HTGR Knowledge Base
Conference Article: Assessment of the load capacity of the dowel and socket system in the HTTR hexagonal block
Takikawa, N.; Ishihara, M.; Iyoku, T.; Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment); Tokumitsu, M.; Koe, S.; Uno, M. (Kawasaki Heavy Industries (Japan))Abstract
The load capacity of the dowel and socket system was demonstrated in the seismic event using full size graphite blocks and finite element analysis. There was good agreement between the measured fracture stress and the calculated fracture stress. This shows the propriety of 3D FEM modeling in which analytical mesh, quoted data and boundary condition were involved. A special method was also developed for the dowel and socket system. It can estimate the stress of full 3D model from the stresses of 1/3 model.
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key words: finite element method; fracture properties; graphite; hexagonal configuration; httr reactor; reactor cores; seismic events; seismic isolation; simulation; carbon; enriched uranium reactors; experimental reactors; gas cooled reactors; graphite moderated reactors; helium cooled reactors; htgr type reactors; mechanical properties; numerical solution; reactor components; research and test reactors
- 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:105-112
- International Atomic Energy Agency, Vienna (Austria)