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Development of Carbon / Carbon Composites for Nuclear Reactor Applications

机译:核反应堆应用碳/碳复合材料的研制

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摘要

Carbon and carbon fiber reinforced materials are promising materials for use in nuclear reactors, due to their excellent thermal and mechanical properties. In the present studies, experiments were carried out to prepare carbon-carbon(C/C) composites using non-graphitizing precursors such as polyacrylonitrile (PAN) fiber and phenolic resin matrix. A typical sample of C/C composite at 40 vol% of PAN fibre showed to be amorphous. These fibers have been used to make a 2-D preform and phenol formaldehyde resin was impregnated, cured and carbonized to form the matrix. Impregnation was carried out under different conditions, and its effect was studied by XRD, Raman spectroscopy and XPS. The C/C composite samples have been irradiated by neutrons at neutron flux of 1x10~(12)n/cm~2/s with varying fluences at 40°C. The stored energy is very less about 23.4 J/g and 43.3 J/g as compared to irradiated graphite. The composites were coated with silicon carbide (SiC) for improved oxidation resistance by chemical vapor deposition technique.
机译:碳和碳纤维增强材料是有希望用于核反应堆的材料,因为它们具有优异的热和机械性能。在本研究中,进行实验以使用非石墨化前体如聚丙烯腈(盘)纤维和酚醛树脂基质制备碳 - 碳(C / C)复合材料。 40体积%的帕纤维的C / C复合材料的典型样品显示为无定形。这些纤维已用于制备2-D预制件,并浸渍苯酚甲醛树脂,固化和碳化以形成基质。在不同的条件下进行浸渍,通过XRD,拉曼光谱和XPS研究其效果。 C / C复合样品通过1×10〜(12)n / cm〜2 / s的中子通量的中子照射,在40℃下变化。与辐照石墨相比,储存的能量非常小约23.4J / g和43.3J / g。用碳化硅(SiC)涂覆复合材料,用于通过化学气相沉积技术改善抗氧化性。

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