核用SiCf/SiC复合材料导热性能研究进展

IF 0.9 4区 材料科学 Q3 MATERIALS SCIENCE, CERAMICS
Weina Guo, Yantao Gao
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引用次数: 0

摘要

连续碳化硅纤维增韧碳化硅复合材料(SiCf/SiC)具有化学活性低、密度小、热膨胀系数小、能量转化率高、高温强度好等优点,是核反应堆领域应用前景广阔的材料。然而,传统的SiCf/SiC复合材料难以满足核反应堆的导热性要求。为了提高SiCf/SiC复合材料的导热性,首先介绍了在核反应堆应用中提高SiCf/SiC复合材料导热性的多种方法。此外,还对这一领域的国际研究进展进行了综述。最后,对导热系数研究的进一步发展进行了讨论和展望。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Review on thermal conductivity of SiCf/SiC composites for nuclear applications
Continuous silicon carbide fibre toughened silicon carbide composites (SiCf/SiC) are highly promising materials for nuclear reactor applications due to their low chemical activity, low density, low coefficient of thermal expansion, high energy conversion rate and good high temperature strength. However, the thermal conductivity requirements of nuclear reactors are difficult to meet in conventional SiCf/SiC composites. To improve the thermal conductivity of SiCf/SiC composites, many approaches to enhance the thermal conductivity of SiCf/SiC composites under nuclear reactor applications were firstly introduced. Further, the worldwide research process in this field has been reviewed. Finally, further development of the thermal conductivity research was discussed and prospected.
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来源期刊
Processing and Application of Ceramics
Processing and Application of Ceramics MATERIALS SCIENCE, CERAMICS-
CiteScore
1.90
自引率
9.10%
发文量
14
审稿时长
10 weeks
期刊介绍: Information not localized
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