Effect of Magnetite Concrete on Splitting Tensile Strength and Gamma Ray Shielding Performance Exposed to Repeated Heating at High Temperature

Author:

Huang Xinyun123,Chen Zhenfu123,Tao Qiuwang123,Xie Liping4,Jin Dan12,Wu Dan12

Affiliation:

1. School of Civil Engineering, University of South China, Hengyang 421001, China

2. Key Laboratory of High-Performance Special Concrete in Hunan Province, University of South China, Hengyang 421001, China

3. Key Laboratory of High-Performance Concrete in China Nuclear Industry, University of South China, Hengyang 421001, China

4. China Nuclear Industry 22ND Construction Company Ltd., Yichang 443101, China

Abstract

Radiation shielding concrete is one of the most used materials in the construction of nuclear power plants and will be subjected to high temperatures for a long time during its service life. This study aims to investigate deterioration of radiation shielding concrete with multiple heating at different temperatures. A microwave oven was used as a heating apparatus to simulate irradiation, and 200, 300, and 400 °C were selected as experimental cycle temperatures. The apparent characteristics, mass loss, splitting tensile strength, and gamma ray shielding properties of the commonly used magnetite shielding concrete were investigated. The results showed that the splitting tensile strength and gamma shielding performance of concrete were dramatically reduced at first heating. Then, as the heating times increased, the splitting tensile strength and gamma shielding properties of the concrete continued to deteriorate, and the higher the increase in heating temperature, the more severe the deterioration of the concrete. During the service period of radiation shielded concrete, the magnitude of temperature under the service conditions will affect the deterioration degree of concrete, and the continuous change of temperature will continuously lead to the deterioration of concrete.

Funder

National Natural Science Foundation of China

Publisher

MDPI AG

Subject

General Materials Science

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