PROGRESS OF THE STUDY ON CORROSION BEHAVIOR OF GRAPHITE IN HTGRS
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.
Peng Wang Xinli Yu Suyuan Yu
INET, Tsinghua University Beijing, China CNNC China Nuclear Power Engineering Co., Ltd.Beijing, China
国际会议
18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)
西安
英文
1-7
2010-05-17（万方平台首次上网日期，不代表论文的发表时间）