# Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2018, Vol. 29 ›› Issue (5): 76

### Stress corrosion cracking behavior of 310S in supercritical water#br# with different oxygen concentrations

Jin-Hua Liu 1,2 • Yue-Ming Tan 2 • Yuan Wang 1 • Bin Gong 2 • Er Jiang 2 • Yong-Fu Zhao 2 • Jia-Zhen Wang 2 • Shan-Xiu Cong 2

1. 1 Key Laboratory of Radiation Physics and Technology, Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610065, China
2 Nuclear Power Institute of China, Chengdu 610041, China
• Contact: Yuan Wang E-mail:wyuan@scu.edu.cn
• Supported by:

This work was supported by the National Natural Science Foundation of China (Nos. 51271171 and 11775150).

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Jin-Hua Liu, Yue-Ming Tan, Yuan Wang, Bin Gong, Er Jiang, Yong-Fu Zhao, Jia-Zhen Wang, Shan-Xiu Cong. Stress corrosion cracking behavior of 310S in supercritical water#br# with different oxygen concentrations.Nuclear Science and Techniques, 2018, 29(5): 76

Abstract:

The effect of dissolved oxygen (DO) on the stress corrosion cracking (SCC) of 310S in supercritical water was investigated using slow-strain-rate tensile tests. The tensile properties, fracture morphology, and distribution of the chemical composition of the oxide were analyzed to evaluate the SCC susceptibility of 310S. The results showed that the rupture elongation decreased significantly as the degree of DO increased. A brittle fracture mode was observed on the fracture surface, and only intergranular cracking was observed on the surface of the gauge section, regardless of the DO. Cracks were widely distributed on the gauge surface near the fracture surface. Oxides were observed in the cracks with two-layered structures, i.e., a Cr-rich inner oxide layer and an Fe-rich outer oxide layer.