Published 1977 | Version v1
Book

Experimental verification of creep analyses for prestressed concrete reactor vessels

  • 1. Central Research Inst. of Electric Power Industry, Abiko, Chiba (Japan). Civil Engineering Lab.

Description

The purpose of this study was to clarify which of the various analytical methods to evaluate the effect of creep on the behaviour of prestressed concrete reactor vessels is most suitable, in view of the comparison with experimental creep data based on the tests of prestressed and reinforced concrete members subjected to long term temperature gradients. The main conclusions within the limit of experiments are as follows: (1) First, experiments were made to determine the properties of concrete under the environmental conditions similar in a operating PCRV. (2) Experimental investigations were carried out in which prestressed concrete beams, hollow cylinders and a full scale model (outside diameter 3 m, external height 4 m, and wall thickness 0.5 m) were subjected to long term temperature gradients under the similar restraining conditions as in the walls of PCRV. (3) Various analytical methods such as effective modulus, rate of creep, superposition etc., have been used to calculate creep strains in prestressed concrete members for PCRV. It was made clear, however, that these methods could not always give a realistic prediction for creep behaviours of concrete members especially in such stage as initial heatup of PCRV, when concrete undergoes fairly wide variation of temperature. The authors proposed a new method of creep analysis based on the theory of strain hardening, which assumes that accumulated creep at a given time influences the creep after that. The experimental and calculated results agreed fairly well. Further, this method was incorporated in the finite element creep analysis for the prestressed concrete hollow cylinder and the full scale model. (Auth.)

Additional details

Publishing Information

Publisher
North-Holland.
Imprint Place
Amsterdam, Netherlands
ISBN
0 444 85062 7
Imprint Title
Structural mechanics in reactor technology
Journal Page Range
v. H p. H4/7 1-12.

Conference

Title
4. international conference on structural mechanics in reactor technology.
Dates
15 - 19 Aug 1977.
Place
San Francisco, USA.

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
10433530
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CREEP; MEDIUM TEMPERATURE; PRESTRESSED CONCRETE; REACTOR VESSELS; STRAIN HARDENING; STRAINS; STRESSES; TEMPERATURE DEPENDENCE
Descriptors DEC
BUILDING MATERIALS; COMPOSITE MATERIALS; CONCRETES; CONTAINERS; HARDENING; MECHANICAL PROPERTIES