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Founded in 1904 and headquartered in Farmington Hills, Michigan, USA, the American Concrete Institute is a leading authority and resource worldwide for the development, dissemination, and adoption of its consensus-based standards, technical resources, educational programs, and proven expertise for individuals and organizations involved in concrete design, construction, and materials, who share a commitment to pursuing the best use of concrete.
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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: Criteria for Reinforced Concrete Nuclear Power Containment Structures
Nuclear Power Containment Structures
Author(s): ACI Committee 349
Publication: Journal Proceedings
Appears on pages(s): 2-28
Keywords: admixtures; anchorage (structural); circular prestressing; comppsite con- struction (concrete and steel); corrosion; cracking (fracturing); deleterious sub- stances; grout; inspection; linings; load tests (structural); loads (forces); mix proportioning.
Abstract:These design criteria are to serve as a guide in the design of reinforced concrete nuclear power containment structures. The first chapter describes the philosophy of these structures in general and it outlines the various factors to be considered in the design. The second chapter gives specific information on design and analysis methods, on load factors, and on allowable stresses and strains. The third chapter deals with the special material requirements pertaining to the construction of nuclear structures, such as ductility, splices, prestressing, corrosion protection, and others. The fourth chapter pertains to the special requirements of documentation and testing, such as preservation of records, performance of leak tests, and weld inspections, etc. These criteria have been prepared by Committee 349 over a period of 6 years, and are based on the experience gained in the design and construction of nuclear power plants. They are released to the profession as a recommended practice. It is intended to eventually make these recommendations a part of the ASME Boiler and Pressure Vessel Code.
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