Research on Intergranular Corrosion of Alloy 690 Used in SG Tubes

Lin Zhenxia; Dang Ying; Xu Qi; Chen Yong

doi:10.13832/j.jnpe.2017.S2.0128

Volume 38 Issue S2

Feb. 2025

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Article Navigation > Nuclear Power Engineering > 2017 > 38(S2): 128-130

YU Hongxing, SU Guanghui, GUAN Zhonghua, HUANG Daishun. Study on Application of CHF Models on Reactor Pressure Vessel Lower Head for Severe Accident Condition[J]. Nuclear Power Engineering, 2012, 33(6): 46-50.

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Lin Zhenxia, Dang Ying, Xu Qi, Chen Yong. Research on Intergranular Corrosion of Alloy 690 Used in SG Tubes[J]. Nuclear Power Engineering, 2017, 38(S2): 128-130. doi: 10.13832/j.jnpe.2017.S2.0128

Citation:

Lin Zhenxia, Dang Ying, Xu Qi, Chen Yong. Research on Intergranular Corrosion of Alloy 690 Used in SG Tubes[J]. Nuclear Power Engineering, 2017, 38(S2): 128-130. doi: 10.13832/j.jnpe.2017.S2.0128

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Research on Intergranular Corrosion of Alloy 690 Used in SG Tubes

doi: 10.13832/j.jnpe.2017.S2.0128

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

Received Date: 2017-08-14
Rev Recd Date: 2017-09-29

Abstract

Abstract

According to the standard（GB/T 15260-1994）, the experiments of intergranular corrosion of homemade and imported Alloy 690 used in SG tubes are conducted in boiling HNO₃ solutions and boiling H₂SO₄-Fe₂（SO₄）₃ solutions. The intergranular corrosion rate and microstructure of tested specimens are obtained from the experiments. It is found that the homemade Alloy 690 has excellent intergranular corrosion resistance, and the intergranular corrosion resistance of homemade Alloy 690 is generally better than that of imported Alloy 690.
- Heat transfer tube,
- Alloy 690,
- Intergranular corrosion,
- Corrosion rate

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