scholarly journals Effect of a Boric Acid Corrosive Environment on the Microstructure and Properties of Concrete

Materials ◽  
2020 ◽  
Vol 13 (21) ◽  
pp. 5036 ◽  
Author(s):  
Yu Wang ◽  
Bei Huang ◽  
Zhongyang Mao ◽  
Min Deng ◽  
Huan Cao

Boric acid, a weak acid, is often used to shield neutrons in water cooling systems in nuclear power stations. The leakage of boric acid in water cooling systems damages the concrete structure and affects the safety of nuclear power engineering. In this experiment, concrete specimens were cured with boric acid at 20, 40, and 70 °C to study the effect of boric acid on the microstructure and properties of concrete. X-ray diffraction (XRD) and thermogravimetry and differential scanning calorimetry (TG-DSC) were used to analyze the change in mineral composition. The microstructure was examined by scanning electron microscope (SEM). The porosity of the concrete was examined by mercury intrusion porosimetry (MIP). The results show that the performance of specimens was stable under the curing conditions of 20 and 40 °C. Under the curing environment of 70 °C, the performance of concrete cured with 0, 2000, and 7000 ppm concentrations was stable, but the compressive strength of the 180,000 ppm specimen was reduced by 27.8% and suffered the most serious loss of mass and surface corrosion, with the most harmful pores. The high concentration of boric acid seriously damaged the surface structure of concrete, which is the main reason for its loss of properties. This situation is extremely dangerous in nuclear power engineering, so the effect of boric acid leakage cannot be ignored.

Author(s):  
E.P. Velikhov ◽  
◽  
A.O. Gol’tsev ◽  
V.D. Davidenko ◽  
A.V. El’shin ◽  
...  

1994 ◽  
Author(s):  
Yuri A. Tarabrin ◽  
Alex R. Matevosov ◽  
Andrey V. Teplenichev

Author(s):  
Akio Yamamoto ◽  
Naoto Iizuka ◽  
Takeshi Yoshinaga ◽  
Haruo Fujimori ◽  
Yuuichi Motora

There are crack experiences of core internal components worldwide. So Thermal and Nuclear Power Engineering Society in Japan organized the committee to prepare the appropriate inspection and evaluation guidelines for core internal components at February, 2000. This committee consists of scholars and representatives from utilities and vendors in Japan. At this committee, guidelines for rational inspection and the evaluation method for structural integrity of each core internal components have been developed. For BWR, inspection guidelines for main core internal components like shroud support, core shroud, top guide, core plate, jet pump etc. were prepared at March 2002. Basic concept of guidelines and inspection guideline of shroud support as example will be explained here.


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