Studies on prestressed concrete reactor vessels. Model experiment on PCRV (in Japanese)
Journal Article
·
· Konkurito Janaru, v. 10, no. 11, pp. 1-11
OSTI ID:4313181
Technology of model experiment on PCRV is described. The model experiment was made to check on the validity of a newly developed, three dimensional stress analysis method, and also to develop new techniques of the experiment for the future. The first phase was three-dimensional photoelasticity experiment with a cylinder with top and bottom slabs to know distribution of stress and prestress. Then epoxy resin model experiment followed to obtain quantitatively stress and deformation within the range of elasticity and to compare these quantities with analytical values. The technique of finite element method developed employed curvedsurface body elements in three dimensions. After this confirmation of the technique, the next step was experiment with a concrete model of the PCRV in the process up to vessel rupture. It is about 1/20 of the PCRV for a 300 MW(e) gas-cooled reactor. Items investigated in the experiment were the stress distribution in internal pressure and prestressing, and vessel behavior from cracking to rupture; and funther temperature stress experiment was carried out with a medium sized concrete model. (JA)
- Research Organization:
- Tokyo Electric Power Co. Inc.
- NSA Number:
- NSA-29-023630
- OSTI ID:
- 4313181
- Journal Information:
- Konkurito Janaru, v. 10, no. 11, pp. 1-11, Journal Name: Konkurito Janaru, v. 10, no. 11, pp. 1-11; ISSN KOJAA
- Country of Publication:
- Japan
- Language:
- Japanese
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