• Title/Summary/Keyword: Ceramic fiber composites

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Manufacturing of Hybrid Metal Matrix Composites used $Al_2O_3$ Short Fiber and $Al_2O_3$-TiC Composite Powder Synthesized by SHS Process (SHS법에 의해 제조된 $Al_2O_3$-TiC복합분말과 $Al_2O_3$단섬유를 강화재로 사용한 하이브리드 금속기 복합재료의 제조)

  • Kim, Dong-Hyeon;Maeng, Deok-Yeong;Lee, Jong-Hyeon;Won, Chang-Whan
    • Korean Journal of Materials Research
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    • v.9 no.3
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    • pp.315-321
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    • 1999
  • Metal matrix composites have been extensively studied because of their excellent characteristics for structural application. $Al_2O_3$ and SiC have been used as a common reinforcement owing to their good mechanical properties. However the manufacturing cost of these ceramic reinforcement is expensive, so the use of the composites has been restricted to special purposes. In this study, we tested the application possibility as a reinforcement of $Al_2O_3$-TiC powder synthesized by SHS(Self-propagating High-temperature Synthesis) process to Al alloy matrix composite. Also, $Al_2O_3$ short fibers were added with the synthesized powders in order to apply to the Al matrix hybrid composites. Squeeze infiltration casting process was used to make the composite with 25vol% of reinforcement. Microstructure and crystal structure were examined by SEM, OM and XRD, also the mechanical properties were studied by the compressive test and wear test.

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Analysis of Thermal Shock Behavior of Cladding with SiCf/SiC Composite Protective Films (SiCf/SiC 복합체 보호막 금속피복관의 열충격 거동 분석)

  • Lee, Dong-Hee;Kim, Weon-Ju;Park, Ji-Yeon;Kim, Dae-Jong;Lee, Hyeon-Geon;Park, Kwang-Heon
    • Composites Research
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    • v.29 no.1
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    • pp.40-44
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    • 2016
  • Nuclear fuel cladding used in a nuclear power plant must possess superior oxidation resistance in the coolant atmosphere of high temperature/high pressure. However, as was the case for the critical LOCA (loss-of-coolant accident) accident that took place in the Fukushima disaster, there is a risk of hydrogen explosion when the nuclear fuel cladding and steam reacts dramatically to cause a rapid high-temperature oxidation accompanied by generation of a huge amount of hydrogen. Hence, an active search is ongoing for an alternative material to be used for manufacturing of nuclear fuel cladding. Studies are currently aimed at improving the safety of this cladding. In particular, ceramic-based nuclear fuel cladding, such as SiC, is receiving much attention due to the excellent radiation resistance, high strength, chemical durability against oxidation and corrosion, and excellent thermal conduction of ceramics. In the present study, cladding with $SiC_f/SiC$ protective films was fabricated using a process that forms a matrix phase by polymer impregnation of polycarbosilane (PCS) after filament-winding the SiC fiber onto an existing Zry-4 cladding tube. It is analyzed the oxidation and microstructure of the metal cladding with $SiC_f/SiC$ composite protective films using a drop tube furnace for thermal shock test.