journal article·2025-01

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

Jiamei Wang, Tianyu Zhu, Yule Wu, Kai Chen, Xianglong Guo, Quanyao Ren, Yuanming Li, Chuanbao Tang, Hongpu Yi, Liang Ye, Shihao Xu, Jing Zhang, Wenxi Tian, Lefu Zhang

Corrosion Science· Volume 242
Publisher page

Abstract

The stress corrosion cracking (SCC) propagation behavior of solution-annealed and precipitation-hardened Alloy 718 was investigated. The results show γ″ and γ′ 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.
Source: expertdata · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Nuclear Materials and Properties · Fusion materials and technologies

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (88)

Show source-provided references
1. Gussev, Maxim, N., Busby, Jeremy, T., Leonard, Keith, J., Stevens. Analysis of stress corrosion cracking in alloy 718 following commercial reactor exposure. Journal of Nuclear Materials: Materials Aspects of Fission and Fusion (2015).
2. H. Jang, J.D. Hong, S.S. Kim, K.B. Eom, O.H. Kwon, C. Jang IGSCC of INCONEL 718 hold down spring in 400 oC steam environment. (2011).
3. Influence of δ phase precipitation on the stress corrosion cracking resistance of alloy 718 in PWR primary water10.1016/j.jnucmat.2008.09.018 ↗
4. M.G. Burke, T.R. Mager, M.T. Miglin, J.L. Nelson. The Effect of Thermal Treatment on SCC of Alloy 718: A Structure-Properties Study. Superalloys1994.10.7449/1994/Superalloys_1994_763_773 ↗
5. Microstructure and stress corrosion resistance of alloys X750, 718, and A286 in light water reactor environments10.1007/BF02833701 ↗
6. The effect of heat treatment on microfissuring in alloy 718
7. The roles of thermal mechanical treatment and δ phase in the stress corrosion cracking of alloy 718 in primary water10.1016/j.corsci.2019.108168 ↗
8. Effect of temperature on hydrogen embrittlement susceptibility of alloy 718 in light water reactor environment10.1016/j.ijhydene.2017.06.211 ↗
9. Hydrogen embrittlement in nickel-based superalloy 718: Relationship between γ′ + γ″ precipitation and the fracture mode10.1016/j.ijhydene.2015.07.053 ↗
10. Alloy 718 for oilfield applications10.1007/s11837-012-0238-z ↗
11. 4 - Environmentally-assisted cracking of nickel-base alloys in light water reactors
12. Environmentally assisted cracking of high strength nickel based alloys
13. SCC of high strength Ni-base alloys in high temperature water
14. 7 - Stress corrosion cracking (SCC) of nickel-based alloys
15. In-situ observation of hydrogen induced crack initiation in a nickel-based superalloy10.1016/j.scriptamat.2017.07.006 ↗
16. J.N. Stevens, K.J. Leonard, M.N. Gussev, G. Ilevbare, J.L. Nelson. HOLD DOWN SPRING FAILURE ANALYSIS. International conference on environmental degradation of materials in nuclear power systems-water reactors 2015..
17. Katayama · 2011
18. S.K. Koh. Stress Corrosion Cracking Life Estimation of Hold-down Spring Screw for Nuclear Fuel Assembly. Asian Pacific Conference Fracture and Strength2005.10.4028/0-87849-978-4.1834 ↗
19. A. Venkatesh. Effects of metallurgical and environmental variables on the performance of alloy 718 for heat exchanger applications. University of Nevada, Las Vegas.; 2008.
20. G. Sjoberg, N.G. Ingesten, R.G. Carlson. Grain Boundary δ-Phase Morphologies, Carbides and Notch Rupture Sensitivity of Cast Alloy 718. (1991).10.7449/1991/Superalloys_1991_603_620 ↗
21. Effects of precipitation on the stress corrosion crack initiation of alloy 718 in simulated pressurized water reactor primary environment
22. Stress corrosion cracking of chemistry and heat treat variants of alloy 718
23. K.J. Leonard, M.N. Gussev, J.N. Stevens, J.T. Busby. Characterization of Materials Properties and Crack Propagation Mechanisms in Damaged Alloy 718 Leaf Springs Following Commercial Reactor Exposure. International conference on environmental degradation of materials in nuclear power systems-water reactors2015.
24. P.L. Andresen. S.C.C. Growth Rate of Stainless Steels in Pressurized Water Reactor Primary Water. Personal communication 2022.
25. The influence of ppb levels of chloride impurities on the stress corrosion crack growth behaviour of low-alloy steels under simulated boiling water reactor conditions10.1016/j.corsci.2016.03.001 ↗
26. Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water10.1016/j.corsci.2016.04.035 ↗
