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TITANIUM CARBIDE AND SILICON CARBIDE THERMAL CONDUCTIVITY UNDER HEAVY IONS IRRADIATION

机译:重离离子照射下的碳化钛和碳化硅导热系数

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SiC_f/SiC ceramic matrix composites (CMC) are considered as structural materials in next generation fission nuclear reactors. However, thermal conductivity of SiC is reduced on the one hand at the highest temperatures, but also under irradiation. Titanium carbide, because of its peculiar thermal properties is an attractive material to be used as a matrix in a CMC to enhance the thermal conductivity of CMC under irradiation and at high temperature. In this study, we performed irradiation experiments on TiC, TiC_xSiC_(1-x) and SiC samples, with heavy ions at room temperature (74 MeV Kr, fluence from 10~(13) to 10~(15) ions/cm2). This energy results in an irradiated layer of about 7 um for TiC. Thermal conductivity of the irradiated layer is measured using IR radiometry as a function of fluence and composition. The structural evolution of the irradiated samples was investigated by Raman micro spectroscopy and transmission electron microscopy.
机译:SiC_F / SiC陶瓷基质复合材料(CMC)被认为是下一代裂变核反应堆中的结构材料。然而,SiC的热导率在最高温度下一方面减小,但也减少了辐照。碳化钛,因为其特殊的热性质是一种有吸引力的材料,其用作CMC中的基质,以提高CMC在照射下和高温下的导热率。在这项研究中,我们对TIC,TIC_XSIC_(1-X)和SIC样品进行了辐照实验,在室温下具有重离子(74meV KR,从10〜(13)至10〜(15)离子/ cm2)。这种能量导致约7μm的辐照层。使用IR辐射测量的照射层的导热率作为注量和组成的函数测量。通过拉曼微光谱和透射电子显微镜研究辐照样品的结构演变。

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