Crack growth and cracking behavior of Alloy 600/182 and Alloy 690/152 welds in simulated PWR primary water

被引:27
作者
Lim, Yun Soo [1 ]
Kim, Dong Jin [1 ]
Kim, Sung Woo [1 ]
Kim, Hong Pyo [1 ]
机构
[1] Korea Atom Energy Res Inst, Nucl Mat Res Div, 989-111 Daedeok Daero, Daejeon 34057, South Korea
关键词
Alloys; 600/182; 690/152; Welding; PWSCC; Crack growth rate; Crack propagation; STRESS-CORROSION CRACKING; CHEMISTRY;
D O I
10.1016/j.net.2018.09.011
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
The crack growth responses of as-received and as-welded Alloy 600/182 and Alloy 690/152 welds to constant loading were measured by a direct current potential drop method using compact tension specimens in primary water at 325 degrees C simulating the normal operating conditions of a nuclear power plant. The as-received Alloy 600 showed crack growth rates (CGRs) between 9.6 x 10(-9) mm/s and 3.8 x 10(-9) mm/s, and the as-welded Alloy 182 had CGRs between 7.9 x 10(-9) mm/s and 7.5 x 10(-7) mm/s within the range of the applied loadings. These results indicate that Alloys 600 and 182 are susceptible to cracking. The average CGR of the as-welded Alloy 152 was found to be 2.8 x 10(-9) mm/s. Therefore, Alloy 152 was proven to be highly resistant to cracking. The as-received Alloy 690 showed no crack growth even with an inhomogeneous banded microstructure. The cracking mode of Alloys 600 and 182 was an intergranular cracking; however, Alloy 152 was revealed to have a mixed (intergranular + transgranular) cracking mode. It appears that the Cr concentration and the microstructural features significantly affect the cracking resistance and the cracking behavior of Ni-base alloys in PWR primary water. (C) 2018 Korean Nuclear Society, Published by Elsevier Korea LLC.
引用
收藏
页码:228 / 237
页数:10
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