The effect of nano-sized precipitates on stress corrosion cracking propagation of Alloy 718 under constant loads in PWR primary water

被引:0
|
作者
Wang, Jiamei [1 ]
Zhu, Tianyu [1 ]
Wu, Yule [1 ]
Chen, Kai [1 ]
Guo, Xianglong [1 ]
Ren, Quanyao [2 ]
Li, Yuanming [2 ]
Tang, Chuanbao [2 ]
Yi, Hongpu [2 ]
Ye, Liang [4 ]
Xu, Shihao [4 ]
Zhang, Jing [3 ]
Tian, Wenxi [3 ]
Zhang, Lefu [1 ]
机构
[1] Shanghai Jiao Tong Univ, Sch Nucl Sci & Engn, Shanghai 200240, Peoples R China
[2] Nucl Power Inst China, Sci & Technol Reactor Syst Design Technol Lab, Chengdu 610213, Peoples R China
[3] Xi An Jiao Tong Univ, Sch Energy & Power Engn, Xian 710049, Peoples R China
[4] China Nucl Power Technol Res Inst Co Lto, Shenzhen 518000, Peoples R China
关键词
Alloy; 718; Precipitates; Stress corrosion cracking; Crack growth rate; TEM; TKD; STAINLESS-STEEL; HYDROGEN EMBRITTLEMENT; HEAT-TREATMENT; NICKEL-ALLOYS; GROWTH RATE; TEMPERATURE; SCC; BEHAVIOR; MICROSTRUCTURE; PREDICTION;
D O I
10.1016/j.corsci.2024.112577
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The stress corrosion cracking (SCC) propagation behavior of solution-annealed and precipitation-hardened Alloy 718 was investigated. The results show gamma '' and gamma ' precipitates are beneficial on retarding its crack growth under constant loads. Nano-sized precipitates at grain boundary (GB) tend to impede GB migration and oxidation beyond the crack tip, thereby compensating for the detrimental effect of a steeper strain gradient resulting from prominent elevated yield strength. The observed 2-40 times increase in CGR in hydrogenated water (near the Ni/ NiO boundary) primarily attributes to the preferential GB oxidation and instability of the oxides during phase transition.
引用
收藏
页数:15
相关论文
共 50 条
  • [21] Assessing the influence of welding-induced mechanics on oxidation and stress corrosion cracking in an Alloy 600-Alloy 152 M weldment under simulated PWR primary water
    Xu, Xinhe
    Pan, Deng
    Li, Entong
    Lu, Zhanpeng
    Cui, Tongming
    Chen, Junjie
    Zheng, Hui
    Li, Kai
    Lozano-Perez, Sergio
    Shoji, Tetsuo
    JOURNAL OF NUCLEAR MATERIALS, 2024, 601
  • [22] Application of Nano-Sized TiO2 as an Inhibitor of Stress Corrosion Cracking in the Steam Generator Tube Materials
    Kim, Kyung Mo
    Lee, Eun Hee
    Kim, Uh Chul
    Choi, Byung Seon
    JOURNAL OF NANOSCIENCE AND NANOTECHNOLOGY, 2010, 10 (01) : 175 - 179
  • [23] Combined effects of lead and magnetite on the stress corrosion cracking of alloy 600 in simulated PWR secondary water
    Song, Geun Dong
    Choi, Won-Ik
    Jeon, Soon-Hyeok
    Kim, Jung Gu
    Hur, Do Haeng
    JOURNAL OF NUCLEAR MATERIALS, 2018, 512 : 8 - 14
  • [24] PROBABILISTIC ENVIRONMENTALLY ASSISTED CRACKING MODELING FOR PRIMARY WATER STRESS CORROSION CRACKING OF ALLOY 600
    Lee, TaeHyun
    Yoon, JaeYoung
    Nam, HyoOn
    Hwang, IlSoon
    15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 2011, : 1715 - 1727
  • [25] Characterization of internal and intergranular oxidation in Alloy 690 exposed to simulated PWR primary water and its implications with regard to stress corrosion cracking
    Lim, Yun Soo
    Kim, Dong Jin
    Kim, Sung Woo
    Hwang, Seong Sik
    Kim, Hong Pyo
    MATERIALS CHARACTERIZATION, 2019, 157
  • [26] Primary water stress corrosion cracking behavior of an Alloy 600/182 weld
    Lim, Yun Soo
    Hwang, Seong Sik
    Kim, Sung Woo
    Kim, Hong Pyo
    CORROSION SCIENCE, 2015, 100 : 12 - 22
  • [27] Effect of dissolved hydrogen concentration in simulated PWR primary water on stress corrosion cracking susceptibility of ni-based alloy at 290°C and 320°C
    Kobayashi T.
    Yonezawa T.
    Dozaki K.
    Hisamune K.
    Sugino W.
    Sato K.
    Transactions of the Atomic Energy Society of Japan, 2016, 15 (01) : 21 - 31
  • [28] Effect of material chemical composition on oxidation and stress corrosion cracking of the submerged arc welding Alloy 52M overlay in a simulated PWR primary water
    Xu, Xinhe
    Jia, Yibo
    Pan, Deng
    Cui, Tongming
    Lu, Zhanpeng
    Lozano-Perez, Sergio
    Chen, Junjie
    Li, Shuangyan
    Shoji, Tetsuo
    JOURNAL OF NUCLEAR MATERIALS, 2024, 588
  • [29] General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants
    Scott, Peter M.
    Combrade, Pierre
    JOURNAL OF NUCLEAR MATERIALS, 2019, 524 : 340 - 375
  • [30] Effect of solid solution carbon on stress corrosion cracking of Alloy 600 in a primary water at 360 °C
    Hur, Do Haeng
    Lee, Deok Hyun
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2014, 603 : 129 - 133