Academic literature on the topic 'Oxydes de plutonium – Synthèse (chimie)'
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Journal articles on the topic "Oxydes de plutonium – Synthèse (chimie)":
Agbodan, Kokou Agbékonyi, Oudjaniyobi Simalou, Gneiny Whad Tchani, and Koffi Jondo. "Etude de l’influence de la basicité sur l’enthalpie de réaction des sels N-méthoxycarbonyl-(oxy)-pyridiniums." International Journal of Biological and Chemical Sciences 14, no. 4 (August 17, 2020): 1489–98. http://dx.doi.org/10.4314/ijbcs.v14i4.26.
Dissertations / Theses on the topic "Oxydes de plutonium – Synthèse (chimie)":
Bardelle, Philippe. "Synthèse du mononitrure mixte d'uranium-plutonium par réduction des oxydes /." Saclay : Commissariat à l'énergie atomique, 1989. http://catalogue.bnf.fr/ark:/12148/cb351007303.
Vigier, Jean-François. "Synthèse d’oxydes d’actinides en milieu chlorure fondu : études structurales et mécanismes réactionnels." Electronic Thesis or Diss., Lille 1, 2012. http://www.theses.fr/2012LIL10051.
The study developed in this thesis concerns actinide oxides synthesis for nuclear fuel refabrication, and more specifically, the actinide (III) precipitation in molten salt LiCl-CaCl2 (30-70%mol) salt at 700°C using wet argon sparging. First, this conversion method is described for neodymium (III) and cerium (III) coconversion. The conversion rates are around 99.9%, and the obtained powders contain mixed oxychloride Ce1-xNdxOCl as main component, with a small amount of mixed oxide Ce1-xNdxO2-0.5x for the high cerium ratio. A second oxychloride CeIV(Nd0.7Ce0.3)IIIO3Cl is obtained in specific conditions and in very low quantity. The structure of this oxychloride is described in this study. The partially oxidative property of the conversion method induces the oxidation of a part of cerium (III) to oxidation state (IV). In the case of uranium (III) conversion by wet argon sparging, all the uranium is oxidized and give the oxide UO2 as single compound. The conversion rate for this element is over 99.9% in the molten chloride, but significant amount of uranium is lost by volatilization during the conversion. Finally, the U(III) and Pu(III) coconversion study shows the highest precipitation sensitivity of uranium (III) in comparison with plutonium (III), responsible of a successive conversion of the two elements, giving an oxide mixture of UO2 et PuO2 with quantitative conversion rate. Surprisingly, the conversion of Pu(III) in the same conditions led to a mixture of PuO2 and PuOCl, characteristic of a partial oxidation from Pu (III) to Pu (IV), in contrast with coconversion of U(III)-Pu(III)
Vigier, Jean-François. "Synthèse d’oxydes d’actinides en milieu chlorure fondu : études structurales et mécanismes réactionnels." Thesis, Lille 1, 2012. http://www.theses.fr/2012LIL10051/document.
The study developed in this thesis concerns actinide oxides synthesis for nuclear fuel refabrication, and more specifically, the actinide (III) precipitation in molten salt LiCl-CaCl2 (30-70%mol) salt at 700°C using wet argon sparging. First, this conversion method is described for neodymium (III) and cerium (III) coconversion. The conversion rates are around 99.9%, and the obtained powders contain mixed oxychloride Ce1-xNdxOCl as main component, with a small amount of mixed oxide Ce1-xNdxO2-0.5x for the high cerium ratio. A second oxychloride CeIV(Nd0.7Ce0.3)IIIO3Cl is obtained in specific conditions and in very low quantity. The structure of this oxychloride is described in this study. The partially oxidative property of the conversion method induces the oxidation of a part of cerium (III) to oxidation state (IV). In the case of uranium (III) conversion by wet argon sparging, all the uranium is oxidized and give the oxide UO2 as single compound. The conversion rate for this element is over 99.9% in the molten chloride, but significant amount of uranium is lost by volatilization during the conversion. Finally, the U(III) and Pu(III) coconversion study shows the highest precipitation sensitivity of uranium (III) in comparison with plutonium (III), responsible of a successive conversion of the two elements, giving an oxide mixture of UO2 et PuO2 with quantitative conversion rate. Surprisingly, the conversion of Pu(III) in the same conditions led to a mixture of PuO2 and PuOCl, characteristic of a partial oxidation from Pu (III) to Pu (IV), in contrast with coconversion of U(III)-Pu(III)
Bardelle, Philippe. "Synthèse du mononitrure mixte d'uranium-plutonium par réduction des oxydes." Aix-Marseille 3, 1988. http://www.theses.fr/1988AIX30049.
Hibert, Nicolas. "Synthèse et caractérisation structurale des complexes de plutonium à base de peroxyde." Thesis, Lille, 2020. http://www.theses.fr/2020LILUR054.
