Research on Uniform Corrosion of Inconel 690 Alloy for Stream Generator in Nuclear Plant Water Environment

Dang Ying; Lin Zhenxia; Pan Xiaoqiang; Li Weijun

doi:10.13832/j.jnpe.2016.03.0061

Volume 37 Issue 3

Feb. 2025

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Dang Ying, Lin Zhenxia, Pan Xiaoqiang, Li Weijun. Research on Uniform Corrosion of Inconel 690 Alloy for Stream Generator in Nuclear Plant Water Environment[J]. Nuclear Power Engineering, 2016, 37(3): 61-65. doi: 10.13832/j.jnpe.2016.03.0061

Citation:

Dang Ying, Lin Zhenxia, Pan Xiaoqiang, Li Weijun. Research on Uniform Corrosion of Inconel 690 Alloy for Stream Generator in Nuclear Plant Water Environment[J]. Nuclear Power Engineering, 2016, 37(3): 61-65. doi: 10.13832/j.jnpe.2016.03.0061

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Research on Uniform Corrosion of Inconel 690 Alloy for Stream Generator in Nuclear Plant Water Environment

doi: 10.13832/j.jnpe.2016.03.0061

Science and Technology on Reaetor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2015-09-16
Rev Recd Date: 2015-12-20

Available Online: 2025-02-15

Abstract

Abstract

Under the stimulated nuclear plant water environment, corrosion property and oxide film characteristics of three kinds of commercial 690 alloys for steam generators were studied in the flow-water corrosion loop. Meanwhile, the general corrosion rate and corrosion product release rate were also estimated using Chinese standard and American standard respectively. The results show that: under the stimulated nuclear plant water environment, 690 alloy tube exhibits very low corrosion rate and corrosion product release rate, and the corrosion performance of Japan Sumitomo 690 alloy tube is better than that of Baosteel 690 alloy tube.
- Heat transfer tube,
- General corrosion rate,
- Corrosion product release rate,
- High temperature and high pressure water