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Home > Publications > International Concrete Abstracts Portal
The International Concrete Abstracts Portal is an ACI led collaboration with leading technical organizations from within the international concrete industry and offers the most comprehensive collection of published concrete abstracts.
Title: Proposed Revision to ACI Standard Code for Concrete Reactor Vessels and Containments (ACI 359-80) .
Author(s): ACI-ASME Committee 359
Publication: Concrete International
Appears on pages(s): 68
Keywords: building codes; deformation; elastic properties; nuclear reactors; pressure control; prestressed concrete; quality control; reinforced concrete
Abstract:Constitutes the requirements for the design, construction, and use of concrete reactor vessels and concrete containment structures for nuclear power plants, The document forms Subsection NCA and Division 2 of ASME Boiler and Pressure Vessel Code Section Ill. ACI 359-80 is printed in two parts: (1) general and (2) rules. The first part covers general requirements for manufacturers and suppliers, and owners of nuclear power plant components including requirements for Code symbol stamping, inspector’s duties, and quality assurance. The second part con-tains rules for design, fabrication, construction, and testing of concrete reactor vessels and concrete con-tainments. Offered as revisions to ACI 359-80 in accordance with the Institute’s standardization procedure. Approved for discussion by the membership; discussion closes Jan. 1, 1982. [Author]
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