53 research outputs found

    Sticker Art Shapes Henri Matisse

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    Sticker Seni Bentuk Henri Matisse. Temukan karya Henri Matisse melalui buku stiker yang menarik. Baca tentang riwayat hidupnya dan kemudian mengeksplorasi enam lukisannya, melihat karya asli dan kemudian mencoba buat versi Anda sendiri di halaman oppsite. Dengan mengatur stiker yang dapat digunakan kembali, Anda dapat bereksperimen dengan warna, bentuk dan chomposition untuk menciptakan asli atau menghasilkan karya individu Anda sendiri dan maasterpiece yang mengejutkan

    Analyse thermique de la stabilité d'oxydes d'uranium et de leurs réactions avec des fluorures alcalins

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    ORSAY-PARIS 11-BU Sciences (914712101) / SudocSudocFranceF

    Electrochemical behavior of iodide ions in molten fluoride salts

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    International audienceThe electrochemical behavior of iodide ions has been studied in the ternary fluoride salt, LiF-NaF-KF and in the binary salts, LiF-CaF2 and LiF-ThF4. The electrochemical study demonstrated that iodide ions are oxidized to produce gaseous species in the three molten fluoride salts. However, the stability of iodide ions was observed to be influenced by the fluroacidity of the molten salt. The efficiency of the extraction of iodide ions was examined in LiF-NaF-KF and LiF-ThF4. UV-visible spectroscopy was used to quantify the amount of iodide ions oxidized after the execution of several coulometries at applied potential, these coulometries simulated the fluorination step in the reprocessing unit designed for the MSFR. The efficiency of extraction determined in LiF-ThF4 is higher than 95 % while it is close to 64 % in LiF-NaF-KF at 650°

    Pyrochemical reprocessing of molten salt fast reactor fuel: focus on the reductive extraction step

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    The nuclear fuel reprocessing is a prerequisite for nuclear energy to be a clean and sustainable energy. In the case of the molten salt reactor containing a liquid fuel, pyrometallurgical way is an obvious way. The method for treatment of the liquid fuel is divided into two parts. In-situ injection of helium gas into the fuel leads to extract the gaseous fission products and a part of the noble metals. The second part of the reprocessing is performed by ‘batch’. It aims to recover the fissile material and to separate the minor actinides from fission products. The reprocessing involves several chemical steps based on redox and acido-basic properties of the various elements contained in the fuel salt. One challenge is to perform a selective extraction of actinides and lanthanides in spent liquid fuel. Extraction of actinides and lanthanides are successively performed by a reductive extraction in liquid bismuth pool containing metallic lithium as a reductive reagent. The objective of this paper is to give a description of the several steps of the reprocessing retained for the molten salt fast reactor (MSFR) concept and to present the initial results obtained for the reductive extraction experiments realized in static conditions by contacting LiF-ThF4-UF4-NdF3 with a lab-made Bi-Li pool and for which extraction efficiencies of 0.7% for neodymium and 14.0% for uranium were measured. It was concluded that in static conditions, the extraction is governed by a kinetic limitation and not by the thermodynamic equilibrium

    Extraction du zirconium dans le réacteur à sels fondus

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    International audienceThe Molten Salt Fast Reactor is a GEN IV reactor which uses a liquid fuel salt constituted of a mixture of fluoride salts: LiF-ThF4-UF4 (77.5-18.5-4 mol%). The working temperature is close to 650°C. The design of MSFR integrates a continuous reprocessing in order to prevent the precipitation of insoluble compounds (fluorides, oxides and oxy-fluorides). In the previous European project EVOL, a reprocessing scheme has been recommended to treat the liquid fuel of the Molten Salt Fast Reactor but this reprocessing scheme do not propose any option to remove zirconium fluoride from the salt whereas this element is one of the more important produced in the core. The aim of this paper is to present the chemical behavior of zirconium in the fuel salt. The thermodynamic stability diagram of zirconium in a fluoride salt is calculated from the thermochemical data of pure compounds. This diagram shows two stable soluble compounds of zirconium, ZrF2 and ZrF4. On the contrary, the experimental study evidences that only ZrF4 is stable in the salt, probably due to the low activity coefficients of zirconium fluoride which was determined equal to-4.33. The reduction of ZrF4 to Zr metal occurs at a potential of 0.377 V against the potential ThF4/Th which constitutes the limit of the electroactivity range of the fuel salt. Then, the electrochemical reduction on solid cathode is retained to perform Zr extraction from the salt

    Blood purification after orellanine intoxication with Cortinarius orellanus

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    International audienc

    Laboratory confirmation of Cortinarius poisoning

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    International audienceDeliberate poisoning with Cortinarius orellanus. Identification of orellanine in renal biopsy ten days and 6 months after the toxic mushroom ingestio

    Intoxication by Cortinarius orellanus: detection and assay of orellanine in biological fluids and renal biopsies

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    International audienceA woman suffering from acute tubulo-interstitial nephritis was admitted to the hospital ten days after deliberate intoxication by ingestion of Cortinarius orellanus. Orellanine, the main toxin responsible for orellanine poisoning, was detected in biological fluids and renal biopsies. It was assayed by direct spectrofluorimetry on two-dimensional thin-layer chromatograms after specific photodecomposition into orelline. The orellanine concentration was 6.12 mg/l in the plasma (10 days after ingestion). Orellanine levels in renal biopsies were 7 micrograms per 25 mm3 of the first biopsy (13 days after ingestion) and 24 micrograms per 8 mm3 of the second biopsy (6 months later)

    Exclusion, résistance, complémentarité : quelles logiques en pratique ?

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    Quand la notion d’intĂ©gration scolaire dĂ©rive vers celle d’accueil, elle peut s’avĂ©rer complice de la rĂ©sistance des familles aux soins. En s’appuyant sur leur expĂ©rience dans un secteur de psychiatrie infanto-juvĂ©nile du Val-de-Marne, et sur un cas clinique, les auteurs insistent sur la primautĂ© des soins pour les enfants souffrants de graves troubles psychiques, et l’intĂ©rĂȘt d’articulations fines, continues et institutionnalisĂ©es avec les intervenants du milieu scolaire

    Corrosion Mitigation in Molten Salt Environments

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    International audienceThe aim of this paper is to present methods for corrosion mitigation in molten salt environments. The corrosion of structural materials depends directly on the redox potential of the salt. When the redox potential of the salt is higher than the standard potentials of the elements constituting the structural materials, corrosion occurs. If the reverse is true, no corrosion is observed. Herein, a methodology for calculating the theoretical potential of a molten salt is provided and compared with experimental measurements. Three ways to mitigate corrosion by modifying the salt redox potential are proposed: (i) using a soluble/soluble redox system; (ii) using a potentiostatic method; and (iii) using an amphoteric compound such as UCl3, TiCl2, or TiCl3. Immersion tests were conducted under the above conditions to validate the methodology.</jats:p
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