PWR Containment Structures Design Experience

by P. Blair Haga, Manager; Reactor Plant Development, Westinghouse Pressurized Water Reactor Systems Div., Nuclear Energy Systems, Pittsburgh, PA,
John D. Stevenson, Manager; Structural Systems Engrg., Westinghouse Pressurized Water Reactor Systems Div., Pittsburgh, PA,

Serial Information: Journal of the Power Division, 1970, Vol. 96, Issue 1, Pg. 145-155

Document Type: Journal Paper


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.

Subject Headings: Structural design | Concrete structures | Structural analysis | Concrete construction | Concrete | Nuclear reactors | Thermal effects | Load factors

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