Title:
Effects of Temperature on a Prestressed Concrete Reactor Vessel Model
Author(s):
T .E. Northup and F.S. Ople, Jr.
Publication:
Symposium Paper
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
DOI:
10.14359/17335
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.