Journal of the Korean Ceramic Society (한국세라믹학회지)

The Korean Ceramic Society (한국세라믹학회)
권호 표지
DOI QR코드

DOI QR Code

Oxidation Behavior of Nuclear Graphite(IG110) with Surface Roughness

표면조도에 따른 원자로급 흑연(IG110)의 산화거동

  • 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) ;
  • Chi, Se-Hwan (Department of Nuclear Hydrogen Project, KAERI)
  • 조광연 (요업기술원 나노소재팀) ;
  • 김경자 (요업기술원 나노소재팀) ;
  • 임연수 (명지대학교 신소재공학과) ;
  • 지세환 (원자력 연구소 원자력수소사업추진반)
  • Published : 2006.10.31
Download PDF
⟨ Previous Next ⟩

Abstract

Graphite is suitable materials as a moderator, reflector, and supporter of a nuclear reactor because of high tolerance to the high temperature and neutron irradiations. Because graphite is so weak to the oxidation, its oxidation study is essentially demanded for the operation and design of the nuclear reactor. This work focuses on the effect of the surface oxidation of graphite according to the surface treatment. With thermogravimeter (TG), oxidation characteristics of the isotropic graphite are measured at the three temperature areas, and oxidation ratio and amounts are estimated as changing the surface roughness. Furthermore, the polished graphite surface produced fom the surface treatment is investigated with the Raman spectroscopic study. Oxidation behaviors of the surface are also evaluated as elimination the polished layer by washing with strong sonication.

Keywords

References

  1. K. L. Hopkinson, B. J. Marsden, G. Dundulis, V. Kopustinskas, M. Liaukonis, J. Augutis, and E. Uspuras, 'Prediction of Fuel Channel-Grapite Gas-Gap Behaviour in RBMK Reactors,' Nuclear Engineering and Design, 223 117-32 (2003) https://doi.org/10.1016/S0029-5493(03)00044-X
  2. H. Kawakami, 'Air Oxidation Behavior of Carbon and Graphite Materials,' Tanso, 124 26-33 (1986)
  3. 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
  4. 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
  5. L. Xiaowei, R. J. 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
  6. 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
  7. 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

Cited by

  1. Wear Properties of Seal Graphite at Elevated Temperature vol.17, pp.3, 2013, https://doi.org/10.6108/KSPE.2013.17.3.015
  2. A Study of Wear Behavior for Sealing Graphite at Elevated Temperature vol.17, pp.5, 2013, https://doi.org/10.6108/KSPE.2013.17.5.113
  3. Sliding Wear Properties of Graphite as Sealing Materials for Cut off Hot Gas vol.37, pp.11, 2013, https://doi.org/10.3795/KSME-A.2013.37.11.1349
  4. Development of Mathematical Model to Predict Specific Wear Rates of Graphite Seal vol.18, pp.4, 2014, https://doi.org/10.6108/KSPE.2014.18.4.067
  5. 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
  6. Mathematical Model to Evaluate Wear Rate of Graphite as Sealing Materials vol.871, pp.1662-8985, 2013, https://doi.org/10.4028/www.scientific.net/AMR.871.200