Published 1979 | Version v1
Book

Creep behavior under sustained temperature gradient in a model of prestressed concrete reactor vessels

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

Description

This paper mainly describes the effects of differential thermal creep on the behaviors of a prestressed concrete pressure vessel model, which was subjected to long-term temperature gradient across the wall up to 600C for a duration of about four months. The height, the outer diameter and the wall thickness of the hollow-cylinder model with top and bottom slabs were 350, 300, and 50 cm respectively, which corresponds to a scale of about 1/10 to the actual structures. The model was prestressed circumferentially and vertically. (orig.)

Additional details

Publishing Information

Publisher
North-Holland Publishing Co.
Imprint Place
Amsterdam, Netherlands
ISBN
0 444 85364 2
Imprint Title
Structural mechanics in reactor technology. Transactions. Vol. H
Journal Page Range
p. H4/9 (1-8).

Conference

Title
5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2).
Dates
9 - 21 Aug 1979.
Place
Berlin, Germany, F.R.

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
12587745
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CREEP; PRESSURE VESSELS; PRESTRESSED CONCRETE; REACTOR VESSELS; TEMPERATURE DEPENDENCE
Descriptors DEC
BUILDING MATERIALS; COMPOSITE MATERIALS; CONCRETES; CONTAINERS; MECHANICAL PROPERTIES

Optional Information

Secondary number(s)
INKA-Conf--79-321-304.