On Properties of Magnetite and Serpentine Concrete at Elevated Temperatures for Nuclear Reactor Shielding

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: On Properties of Magnetite and Serpentine Concrete at Elevated Temperatures for Nuclear Reactor Shielding

Author(s): S. Ohgishi, S. Miyasaka, and J. Chida

Publication: Special Publication

Volume: 34

Issue:

Appears on pages(s): 1243-1256

Keywords: compressive strength; concrete; density (mass/volume); heavyweight aggregates; heavyweight concretes; high temperature; magnetite; modulus of elasticity; mortars (material); nuclear reactor containment; nuclear reactors; ophicalcite; radiation shielding

Date: 1/1/1972

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.