Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints

doi:10.1016/j.jnucmat.2024.155560

IMR OpenIR

	Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints
	Li, Hui 1; Li, Gang 2; Sun, Wei 3,4; Shao, Xuejiao 1; Ma, Guowen 2; Ming, Hongliang 3,4; Zhu, Yichao 2,5
通讯作者	Ming, Hongliang(hlming12s@imr.ac.cn) ; Zhu, Yichao(yichaozhu@dlut.edu.cn)
	2025-02-01
发表期刊	JOURNAL OF NUCLEAR MATERIALS
ISSN	0022-3115
卷号	605 页码:13
摘要	Reliable predictions of the stress corrosion cracking (SCC) behaviour of 690 weld joints in service for several decades in primary water reactor (PWR) have become increasingly important. Now there is still a huge gap between engineering demands and what current experimentation can reach out to, and a semi-phenomenological predictive tool is proposed to fill this gap. The key idea here is to calibrate the parameters of a partial differential equation model presumably to work during the whole SCC life span against experimentally obtainable information, and then to make predictions over SCC indices that are not experimentally reachable. Experimental studies are also conducted to measure the crack growth rates under ten working conditions of interest. Upon calibration, the proposed predictive tool can deliver, within a few seconds on a normal laptop, the evolution profile of crack throughout the whole SCC process. As a rather aggressive case in PWR, the SCC crack initiation time of a 20% cold worked 690 weld joint bearing a 0.5 mm-deep scratch is predicted to be similar to 40 years under an applied load of 200 MPa. With the calibrated model, an explicit formula to predict the PWSCC crack incubation time of 690 weld joints is finally given against various aqueous, mechanical, metallurgical and geometric factors.
关键词	Pressurised water stress corrosion cracking Inconel 690 alloy 690 weld joints Crack growth rate Dynamics model Crack initiation
资助者	National Natural Science Foundation of China ; Youth Innovation Promotion Association CAS
DOI	10.1016/j.jnucmat.2024.155560
收录类别	SCI
语种	英语
资助项目	National Natural Science Foundation of China[12102416] ; National Natural Science Foundation of China[12172074] ; Youth Innovation Promotion Association CAS[2022187]
WOS研究方向	Materials Science ; Nuclear Science & Technology
WOS类目	Materials Science, Multidisciplinary ; Nuclear Science & Technology
WOS记录号	WOS:001391964800001
出版者	ELSEVIER
引用统计
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/180808
专题	中国科学院金属研究所
通讯作者	Ming, Hongliang; Zhu, Yichao
作者单位	1.Nucl Power Inst China, Natl Key Lab Nucl Reactor Technol, Chengdu 610213, Peoples R China 2.Dalian Univ Technol, Dept Engn Mech, Dalian 116023, Peoples R China 3.Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Liaoning Key Lab Safety & Assessment Tech Nucl Mat, Shenyang 110016, Peoples R China 4.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China 5.Dalian Univ Technol, State Key Lab Struct Anal Optimizat & CAE Software, Dalian, Peoples R China
推荐引用方式 GB/T 7714	Li, Hui,Li, Gang,Sun, Wei,et al. Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints[J]. JOURNAL OF NUCLEAR MATERIALS,2025,605:13.
APA	Li, Hui.,Li, Gang.,Sun, Wei.,Shao, Xuejiao.,Ma, Guowen.,...&Zhu, Yichao.(2025).Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints.JOURNAL OF NUCLEAR MATERIALS,605,13.
MLA	Li, Hui,et al."Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints".JOURNAL OF NUCLEAR MATERIALS 605(2025):13.