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Home > Publications > International Concrete Abstracts Portal
The International Concrete Abstracts Portal is an ACI led collaboration with leading technical organizations from within the international concrete industry and offers the most comprehensive collection of published concrete abstracts.
Showing 1-5 of 74 Abstracts search results
Document:
SP34-72
Date:
January 1, 1972
Author(s):
H. Benzler
Publication:
Symposium Papers
Volume:
34
Abstract:
A synopsis of the present methods of information exchange in the field of prestressed concrete reactor pressure vessels, particularly as handled by the Commission of the European Communities, is presented. Suggestions are also presented to aid the transfer of information.
DOI:
10.14359/18128
SP34-73
M. De. Pra
A criticism of the present philosophy in concrete research is presented.
10.14359/18129
SP34-39
G.D. Whitman, J.P. Callahan, and J.M. Corum
The efffects of the thermal conditions imposed on a prestressed concrete pressure vessel (PCRV) present a major uncertainty in predicting long-term vessel behavior. In current vessel deesigns insulating and cooling are provided to limit concrete temperatures to 200 F (93 C) or less; however, the time-dependent behavior of the structures may be significantly affected by this relatively low temperature.
10.14359/18095
SP34-40
H. Abe, T. Kawahara, T. Ito and A. Haraguchi
Reinforced concrete and prestressed concrete structures are not, in general, exposed to high temperature, and the thermal stress is of almost no importance in these structures. However, with the recent trend of establishment of nuclear power stations, concrete has come in to use in such places as shielding, pressure vessels and containment structures. . .This paper presents results of an investigation on the determination of proportion, selection of material, the concept of design constants in analyzing thermal stress, and factor of elevated temperature affecting thermal and mechanical properties of concrete.
10.14359/18096
SP34-33
N. Jundi, T.W. Kennedy, E.S. Perry and J.N. Thompson
At the request of the United States Atomic Energy Commision, a basic research program to develop and improve the technology of prestressed reactor vessels was formualted and initiated by the Oak Ridge National Laboratory, which is operated by the Union Carbide Corporation. As a part of this program, and extensive study of the time-dependent deformation of concrete specimens subjected to various stress conditions and elevated temperatures was begun at the University of Texas at Austin. This paper discusses the experimental aspects of this study and includes the preliminary investigations, preparation of specimens, and instrumentation as well as the testing procedure (References 3 and 4). Data analysis and results of the study are presented in Reference 1, 2, 4, 5, and 6.
10.14359/18089
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