the cerebral vascular compartment. Pericytes and communication between pericytes and endothelial cells play a major role in vessel stabilization in the formation and regulation of the blood-brain barrier and in the control of cerebral blood flow. We show in a murine model of brain irradiation, that pericytes are a target of early brain irradiation. After irradiation, the morphology of pericytes is altered and markers of activation of pericytes are overexpressed. Consequently, communication between the endothelial cell and pericyte is disrupted , which results in a decreased capacity of pericytes for inducing a vascular constriction after electrical stimulation. Concomitantly, the permeability of the blood - brain barrier is abnormally increased after irradiation. Treatment with thalidomide administered in the week before and after irradiation, prevents the effects of irradiation on pericytes . Communication between pericytes and endothelial cells are maintained as well as the contractile properties of pericytes. The impermeability of the blood brain barrier is also preserved. The PDGF-β/PDGFR-β signaling pathway, which is essential for the recruitment of pericytes by endothelial cells, is at least partially involved in the protective effect of thalidomide. Further studies are needed to define the mechanisms underlying the effect of irradiation on the pericytes and the protective effect of thalidomide. We have, in parallel, developed a model of murine luciferase positive CNS lymphoma to verify first, the safety of the combination of radiotherapy and thalidomide and its derivatives of the class of immunomodulators ( IMiDs ), lenalidomide and pomalidomide. These three molecules do not decrease the antitumor effect of radiotherapy, but the antitumoral effect of the association of radiotherapy and pomalidomide is synergistic. The concept of the normalization of the tumor vascularization refers to molecules capable not to induce regression of the abnormal tumor vessels but to "normalize" the tumoral vasculature in order to improve, on one hand , the availability of chemotherapy in the tumor , and on the other hand, the tumor oxygenation to increase the effectiveness of radiotherapy. Our results are in favor of such an effect exerted by pomalidomide in our murine model of cerebral lymphoma, characterized by perivascular tumor infiltration and capillary leak .Our work provide a biological rational for future clinical trials with IMiDs in the treatment of brain lymphomas or malignant brain tumors.

Ce travail de thèse s’intéresse à l’altération des verres nucléaires, et plus précisément à la durabilité du verre de référence SON68, dans un système complexe simulant les conditions du stockage géologique profond. L’approche repose sur une complexification progressive du système afin de mieux comprendre les mécanismes régissant l’altération du verre irradiant au contact de l’eau du site (eau du Callovo-Oxfordien) et en présence de fer simulant le surconteneur. Dans un premier temps, l’étude se focalise sur l’effet de l’eau souterraine sur l’altération du verre de référence non radioactif dans le régime de vitesse résiduelle à 70°C. Les résultats montrent que le magnésium présent dans l’eau contribue, au-dessus d’un pH seuil, à former des phyllosilicates magnésiens au détriment du gel passivant, ce qui induit une augmentation de l’altération du verre. Cette étude confirme des travaux antérieurs et apportent de nouvelles données à 70°C. Par la suite, une source de fer est introduite dans le système (verre non radioactif – eau du COx) afin de simuler la présence du surconteneur. Les expériences sont menées en milieu anoxique sur des monolithes de verre et de fer, mis en regard et séparés d’environ 80 µm, puis immergés dans l’eau du COx à 70 et 90 °C. Dans ces conditions, il est observé que la température n’induit qu’un faible impact sur les cinétiques et les réactions qui contrôlent l’altération du verre. La corrosion du fer conduit principalement à la précipitation de sidérite (carbonate de fer au degré d’oxydation II) et d’aragonite (carbonate de calcium). Par ailleurs, une altération du verre plus importante en présence de fer est observée. La cause la plus probable est la précipitation de silicates de fer, qui, comme les silicates magnésiens, se forment au détriment du gel passivant. Ces phases ont été identifiées principalement au degré d’oxydation III, indiquant ainsi une oxydation du fer proche du verre. Dans ce cas, la précipitation de silicates magnésiens est inhibée et seuls des silicates de fer précipitent. Enfin, l’influence de l’irradiation sur le comportement du verre a été étudiée. La radiolyse de l’eau devant produire des espèces oxydantes comme H2O2 à l’interface verre/eau, une première étude s’est focalisée sur l’altération du verre dans l’eau du COx en présence de H2O2 dans le régime de vitesse résiduelle. Les résultats montrent que la décomposition de cette espèce à la surface des grains de verre semble avoir un impact local en favorisant la précipitation de