Title: Proposed ACI Standard: Code for Concrete Reactor Vessels and Containments
Author(s): ACI-ASME Committee 359
Publication: Journal Proceedings
Appears on pages(s): 323-327
Keywords: building codes; deformation; elastic properties; nuclear power plants; nuclear reactor containment; nuclear reactors; pressure control; prestressed concrete; quality control; reinforced concrete; relief valves:shells (structural forms); vacuum.
This proposed standard, which has been prepared by the Joint ACI-ASME Technical Committee on Concrete Pressure Components for Nuclear Service [ACI-ASME Committee 359), constitutes the requirements for the design, construction, and use of concrete reactor vessels and concrete containment structures for nuclear power plants. Publication of the standard has been approved by ACI and ASME on a trial use and comment basis for a period that is expected to last about one year, after which there will be public hearings leading to its formal adoption as a code. The Societies have agreed that the document will form Division 2 of ASME Boiler and Pressure Vessel Code, Section Ill. The current publication and all later changes in it are subject to procedures agreed to by the two Societies.