Discussion. The design construction and testing of a prestressed concrete reactor pressure vessel model

Journal Article · Thu Nov 01 04:00:00 EST 1962 · Proceedings of the Institution of Civil Engineers

DOI:https://doi.org/10.1680/iicep.1962.10883· OSTI ID:4786874

BAKER, A. L. L.; MONCRIEFF, M. L. A.; HANNAH, I. W.; GILL, S.; DAVIDSON, I.; BURROW, R. E. D.; CHABOWSKI, A. J.; HOUGHTON BROWN, A.; ROSS, A. D.; ALLISON, G. D.; BESSON, F.; HARRIS, A. J.; COMMON, D. K.; MILES, J. R.; NEVILLE, A. M.

The design, construction, and pressure testing of a onesixth-scale model prestressed concrete pressure vessel for containing a nuclear reactor are described. Such vessels may ultimately enable the thick-walled steel pressure vessels with independent concrete biological shield, currently used in gas- cooled, graphite-moderated nuclear power stations, to be replaced by a single composite structure. The work demonstrated that such a development is not only feasible, but appears to offer considerable economic advantages, without any diminution of the high safety standards demanded by the industry.

• Research Organization: Originating Research Org. not identified
• Sponsoring Organization: USDOE
• NSA Number: NSA-16-030113
• OSTI ID: 4786874
• Journal Information: Proceedings of the Institution of Civil Engineers, Journal Name: Proceedings of the Institution of Civil Engineers Journal Issue: 3 Vol. 23; ISSN 1753-7789
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

43 PARTICLE ACCELERATORS
CONCRETES
ECONOMICS
GAS COOLANT
GRAPHITE MODERATOR
MOCKUP
PLANNING
POWER PLANTS
PRESSURE VESSELS
RADIATION DOSES
REACTOR SAFETY
REACTORS
SHIELDING
STRESSES
TESTING