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Elaboration of Uranium Monocarbide Samples for Diffusion studies

机译:织造铀单数样品进行扩散研究

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Mixed Uranium-Plutonium Carbides are candidate fuels for 4th generation nuclear reactors. In this frame, a research program is underway at CEA (French alternative and atomic energies commission) to gather basic properties of such material to get a better understanding of in-pile behaviour. In the field of solid state physics, the measurement of transport properties and in particular diffusion coefficient requires the preparation of uranium carbide samples with very specific characteristics: very low oxygen content, mono-phased UC, high density (greater than 95% of the theoretical one), coarse microstructure, accurate samples geometry. In this paper the Process development is presented to manufacture such samples and the specific equipments which have been set up in glove-box. Characterizations of the first samples are also given.
机译:混合铀 - 钚碳化物是第4代核反应堆的候选燃料。在这一框架中,CEA(法国替代和原子能委员会)正在进行研究计划,以收集这些材料的基本性质,以更好地了解桩子行为。在固态物理学领域中,传输性能和特定扩散系数的测量需要制备具有非常特异性特异性的碳化铀样品:非常低的氧含量,单相UC,高密度(大于理论的95%一个),粗糙的微观结构,精确的样本几何形状。本文提出了过程开发,制造了在手套箱中设置的这些样品和特定设备。还给出了第一个样品的特征。

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