HTGR Knowledge Base
Conference Article: Component test of the core support post of the HTTR
Ishihara, M.; Iyoku, T.; Takikawa, N.; Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment); Jinza, K.; Tsuji, N.; Miki, T. (Fuji Electric Co. Ltd., Kawasaki, Kanagawa (Japan))Abstract
The component test of core support post for the High Temperature Engineering Test Reactor (HTTR) was carried out to verify its structural integrity using full-scale and 1/2-scale models of core support post and seat. The compressive fracture load (buckling load) of support post was measured under the conditions of post inclination angles to the post axis up to about 1 degree, cyclic load above maximum applied load and oxidation weight loss under about 30% at room temperature. In the cyclic load test, compressive fracture load was also measured after 200 times of cyclic load applied. The magnitude of this cyclic load was about 2.5 times of the maximum applied load in the design of HTTR. In this report the effects of compressive fracture load on post inclination angle, cyclic load and oxidation weight loss of this component were discussed and obtained fracture loads were compared with the applied load in the design of HTTR.
view the full text of this article (11 pages, format: PDF, size= 1148kB)
key words: deformation; httr reactor; mechanical properties; reactor components; reactor cores; supports; testing; enriched uranium reactors; experimental reactors; gas cooled reactors; graphite moderated reactors; helium cooled reactors; htgr type reactors; mechanical structures
- Reference:
- Specialists' meeting on the status of graphite development for gas cooled reactors. Tokai,
Ibaraki (Japan). 9-12 Sep 1991
- International Atomic Energy Agency, Vienna (Austria)
- IAEA-TECDOC--690, pp:95-105
- International Atomic Energy Agency, Vienna (Austria)