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| Effect of Water Chemistry on Stress Corrosion Cracking of T22 Steel Used in Once Through Steam Generator of Nuclear Power |
WANG Lei1, TAO Zeyu2, LIU Feng3, KUANG Wenjun4( ), MA Xin2, YAO Yao3, ZHANG Guowei1 |
1.CNNC Xiapu Nuclear Power Co. Ltd., Ningde 355100, China 2.School of Materials Science and Engineering, Xi'an Jiaotong University, Xi'an 710049, China 3.China Xi'an Thermal Power Research Institute Co. Ltd., Xi'an 710054, China 4.School of Materials Science and Engineering, South China University of Technology, Guangzhou 510641, China |
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Cite this article:
WANG Lei, TAO Zeyu, LIU Feng, KUANG Wenjun, MA Xin, YAO Yao, ZHANG Guowei. Effect of Water Chemistry on Stress Corrosion Cracking of T22 Steel Used in Once Through Steam Generator of Nuclear Power. Journal of Chinese Society for Corrosion and protection, 2026, 46(4): 1067-1080.
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Abstract For the known generation IV nuclear power plants, such as high-temperature gas-cooled reactors (HTGRs) and sodium-cooled fast reactors (SFRs), once-through steam generators typically adopt a reducing all-volatile treatment [AVT(R)] as the feedwater chemistry control strategy. However, this water chemistry induces flow-accelerated corrosion (FAC) for the related structural components, which can result in heat-transfer tube fouling and throttling valve blockage. Oxygenated treatment (OT) is an effective approach to mitigate throttling valve deposition. Nevertheless, the potential impact of increased dissolved oxygen on the stress corrosion cracking (SCC) susceptibility of structural materials remains to be clarified. In this study, the SCC behavior of T22 steel, widely used in the evaporator section of once-through steam generators in Generation IV reactors, was systematically evaluated in conditions of AVT(R), AVT(O), and OT respectively by using slow strain rate tensile (SSRT) tests. The results demonstrate that an increased dissolved oxygen concentration does not significantly alter the oxidation behavior of T22 steel. Importantly, the adoption of oxidizing AVT or OT conditions does not increase the SCC susceptibility of T22 steel. This work provides a technical foundation for addressing throttling valve deposition in once-through steam generators and offers valuable guidance for optimizing feedwater chemistry in generation IV nuclear power systems.
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Received: 16 September 2025
32134.14.1005.4537.2025.298
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Corresponding Authors:
KUANG Wenjun, E-mail: wjkuang@scut.edu.cn
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