The graphite has been widely used as moderator and structure materials in high-temperature gas-cooled reactors (HTGRs). However the graphite can be corroded by such oxidizing impurities as O2, H2O and CO2 in the coolant, resulting in the degradation of its thermal and mechanical properties. In addition, in water ingress and air ingress accidents, the corrosion of graphite materials is more serious. In this paper, the recent researches, which include the experimental study and computational simulations, on the graphite oxidation behavior during normal operation, water ingress and air ingress accidents were reviewed. Some significant problems concerned in the graphite oxidation for further studying were also put forward.
- Nuclear Engineering Division
Progress of the Study on Corrosion Behavior of Graphite in HTGRs
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Wang, P, Yu, X, & Yu, S. "Progress of the Study on Corrosion Behavior of Graphite in HTGRs." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 5. Xi’an, China. May 17–21, 2010. pp. 379-385. ASME. https://doi.org/10.1115/ICONE18-30357
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