Effects of Temperature on a Prestressed Concrete Reactor Vessel Model

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Title: Effects of Temperature on a Prestressed Concrete Reactor Vessel Model

Author(s): T .E. Northup and F.S. Ople, Jr.

Publication: Special Publication

Volume: 25

Issue:

Appears on pages(s): 149-172

Keywords: age; aggregates; andesite; concretes; creep properties; creep recovery; deflection; finite-element method; high temperature tests; models; moisture content; nuclear reactors; pressure; pressure vessels; prestressed concrete; research shrinkage; strains

Date: 1/1/1971

Abstract:
Results of elevated temperature tests on a one-quarter scale prestressed concrete reactor vessel (PCRV) model are reported. The long-terms behavior of the PCRV model was evaluated for sustained temperatures up to 140 F (60 C). Major emphasis was placed on the creep of concrete subjected to complex mechanical and thermal loading conditions.