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Fabrication and Ion Irradiation Characteristics of SiC-Based Ceramics for Advanced Nuclear Energy Systems

차세대 원자력 시스템용 탄화규소계 세라믹스의 제조와 이온조사 특성 평가

  • Kim, Weon-Ju (Division of Nuclear Materials Technology and Development, Korea Atomic Energy Research Institute) ;
  • Kang, Seok-Min (Division of Nuclear Materials Technology and Development, Korea Atomic Energy Research Institute) ;
  • Park, Kyeong-Hwan (Division of Nuclear Materials Technology and Development, Korea Atomic Energy Research Institute, Institute of Advanced Energy, Kyoto University) ;
  • Kohyama Akira (Institute of Advanced Energy, Kyoto University) ;
  • Ryu, Woo-Seog (Division of Nuclear Materials Technology and Development, Korea Atomic Energy Research Institute) ;
  • Park, Ji-Yeon (Division of Nuclear Materials Technology and Development, Korea Atomic Energy Research Institute)
  • 김원주 (한국원자력연구소 원자력재료기술개발부) ;
  • 강석민 (한국원자력연구소 원자력재료기술개발부) ;
  • 박경환 (한국원자력연구소 원자력재료기술개발부, 교토대학교 에너지이공학연구소) ;
  • ;
  • 류우석 (한국원자력연구소 원자력재료기술개발부) ;
  • 박지연 (한국원자력연구소 원자력재료기술개발부)
  • Published : 2005.08.01

Abstract

SiC-based ceramics are considered as candidate materials for the advanced nuclear energy systems such as the generation IV reactors and the fusion reactors due to their excellent high-temperature strength and irradiation resistance. The advanced nuclear energy systems and their main components adopting ceramic composites were briefly reviewed. A novel fabrication method of $SiC_f/SiC$ composites by introducing SiC whiskers was also described. In addition, the charged-particle irradiation ($Si^{2+}$ and $H^{+}$ ion) into CVD SiC was carried out to simulate the severe environments of the advanced nuclear reactors. SiC whiskers grown in the fiber preform increased the matrix infiltration rate by more than $60\%$ compared to the conventional CVI process. The highly crystalline and pure SiC showed little degradation in hardness and elastic modulus up to a damage level of 10 dpa at $1000^{\circ}C$.

Keywords

References

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