silicates magnésiens et, par conséquent, en augmentant l’altération du verre. Cet effet est immédiat et ne se produit que très localement sur les grains en surface du réacteur. Mais, globalement, les données montrent que cette espèce n’a pas un impact significatif sur l’altération du verre dans le régime cinétique résiduel et pour la géométrie considérée. Ce travail s’achève par la réalisation de deux expériences d’altération d’un verre radioactif, dopé en 238Pu, et altéré dans l’eau du COx à 70°C en présence de fer, en suivant une géométrie similaire à celle conduite sur le verre non radioactif. Les caractéristiques du verre permettent de s’intéresser à l’effet du débit de dose α. Par rapport aux témoins non radioactifs, une plus forte oxydation du fer est mise en évidence, avec principalement des précipités de goethite et de ferrihydrite, oxydes de fer au degré d’oxydation III. Cette précipitation de phases oxydées peut s’expliquer par la réaction entre H2O2 et Fe qui favoriserait l’oxydation du Fe2+ en Fe3+. Sur la base des analyses de solution et des premières observations par MEB, il semble que les épaisseurs de verre altéré soient globalement similaires en présence d’un champ d’irradiation  et dans le milieu non radioactif témoin. Néanmoins, des caractérisations complémentaires du solide devront être réalisées afin de mieux comprendre les processus limitants. / This work intends to provide a better understanding of the alteration of R7T7-type nuclear waste glass in a complex environment such as the deep geological repository. This approach aims to progressively complexify the glass leaching environment in order to better understand the mechanisms involved on the alteration of a radioactive glass in contact with the Callovo-Oxfordian groundwater (COx groundwater) and an iron source, simulating the glass carbon steel overpack. First, the study focusses on the impact of groundwater on the glass alteration under the residual rate regime at 70°C. Results show that magnesium present in the Callovo-Oxfordian groundwater contributes, over a pH threshold, to the precipitation of magnesium phyllosilicates consuming the passivating gel and thus increasing the glass alteration. This work confirms previous studies and brings new data at 70 °C. Thereafter, an iron source was introduced in the leaching environment (glass – COx groundwater) in order to simulate the carbon steel overpack. The experiments were performed in an anoxic environment with a glass monolith and an iron foil, facing each other with an 80 µm gap, and then immerged in the COx groundwater at 70 and 90 °C. On these conditions, a weak impact of the temperature was perceived on the kinetics and the reactions controlling glass alteration. The iron corrosion led mainly to the precipitation of siderite (an Fe2+-carbonate) and aragonite (a calcium carbonate). Furthermore, an increase of glass alteration was observed while using an iron foil. The main cause explaining this phenomenon is the formation of iron silicates, as seen with magnesium silicates, precipitating at the expense of the passivating gel. These phases were identified mainly at the oxidation state III, indicating an iron oxidation near the glass. It should be noted that in this case, magnesium precipitation is suppressed and only iron silicates precipitate. Finally, the influence of irradiation on glass alteration was studied. Water radiolysis induces the production of oxidizing species such as H2O2 at the glass/water interface. Therefore, a first study focused on glass alteration in the COx groundwater in the presence of H2O2 under the residual rate regime. Results showed that this specie decomposition was higher at the surface of the glass grains and seemed to have a very local impact, favouring the magnesium silicate precipitation and the enhancement of glass alteration. This prompt effect was only observed locally on grains at the surface of the reactor. However, globally, the data showed that H2O2 does not have a significant impact on glass alteration in this residual rate regime and this geometry. At last, this work came to experiments using a radioactive glass, doped with 238Pu, altered in the COx groundwater at 70 °C in the presence of an iron source, and using the same geometry than the one conducted with the non-radioactive glass. The glass characteristics allowed us to focus only on the α-dose rate effect. Comparing with the non-radioactive reference, a higher iron oxidation was noticed, with the precipitation of iron oxides at the oxidation state III, such as goethite and ferrihydrite. This can be explained by the reaction between H2O2 and iron, favouring the oxidation of Fe2+ to Fe3+. From solution analysis and the first SEM observations, it seems that globally, the glass alteration thickness is the same regardless the α-irradiation field. Nevertheless, supplementary data on solid characterisations must be performed in order to understand and be conclusive about the mechanisms involved on the glass alteration mechanisms under these conditions.