Review on crack growth driving force at the tip of stress corrosion cracking in the safe end dissimilar metal welded joint

被引:2
作者
Wang, Zheng [1 ]
Xue, Yuxuan [1 ,2 ]
Wang, Rongxin
Wu, Jun [1 ]
Zhang, Yubiao [1 ]
Xue, He [1 ]
机构
[1] Xian Univ Sci & Technol, Sch Mech Engn, 58 Yanta Middle Rd, Xian 710054, Peoples R China
[2] Univ Hong Kong, Dept Ind & Mfg Syst Engn, Hong Kong, Peoples R China
基金
中国国家自然科学基金;
关键词
Stress corrosion cracking (SCC); Mechanical state at the Crack tip; Crack growth driving force; One overload; Multiscale; Multi-field coupling; AUSTENITIC STAINLESS-STEEL; PWR PRIMARY WATER; QUANTITATIVE PREDICTION; MECHANICAL-PROPERTIES; HEAT-TREATMENT; STRAIN-RATE; ENVIRONMENTAL CRACKING; FRACTURE-RESISTANCE; BASE ALLOYS; BEHAVIOR;
D O I
10.1016/j.nucengdes.2024.113609
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 welded structural materials of nuclear power plants (NPPs) are susceptible to environmentally-assisted cracking (EAC), represented by stress corrosion cracking (SCC), in prolonged high-temperature and high-pressure water environments, posing a significant threat to plant safety. This study aims to provide a critical review for the crack growth driving force at the tip of SCC in the safe end dissimilar metal welded joint (DMWJ) of NPPs. Firstly, SCC's background, importance, and current research status are introduced. Secondly, a review and analysis are conducted on SCC's initiation and growth stages, focusing on experimental methods, predictive models of crack growth rate, crack tip mechanical states, and influencing factors, clarifying the main achievements and challenges in current experimental and theoretical research. Finally, a method to mitigate crack tip driving force is proposed, followed by an in-depth analysis from a mechanical perspective on the relationship between crack growth driving force and crack growth resistance, highlighting future research trends. This review provides theoretical references and technical support for addressing the issue of SCC in welded structural materials of NPP primary circuit.
引用
收藏
页数:17
相关论文
共 99 条
[71]  
Shoji T, 2008, Environment-Induced Cracking of Materials, P107, DOI DOI 10.1016/B978-008044635-6.50051-0
[72]   Formulating stress corrosion cracking growth rates by combination of crack tip mechanics and crack tip oxidation kinetics [J].
Shoji, Tetsuo ;
Lu, Zhanpeng ;
Murakami, Hiroyoshi .
CORROSION SCIENCE, 2010, 52 (03) :769-779
[73]   Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels [J].
Song, Miao ;
Wang, Mi ;
Lou, Xiaoyuan ;
Rebak, Raul B. ;
Was, Gary S. .
JOURNAL OF NUCLEAR MATERIALS, 2019, 513 :33-44
[74]   Mechanical properties-micro structure correlation in neutron irradiated heat-affected zones of austenitic stainless steels [J].
Stoenescu, R. ;
Schaeublin, R. ;
Gavillet, D. ;
Baluc, N. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 362 (2-3) :287-292
[75]   Stress corrosion cracking growth rate prediction model for nuclear power turbine rotor steel in a simulated environment [J].
Su, Tian ;
Huang, Yuhui ;
Xuan, Fu-Zhen .
JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T, 2023, 23 :830-844
[76]   SCC growth behaviors of austenitic stainless steels in simulated PWR primary water [J].
Terachi, T. ;
Yamada, T. ;
Miyamoto, T. ;
Arioka, K. .
JOURNAL OF NUCLEAR MATERIALS, 2012, 426 (1-3) :59-70
[77]   A phase field method for modeling stress corrosion crack propagation in a nickel base alloy [J].
Thanh-Tung Nguyen ;
Bolivar, Jose ;
Rethore, Julien ;
Baietto, Marie-Christine ;
Fregonese, Marion .
INTERNATIONAL JOURNAL OF SOLIDS AND STRUCTURES, 2017, 112 :65-82
[78]   Failures and leak inspection techniques of tube-to-tubesheet joints: A review [J].
Thekkuden, Dinu Thomas ;
Mourad, Abdel-Hamid Ismail ;
Bouzid, Abdel-Hakim .
ENGINEERING FAILURE ANALYSIS, 2021, 130
[79]  
Tsubota M., 2005, PROC 12 INT C EDM NU, P109, DOI [10.1016/j.corsci.2022.110179, DOI 10.1016/J.CORSCI.2022.110179]
[80]   Fracture mechanism of a dissimilar metal welded joint in nuclear power plant [J].
Wang, H. T. ;
Wang, G. Z. ;
Xuan, F. Z. ;
Tu, S. T. .
ENGINEERING FAILURE ANALYSIS, 2013, 28 :134-148