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
来源
JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE | 2016年 / 2卷 / 01期
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
相关论文
共 13 条
  • [1] Bartels D. M., 2006, SUPERCRITICAL WATER
  • [2] Eliaz N, 2003, T INDIAN I METALS, V56, P305
  • [3] Fujisawa R., 2005, CORROSION 2005
  • [4] Guzonas D., 2009, POWERPLANT CHEM, V11, P284
  • [5] Stress corrosion cracking susceptibility of austenitic stainless steels in supercritical water conditions
    Novotny, R.
    Hahner, P.
    Siegl, J.
    Hausild, P.
    Ripplinger, S.
    Penttila, S.
    Toivonen, A.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 409 (02) : 117 - 123
  • [6] Penttila S., 2009, P 4 INT S SUP WAT CO
  • [7] The effect of temperature on the SSRT behavior of austenitic stainless steels in SCW
    Shen, Zhao
    Zhang, Lefu
    Tang, Rui
    Zhang, Qiang
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 454 (1-3) : 274 - 282
  • [8] Steven A. A., 2003, LM03K049 LOCKH MART
  • [9] Tsuchiya Y., 2007, P NACE INT CORROSION
  • [10] Was G., 2005, P 12 INT C ENV DEGR, P1343