Concrete Properties Relevant to Reactor Shield Behavior

ABOUT THE 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.

International Concrete Abstracts Portal

  


Title: Concrete Properties Relevant to Reactor Shield Behavior

Author(s): C. P. Thorne

Publication: Journal Proceedings

Volume: 57

Issue: 5

Appears on pages(s): 1491-1508

Keywords: none

Date: 5/1/1961

Abstract:
Available information on the factors affecting the properties of concrete relevant to the determination of the stresses in a concrete reactor shield is examined in detail, and the need for further investigation of several of these properties is noted. As a result of this examination it is possible to state the type of concrete best suited to the particular requirements of reactor shielding. The effect of partial drying of the shield on the distribution of tempera-ture and unrestrained strain is examined theoretically and it is shown that the distribution of moisture content in the shield is of major importance.