한국세라믹학회지 (Journal of the Korean Ceramic Society)

  • 제43권12호
  • /
  • Pages.833-838
  • /
  • 2006
  • /
  • 1229-7801(pISSN)
  • /
  • 2234-0491(eISSN)
한국세라믹학회 (The Korean Ceramic Society)
권호 표지
DOI QR코드

DOI QR Code

원자로급 흑연의 산화거동 및 산화에 따른 물성변화

Oxidation Behavior and Property Changes of Nuclear Graphite

  • 조광연 (요업기술원 나노소재팀) ;
  • 김경자 (요업기술원 나노소재팀) ;
  • 임연수 (명지대학교 신소재공학과) ;
  • 정윤중 (명지대학교 신소재공학과) ;
  • 지세환 (원자력연구소 원자력수소연구팀)
  • 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)
  • 발행 : 2006.12.31
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

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.

키워드

참고문헌

  1. B. C. Mitchell, J. Smart, S. L. Fok, and B. J. Marsden, 'The Mechanical Testing of Nuclear Graphite,' J. Nuclear Mater., 322 126-37 (2003) https://doi.org/10.1016/S0022-3115(03)00322-2
  2. A. Kurumada, T. Oku, K. Harada, K. Kawamata, S. Sato, T. Hiraoka, and B. McEaney, 'Effects of Burn-Off on Thermal Shock Resistances of Nuclear Carbon Materials,' Carbon, 35 [8] 1157-65 (1997) https://doi.org/10.1016/S0008-6223(97)00088-2
  3. L. Xiaowei, R. Jean-Charles, and Y. Suyuan, 'Effect of Temperature on Graphite Oxidation Behavior,' Nuclear Engineering and Design, 227 273-80 (2004) https://doi.org/10.1016/j.nucengdes.2003.11.004
  4. T. Chunhe and G. Jie, 'Improvement in Oxidation Resistance of the Nuclear Graphite by Reaction-Coated SiC Coating,' J. Nuclear Mater., 224 103-08 (1995) https://doi.org/10.1016/0022-3115(95)00031-3
  5. G. B. Neighbour and P. J. Hacker, 'The Variation of Compressive Strength of AGR Moderator Graphite with Increasing Thermal Weight Loss,' Mater. Lett., 51 307-14 (2001) https://doi.org/10.1016/S0167-577X(01)00309-3
  6. ASTM C 1179-91
  7. E. L. Fuller and J. M. Okoh, 'Kinetics and Mechanism of the Reaction of Air with Nuclear Grade Graphite: IG-110,' J. Nuclear Mater., 240 241-50 (1997) https://doi.org/10.1016/S0022-3115(96)00462-X
  8. R. Moormann, H. K. Hinssen, and K. Kuhn, 'Oxidation Behaviour of an HTR Fuel Element Matrix Graphite in Oxygen Compared to a Standard Nuclear Graphite,' Nuclear Engineering and Design, 227 281-84 (2004) https://doi.org/10.1016/j.nucengdes.2003.11.001

피인용 문헌

  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