International Concrete Abstracts Portal

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: 

SP34-37

Date: 

January 1, 1972

Author(s):

M.A. Mukaddam, and B. Bresler

Publication:

Symposium Papers

Volume:

34

Abstract:

A mathematical model is developed which defines deformation of concrete taking into account temperature history, load history, aging of concrete, and influence of temperature on creep of concrete. Previously published experimental data on sealed specimens is used to dervice constitutive relations which account for effect of temperature on creep. These expressions are applied to concrete under variable uniaxial compression and variable temperature.

DOI:

10.14359/18093


Document: 

SP34-38

Date: 

January 1, 1972

Author(s):

Y. Aoyagi, H. Ohnuma, and M. Kawasaki

Publication:

Symposium Papers

Volume:

34

Abstract:

Considerable thermal gradients exist in nuclear reactor pressure vessels. This paper presents the results of experimental studies on the effects of creep at elevated temperatures on the relaxation of stress and on the amounts of deformation in flexurally restrained prestressed concrete beams.

DOI:

10.14359/18094


Document: 

SP34-39

Date: 

January 1, 1972

Author(s):

G.D. Whitman, J.P. Callahan, and J.M. Corum

Publication:

Symposium Papers

Volume:

34

Abstract:

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.

DOI:

10.14359/18095


Document: 

SP34

Date: 

January 1, 1972

Author(s):

Editor: Clyde E. Kesler

Publication:

Symposium Papers

Volume:

34

Abstract:

SP34 Contains a presentation from the International Symposium "Concrete for Nuclear Reactors," held in Berlin in 1970 plus additional selected papers and discussions, and a 365-entry annotated bibliography on concrete for radiation shielding. Subjects include: what the designer needs to know; concrete strength under different states of stress; behavior under long-term thermal influences; effects of neutron irradiation; and future research and development.

DOI:

10.14359/14087


Document: 

SP34-40

Date: 

January 1, 1972

Author(s):

H. Abe, T. Kawahara, T. Ito and A. Haraguchi

Publication:

Symposium Papers

Volume:

34

Abstract:

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.

DOI:

10.14359/18096


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