Proposed Revision to ACI Standard Code for Concrete Reactor Vessels and Containments (ACI 359-80) .

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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

Volume: 3

Issue: 10

Appears on pages(s): 68

Keywords: building codes; deformation; elastic properties; nuclear reactors; pressure control; prestressed concrete; quality control; reinforced concrete

Date: 10/1/1981

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]