Journal of the Korean Ceramic Society (한국세라믹학회지)

The Korean Ceramic Society (한국세라믹학회)
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Oxidation Behavior and Property Changes of Nuclear Graphite

원자로급 흑연의 산화거동 및 산화에 따른 물성변화

  • Cho, Kwang-Youn (Division of Nano Materials Application, KICET) ;
  • Kim, Kyong-Ja (Division of Nano Materials Application, KICET) ;
  • Lim, Yun-Soo (Division of Materials Science and Engineering, Myongji University) ;
  • Chung, Yun-Joong (Division of Materials Science and Engineering, Myongji University) ;
  • Chi, Se-Hwan (Department of Nuclear Hydrogen Project, KAERI)
  • 조광연 (요업기술원 나노소재팀) ;
  • 김경자 (요업기술원 나노소재팀) ;
  • 임연수 (명지대학교 신소재공학과) ;
  • 정윤중 (명지대학교 신소재공학과) ;
  • 지세환 (원자력연구소 원자력수소연구팀)
  • Published : 2006.12.31
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Abstract

Graphite is suitable for high temperature structural materials because of chemical stability as well as unique crystal structure. Especially, graphite can be used as a part of a nuclear reactor due to high tolerance at the extreme conditions of high temperature and neutron irradiations. Although study of oxidation properties or behaviors of graphite are very important and essential for the life and stability of the nuclear reactor, most of studies treat this theme lightly. This work focuses on the oxidation characteristics of several grade isotropic graphite of the nuclear reactor.

Keywords

References

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Cited by

  1. Wear Properties of Nuclear Graphite IG-110 at Elevated Temperature vol.38, pp.5, 2014, https://doi.org/10.3795/KSME-A.2014.38.5.469