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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: 

SP34-65

Date: 

January 1, 1972

Author(s):

N. Czaika

Publication:

Symposium Papers

Volume:

34

Abstract:

An analysis of the instrumentation; trandsucers, intercircuits, computing devices, and recording instruments; used in prestressed concrete reactor pressure vessels is presented.

DOI:

10.14359/18121

Document: 

SP34-66

Date: 

January 1, 1972

Author(s):

A. Honig and L . Pospisilova

Publication:

Symposium Papers

Volume:

34

Abstract:

The biological shields of nuclear reactors are partly thick-walled concrete constructions which do not require special attention, as far as their strength is concerned. . .In this report some types of radiometric probes suitable for density measurement, as well as the results of the reactor shield construction of a nuclear power station, an experimental nuclear reactor, and a biological shield of a betatron are described. The RILEM program: comparision of commerical portable gages for radiometric determination of building materials density and moisture is discussed.

DOI:

10.14359/18122

Document: 

SP34-57

Date: 

January 1, 1972

Author(s):

S. Ohgishi, S. Miyasaka, and J. Chida

Publication:

Symposium Papers

Volume:

34

Abstract:

A general rule for nuclear reactor biological shielding materials is that an ordinary concrete or high-density concrete using an aggregate such as magnnetite, limonite, etc., is the most reasonable for a thermal neutron reactor. . .This paper consists of two parts: first, an experiment on magnetite aggregate concrete and ordinary concrete at elevated temperatures from 20 C to 600 C is reported, and second an experiment on serpentine aggregate concrete and ophicalcite aggregate concrete subjected to different degrees of heating is reported.

DOI:

10.14359/18113

Document: 

SP34-58

Date: 

January 1, 1972

Author(s):

L. Muhe

Publication:

Symposium Papers

Volume:

34

Abstract:

The interaction of pressure grout and the wires in post-tensioning tendons is investigated both during and after pressure grouting. Basic tests on a minimum spacing between the wires in one bundle, sutdies on the procedure of grout flow in the longitudinal direction and finally a model test for the grout flow in the cross direction of a prestressed duct are reported.

DOI:

10.14359/18114

Document: 

SP34-59

Date: 

January 1, 1972

Author(s):

F. Scotto

Publication:

Symposium Papers

Volume:

34

Abstract:

The state of the art of corrosion protection for prestressing tendons in nuclear reaction pressure vessels is presented. Proposals for improving grouting and other corrosion protection techniques are given. The two methods of protection, conventional (mortar grouting) and nonconventional, are compared and contrasted.

DOI:

10.14359/18115

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