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http://dx.doi.org/10.4191/KCERS.2006.43.12.833

Oxidation Behavior and Property Changes of Nuclear Graphite  

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)
Publication Information
Journal of the Korean Ceramic Society / v.43, no.12, 2006 , pp. 833-838 More about this Journal
Abstract
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.
Keywords
Graphite; Oxidation; Nuclear; Activation energy;
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