In the framework of the improvement of the reused nuclear fuel manufacturing and the Pu multirecycling, U-Pu coconversion represent a potential alternative to the current mixing process of uranium and plutonium oxide powders. Compared to carbon-based U-Pu coconversion processes, the peroxide process has the advantage of, among others, leading to the absence of residual carbon in oxide powder. However, the current knowledge of plutonium peroxide is incomplete and scattered, hindering the plutonium conversion and U-Pu coconversion technological developments. Thus, the evaluation of the feasibility of this process requires a preliminary strengthening of the knowledge of plutonium peroxide physico-chemical properties. The first part of this work has been dedicated to the characterization of plutonium peroxide soluble complexes and salts. Molar extinction coefficient of soluble complexes have been estimated in order to quantify the plutonium loss in precipitation experiments. The experimental conditions enabling very high yield of precipitation of Pu and an easy-filterable powder have been determined. Moreover, a new database of plutonium peroxide salt properties has been established from the characterizations obtained. In the second part, syntheses carried out with mixed systems such as U-Pu and U-Th have led to obtaining a mix of uranyl peroxide and +IV actinide peroxide salt. The experimental conditions enabling very high yields for uranium and for plutonium and an easy-filterable powder have been determined. Then, thermal treatment of the precipitate has led to obtaining an oxide powder with a good ability to the manufacturing of sintered oxide pellet and which enables to demonstrate the feasibility of U-Pu conversion process at the laboratory scale
Legrand, Olivier. "Nouveaux oxydes d'ortho-hydroxyarylphosphines chiraux, synthèse et applications en catalyse asymétrique." Aix-Marseille 3, 1999. http://www.theses.fr/1999AIX30046.
Fournier, Sabine. "Etude de la dissolution des oxydes mixtes (U,Pu)O2 à forte teneur en plutonium." Montpellier 2, 2000. http://www.theses.fr/2000MON20203.
Xin, Baowei. "De la chimie douce, au milieu hydrothermal étendu au domaine supercritique, du réacteur fermé au dispositif en continu : synthèse d'oxydes métalliques nanostructurés." Dijon, 2005. http://www.theses.fr/2005DIJOS015.
Estevenon, Paul. "Synthèse et caractérisation de silicates MSiO4 (M = Ce, Th, U, Np, Pu)." Thesis, Montpellier, Ecole nationale supérieure de chimie, 2018. http://www.theses.fr/2018ENCM0013/document.
Actinides, and mainly plutonium, are the main contributors to the long-term radiotoxicity of spent nuclear fuel. In conditions representative for geological repository, the interactions between such radioelements and silicate species could influence the mobility of the actinides in the environment and thus, could affect the safety of the storage facilities. Especially, the formation of actinide silicate, AnSiO4, has to be considered carefully, since thorium and uranium silicate are ubiquitous in environmental silicate rich media and under reductive conditions. Because the chemistry of AnSiO4 is poorly known, their preparation is a prerequisite in order to determine thermodynamic data associated to their formation and to evaluate their stability under geological repository conditions.The first part of this work consisted in the preparation, under hydrothermal conditions, of ThSiO4, USiO4 and CeSiO4 as surrogates of PuSiO4. This study allowed us to determine the preponderant parameters which impact the formation of silicate phases, to establish optimized conditions for their synthesis as pure phases and then to propose potential mechanisms of formation. For all of these syntheses, the competition between the complexation of metal cations by silicate ions and their hydrolysis played a predominant role. Three different and efficient strategies have been identified for the formation of actinide silicates. The first one was characterized by the use of weakly acid reactive media to limit the hydrolysis of actinide in solution. The second involved the use of strong ligands to maintain the actinide in solution in weakly basic media. The third was developed with element oxidation states that also protected it against hydrolysis. The transposition of these strategies to the preparation of PuSiO4 allowed to determine the suitable synthesis conditions to form PuSiO4 and then to identify the differences in terms of reactivity between Pu(IV) and surrogate elements
Boyer, Jérémie. "Indolone-1 oxydes 2-substituées : synthèse et capacité de piégeage de radicaux." Toulouse 3, 2004. http://www.theses.fr/2004TOU30014.
Nitrone compounds have been the subject of many developments since the discovery of their capacity to trap free radicals. This property of spin trapping coupled with electron paramagnetic resonance (EPR) analysis made it possible to highlight many redox mechanisms in chemistry and in biology. This memoir describes the synthesis and the radical trapping properties of a series of nitrones, the indolone-1-oxides. These indolone-1-oxides were synthesized in two different ways both starting from an arylaldehyde substituted by a nitro group in the ortho position. A series of eight compounds was obtained and tested for their capacities to trap free radicals. The spin trapping experiments were carried out initially by EPR on this series by testing various free radicals (hetero- or carbon-centered). The study made it possible to determine the capacity of indolone-1-oxides to trap various types of radicals giving particularly stable nitroxide adducts. Two of these nitrones spontaneously yielded nitroxide adducts in solution. The trapping properties were then evaluated by indirect methods measuring the capacity of the nitrones to protect or to delay the degradation of a molecular probe by radical attack. The first method evaluated the capacity of nitrones to inhibit the bleaching of b-carotene caused by lipoperoxyl radical attack in lipophilic medium. The second method followed the inhibition of the fluorescence decay of fluorescein undergoing radical attack initiated by 2,2'-azobis(2-amidinopropane)dihydrochloride (AAPH) in hydrophilic medium. The various methods used in this work show that the indolone-1-oxide series has, at very low concentrations, very good free radical trapping capacities. These nitrones will thus make good molecular tools for the study of redox mechanisms in biological systems