Oxidation Behavior of Nuclear Graphite(IG110) with Surface Roughness

被引：0

作者：

Cho, Kwang-Youn ^{[1
]}

Kim, Kyong-Ja ^{[1
]}

Lim, Yun-Soo ^{[2
]}

Chi, Se-Hwan ^{[3
]}

机构：

[1] KICET, Div Nano Mat Applicat, Seoul 153801, South Korea

[2] Myongji Univ, Div Mat Sci & Engn, Yongin 449728, South Korea

[3] KAERI, Dept Nucl Hydrogen Project, Daejeon 305353, South Korea

来源：

JOURNAL OF THE KOREAN CERAMIC SOCIETY | 2006年 / 43卷 / 10期

关键词：

Graphite; Oxidation; Nuclear; Surface roughness;

D O I：

暂无

中图分类号：

TQ174 [陶瓷工业]; TB3 [工程材料学];

学科分类号：

0805 ; 080502 ;

摘要：

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 from 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

引用

页码：613 / 618

页数：6

共 7 条

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