Advanced SearchSearch Tips
Thermal Emissivity of Nuclear Graphite as a Function of Its Oxidation Degree (1) -Effects of Density, Porosity, and Microstructure-
facebook(new window)  Pirnt(new window) E-mail(new window) Excel Download
  • Journal title : Carbon letters
  • Volume 10, Issue 3,  2009, pp.225-229
  • Publisher : Korean Carbon Society
  • DOI : 10.5714/CL.2009.10.3.225
 Title & Authors
Thermal Emissivity of Nuclear Graphite as a Function of Its Oxidation Degree (1) -Effects of Density, Porosity, and Microstructure-
Seo, Seung-Kuk; Roh, Jae-Seung; Kim, Eung-Seon; Chi, Se-Hwan; Kim, Suk-Hwan; Lee, Sang-Woo;
  PDF(new window)
Thermal emissivity of commercial nuclear graphites (IG-110, PCEA, IG-430 and NBG-18) following changes in oxidation degrees were examined. Specimens were oxidized to 0%, 5%, and 10% in air flow of 5l/min at using a furnace, and the thermal emissivities were measured using an infrared spectrum analyzer. The measuring temperatures for the thermal emissivity were , , , . Also density and porosity of the specimens were observed to compare with thermal emissivity. Results showed that emissivity increased with oxidation, and the 10% oxidized NBG-18 showed the highest emissivity (0.890) which value is larger for 24% than the value of as-received specimen. Investigation of factors affecting the emissivity revealed that increases in the surface roughness and porosity due to oxidation were responsible for the increase in emissivity after oxidation.
Nuclear graphite;Oxidation;Emissivity;Microstructure;Porosity;Density;
 Cited by
Thermal Emissivity of Nuclear Graphite as a Function of its Oxidation Degree (3): Structural Study using Scanning Electron Microscope and X-Ray Diffraction,;;;;;

Carbon letters, 2011. vol.12. 1, pp.8-15 crossref(new window)
Mitchell, B. C.; Smart, J.; Fok, S. L.; Marsden, B. J. J. Nuclear Materials, 2003, 322, 126. crossref(new window)

Luo, X.; Robin, J. C.; Yu, S. Nuclear Engineering and Design, 2004, 227, 237.

Rainer, M.; Hinssen, H. K.; Kerstin, K. Nuclear Engineering and Design, 2004, 227, 281. crossref(new window)

Kurumada, A.; Oku, T.; Harada, K.; Kawamata, K.; Sato, S.; Hiraoka T.; McEaney, B. Carbon, 1997, 35(8), 1157. crossref(new window)

Idaho National Engineering & Environmental Laboratory, "Very High Temperature Gas Cooled Reactor Systems", 2002 Winter ANS Meeting, Washington, D.C.

Chunhe, T.; Jie, G.. J. Nuclear Materials, 1995, 224, 103. crossref(new window)

Zhao, C. Y.; Lu, T. J.; Hodson, H. P. International Journal of Heat and Mass Transfer, 2004, 47, 2927. crossref(new window)

Zueco, J.; Alhama, F. J. Quantitative Spectroscopy & Radiative Transfer, 2006, 101, 73. crossref(new window)

Ball, M.; Pinkerton, H.; Harris, A. J. L. J. of Volcanology and Geothermal Research, 2008, 173, 148. crossref(new window)

Gardner, L.; Ng, K. T. Fire Safety Journal, 2006, 41, 185. crossref(new window)

Yi, J.; He, X. D.; Sun, Y.; Li, Y. Applied Surface Science, 2007, 253, 4361. crossref(new window)

Bellayer, S.; Gilman, J. W.; Rahatekar, S. S.; Bourbigot, S.; Flambard, X.; Hanssen, L. M.; Guo, H.; Kumar, S. Carbon, 2007, 45, 2417. crossref(new window)

Kim, E. S.; Kim, Y. W. "Effect of a Thermal Oxidation on the Compressive Strengths of Selected Nuclear Graphites", Transactions of the Korean Nuclear Society Autumn Meeting PyeongChang, Korea, 2007.

Chi, S. H.; Kim, G. C. J. Nuclear Materials, 2008, 381, 9. crossref(new window)