Abstract

In this study, the effect of boric acid in the cooling water system of nuclear power plants on the durability of reinforced concrete was experimentally studied. The mechanical properties of reinforced concrete under boric acid solution environments were studied by accelerated test methods. In addition, the effect of boric acid on the electrochemical behavior of steel bar and microstructure of concrete was studied. The results showed that boric acid corrosion does not affect reinforced concrete to a large extent, as corrosion only occurs on the surface of reinforced concrete, and thus, the internal reinforced concrete still maintains a high alkaline environment. At a boric acid concentration of 3%, corrosion products are crystallized on the surface of the specimen, which inhibits further corrosion.

Highlights

  • Boric acid, as a nuclear reactor moderator, is widely used in the cooling water system of nuclear power plants

  • It is present in the in-containment refueling water storage tank (IRWST) and spent fuel pool, which are constructed with reinforced concrete with stainless steel coating. e operating characteristics of the nuclear power plant do not allow IRWST and spent fuel pool to be emptied frequently for inspection, and liquid leakage from them will have the long-term effect of boric acid corrosion on concrete. erefore, the effect of boric acid corrosion on reinforced concrete needs to be studied in a systematic way

  • At a boric acid concentration of 3%, the compressive strength loss rate fluctuates at the late stage of corrosion, mainly because the corrosion products attached to the surface of the specimen are gradually uniform, and the stress concentration caused by the corrosion products gradually disappears

Read more

Summary

Introduction

As a nuclear reactor moderator, is widely used in the cooling water system of nuclear power plants. Nuclear power plant structures have high importance and should have a long service life Boric acid plays an important role in the cooling water system for nuclear fuel reactivity control and is present in the primary loop cooling water, which is in direct contact with the core and nuclear fuel It is present in the in-containment refueling water storage tank (IRWST) and spent fuel pool, which are constructed with reinforced concrete with stainless steel coating. E operating characteristics of the nuclear power plant do not allow IRWST and spent fuel pool to be emptied frequently for inspection, and liquid leakage from them will have the long-term effect of boric acid corrosion on concrete. It is present in the in-containment refueling water storage tank (IRWST) and spent fuel pool, which are constructed with reinforced concrete with stainless steel coating. e operating characteristics of the nuclear power plant do not allow IRWST and spent fuel pool to be emptied frequently for inspection, and liquid leakage from them will have the long-term effect of boric acid corrosion on concrete. erefore, the effect of boric acid corrosion on reinforced concrete needs to be studied in a systematic way

Methods
Results
Conclusion
Full Text
Published version (Free)

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call