Browse > Article
http://dx.doi.org/10.3795/KSME-A.2014.38.5.469

Wear Properties of Nuclear Graphite IG-110 at Elevated Temperature  

Wei, Dunkun (Dept. of Mechanical Design Engineering, Chungnam Nat'l Univ.)
Kim, Jaehoon (Dept. of Mechanical Design Engineering, Chungnam Nat'l Univ.)
Kim, Yeonwook (Dept. of Mechanical Design Engineering, Chungnam Nat'l Univ.)
Publication Information
Transactions of the Korean Society of Mechanical Engineers A / v.38, no.5, 2014 , pp. 469-474 More about this Journal
Abstract
The high temperature gas-cooled reactor (HTR-10) is designed to produce electricity and hydrogen. Graphite is used as reflector, support structures, and a moderator in reactor core; it has good resistance to neutron and is a suitable material at high temperatures. Friction is generated in the graphite structures for the core reflector, support structures, and moderator because of vibration from the HTR-10 fuel cycle flow. In this study, the wear characteristics of the isotropic graphite IG-110 used in HTR-10 were evaluated. The reciprocating wear test was carried out for graphite against graphite. The effects of changes in the contact load and sliding speeds at room temperature and $400^{\circ}C$ on the coefficient of friction and specific wear rate were evaluated. The wear behavior of graphite IG-110 was evaluated based on the wear surfaces.
Keywords
High Temperature Gas Reactor; Graphite IG-110; Wear Characteristics; Specific Wear rate;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
연도 인용수 순위
1 Liu, J. J., Wang M. Z., Zhang Z. M., Zhang Z. Sh. and He S. Y., 2001, "Feature of Reactor Structure Design for 10MW High Temperature Gas-Cooled Reactor," Institute of Nuclear Energy Technology, Vol. 22, No. 1, pp. 53-56.
2 Seo S. K., 2009, "Thermal Emissivity Changes of Nuclear Graphite as a Function of Oxidation Degrees," Department of Impormation & Nano Materials Engineering Graduate School, Kumoh National Institute of Technology.
3 Hong, S. D., 2011, "Development of Essential Technology for VHTR," Korea Atomic Energy Research Institute, pp. 335-340.
4 Rainer, M., Hinssen, H. K. and Kerstin, K., 2004, "Oxidation Behaviour of an HTR Fuel Element Matrix Graphite in Oxygen Compared to a Standard Nuclear Graphite" Nuclear Engineering and Design, pp. 281-284.
5 Juri, P., Mart, V. and Sergei, L., 2006, "Friction and Dry Sliding Wear Behavior of Cermets," Wear, Vol. 260, pp. 815-824.   DOI   ScienceOn
6 Lee, J. S., Kim, E., Park, J. S. and Kim, J., 2001, "Frictional Characteristics of Silicon Graphite Lubricated with Water at High Pressure and High Temperature," Proceeding of KSME Fall Annual Meeting, pp. 151-156.   과학기술학회마을
7 Luo, X. W., Yu, S. Y., Sheng, X. Y. and He, S. Y., 2005, "Wear Behavior of Graphite IG-11 in Different Gas Environments," Institute of Nuclear Energy Technology, Vol. 25, No. 2, pp. 173-177.
8 Kim, Y. W., Kim, J. H., Yang, H. Y., Park, S. H., Lee, H. G., Kim, B. K., Lee, S. B. and Kwak, J. S., 2013, "A Study of Wear Behavior for Sealing Graphite at Elevated Temperature," Journal of the Korean Society of Propulsion Engineers, Vol. 17, No. 4, pp.1-8.
9 Cho, K. Y., Kim, K. J., Lim, Y. S. and Chi, S. H., 2006, "Oxidation Behavior of Nuclear Graphtie(IG-110) with Surface Roughness," Journal of the Korean Ceramic Society, Vol. 43, No. 10, pp. 613-618.   과학기술학회마을   DOI   ScienceOn
10 Luo, X. W., Yu, S. Y., Sheng X. Y. and He, S.Y., 2005, "Temperature Effect on IG-11 Graphite Wear Performance," Nuclear Engineering and Design, Vol. 235, pp. 2261-2274.   DOI   ScienceOn
11 Li, J. L. and Xiong, D. S., 1997, "Tribological Behavior of Carbon-Graphite Seal Materials in Partial Pressure of Helium and Hydrogen," Tribology Letter, Vol. 3, pp. 175-184.   DOI
12 Cho, K. Y., Kim, K. J., Lim, Y. S., Chung, Y. J. and Chi, S. W., 2006, "Oxidation Behavior and Property Changes of Nuclear Graphite," Journal of the Korean Ceramic Society, Vol. 43, No. 12, pp. 833-838.   과학기술학회마을   DOI   ScienceOn