Effect of Oxidation Chemistry of Supercritical Water on Stress Corrosion Cracking of Austenitic Steels

被引:2
|
作者
Gong, Bin [1 ]
Huang, Yanping [2 ]
Jiang, E. [1 ]
Zhao, Yongfu [1 ]
Liu, Weiwei [1 ]
Zhou, Zhiru [3 ]
机构
[1] Nucl Power Inst China, Water Chem Lab, Third Sect Huafu Rd, Chengdu 610213, Sichuan, Peoples R China
[2] Nucl Power Inst China, CNNC Key Lab Nucl Reactor Thermalhydraul Technol, POB 622-200, Chengdu 610041, Sichuan, Peoples R China
[3] Nucl Power Inst China, Int Cooperat Dept, Third Sect Huafu Rd, Chengdu 610213, Sichuan, Peoples R China
基金
中国国家自然科学基金;
关键词
supercritical water-cooled reactor; water chemistry; stress corrosion cracking; cladding; austenitic steel;
D O I
10.1115/1.4031076
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Austenitic steel is a candidate material for supercritical water-cooled reactor (SCWR). This study is to investigate the stress corrosion cracking (SCC) behavior of HR3C under the effect of supercritical water chemistry. A transition phenomenon of the water parameters was monitored during a pseudocritical region by water quality experiments at 650 degrees C and 30 MPa. The stress-strain curves and fracture time of HR3C were obtained by slow strain rate tensile (SSRT) tests in the supercritical water at 620 degrees C and 25 MPa. The concentration of the dissolved oxygen (DO) was 200-1000 mu g/kg, and the strain rate was 7.5 x 10(-7)/s. The recent results showed that the failure mode was dominated by intergranular brittle fracture. The relations of the oxygen concentration and the fracture time were nonlinear. 200-500 mu g/kg of oxygen accelerated the cracking, but a longer fracture time was measured when the oxygen concentration was increased to 1000 mu g/kg. Chromium depletion occurred in the oxide layer at the tip of cracks. Grain size increased and chain-precipitated phases were observed in the fractured specimens. These characteristics were considered to contribute to the intergranular SCC.
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页数:8
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