HTGR Knowledge Base
Conference Article: Theoretical Analysis On The Tribological Properties Of HTGR-10 Graphite
Xuanyu Sheng, Suyuan Yu, , Institute of Nuclear and New Energy Technology, Beijing, CHINAAbstract
The friction contact modals on the friction contact are summarized here. Based on Finite Element Method, the contact pressure on rough surface is calculated. The influence of the worn surface on the distribution of contact pressure is also investigated. According to our experimental result of graphite wear rate, we estimate the wear of graphite pebble used in HTGR-10. It shows that the 80% graphite will wear out in 10 years running time.
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key words: Graphite, wear, friction contact, nuclear reactor
- Reference:
- Proceedings of the Conference on High Temperature Reactors, Beijing, China, September, 22-24, 2004
- International Atomic Energy Agency, Vienna (Austria)
- HTR-2004, pp:1-7
- International Atomic Energy Agency, Vienna (Austria)