Research Article
Jan 1970
PWR Containment Structures Design Experience
Authors: P. Blair Haga and John D. StevensonAuthor Affiliations
Abstract
The design philosophy being used in the construction of a number of concrete nuclear power reactor containment structures is analyzed. A brief description of the pressurized water reactor (PWR) thermal generating system is also presented. Loading and stress criteria as well as the engineered safeguard systems currently being employed are summarized in detail. Specific comparisons between design parameters for four containment structures are presented in tabular form for ease of reference.
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Information
Published In
Journal of the Power Division
Volume 96 • Issue 1 • January 1970
Pages: 145 - 155
Copyright
© 1970 American Society of Civil Engineers.
History
Published in print: Jan 1970
Published online: Feb 11, 2021
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Authors
Affiliations
P. Blair Haga
Manager, Reactor Plant Development, Westinghouse Pressurized Water Reactor Systems Division, Nuclear Energy Systems, Pittsburgh, Pa.
John D. Stevenson
Manager, Structural Systems Engrg., Westinghouse Pressurized Water Reactor Systems Division, Pittsburgh, Pa.
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ASCE Library Cards let you download journal articles, proceedings papers, and available book chapters across the entire ASCE Library platform. ASCE Library Cards remain active for 24 months or until all downloads are used. Note: This content will be debited as one download at time of checkout.
Terms of Use: ASCE Library Cards are for individual, personal use only. Reselling, republishing, or forwarding the materials to libraries or reading rooms is prohibited.
Terms of Use: ASCE Library Cards are for individual, personal use only. Reselling, republishing, or forwarding the materials to libraries or reading rooms is prohibited.