27. IGSCC of non-sensitized stainless steels in high temperature water10.1016/j.jnucmat.2008.08.005 ↗
28. Dependence of stress corrosion cracking for cold-worked stainless steel on temperature and potential, and role of diffusion of vacancies at crack tips10.5006/1.3278507 ↗
29. P.W.E. Peter L. Andresen. EFFECTS OF PWR PRIMARY WATER CHEMISTRY AND DEAERATED WATER ON SCC. Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System – Water Reactors2005.
30. P.L. Andresen. Effects of yield strength, corrosion potential, stress intensity factor, silicon and grain boundary characters on the SCC of stainless steel. Am. Nucl. Soc. (2003).
31. Stress corrosion cracking of Alloy 600
32. Andresen · 2011
33. Effects of hydrogen on stress corrosion crack growth rate of nickel alloys in high-temperature water
34. D.S. Morton, S.A. Attanasio, G.A. Young. Primary Water SCC Understanding and Characterization Through Fundamental Testing in the Vicinity of the Nickel/Nickel Oxide Phase Transition. office of scientific & technical information technical reports (2001).10.2172/821310 ↗
35. D.S. Morton, S.A. Attanasio, J.S. Fish, M.K. Schurman. Influence of dissolved hydrogen on nickel alloy SCC in high temperature water. CORROSION-US (1999).10.2172/314149 ↗
36. Effect of dissolved oxygen and hydrogen on the stress corrosion cracking behavior of alloy 600 in high temperature water10.1016/j.jnucmat.2020.152603 ↗
37. δ-phase precipitation regularity of cold-rolled fine-grained GH4169 alloy plate and its effect on mechanical properties10.1016/S1003-6326(20)65461-9 ↗
38. INCONEL 718: A solidification diagram10.1007/BF02650300 ↗
39. P.L. Andresen, M.B. Toloczko, S.M. Bruemmer, B. Alexandreanu. Recommended Capabilities, Best Practices and Reporting Requirements for SCC Growth Rate Testing of Resistant Materials in PWR Primary Water, adopted by the Alloy 690/52/152 PWSCC Research Collaboration. K. Ahluwalia (Coordinator), EPRI (2004).
40. Insights into the stress corrosion cracking propagation behavior of Alloy 690 and 316 L stainless steel in KOH versus LiOH oxygenated water10.1016/j.corsci.2023.111556 ↗
41. The effect of potassium hydroxide primary water chemistry on the IASCC behavior of 304 stainless steel10.1016/j.jnucmat.2021.153323 ↗
42. P.C.P. L. Andresen. SCC initiation and growth in PWR primary water containing KOH vs. LiOH. 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2019..
43. Le-fu, Zhang, Jia-mei, Wang. High-Temperature Electrochemical Corrosion Behavior of Fe-Cr-Ni Alloys in Simulated Pressurized Water Reactor Water. Corrosion the Journal of Science & Engineering (2018).10.5006/2566 ↗
44. P.L. Andresen. Stress Corrosion Cracking Testing Guidelines: With Emphasis on High Temperature Water. EPRI, Palo Alto, CA, 2020. pp. 1292949031..
45. Investigations on the SCC initiation behavior of cold worked 316 L in high temperature oxygenated water at constant loads10.1016/j.corsci.2022.110336 ↗
46. Insights into the roles of intergranular carbides in the initiation of intergranular stress corrosion cracking of alloy 690 in simulated PWR primary water10.1016/j.corsci.2021.110048 ↗
47. Effect of δ-ferrite on the stress corrosion cracking behavior of 321 stainless steel10.1016/j.corsci.2019.07.005 ↗
48. Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water10.1016/j.corsci.2016.04.035 ↗
49. Effect of thermal aging on the environmental assisted cracking behavior of 308L weld metal in high temperature water10.1016/j.corsci.2022.110902 ↗
50. E. Andrieu, B. Max, B. Viguiera. Oxidation Assisted Intergranular Cracking in Alloy 718: Effects of Strain Rate and Temperature. (2015).
51. M.R.P.M. Stress, E. Corrosion Cracking PWSCC Of Thick-Wall Alloy Materials MRP- Revision, C. Palo Alto.
52. Materials Reliability Program: Recommended Factors of Improvement for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) Growth Rates of Thick-Wall Alloy 690 Materials and Alloy 52, 152, and Variants Welds (MRP-386). EPRI, Palo Alto, CA: 2017. 3002010756.
53. Effect of dissolved oxygen and hydrogen on stress corrosion cracking of cold worked alloy 690MA
54. Intergranular stress corrosion cracking growth behavior of Ni-Cr-Fe alloys in pressurized water reactor primary water10.5006/1205 ↗
55. Speidel · 2013
56. P.L. Andresen. Unusual cold work and strain rate effects on SCC. (2009).
57. S.M. Bruemmer, M.J. Olszta, N.R. Overman, M.B. Toloczko MICROSTRUCTURAL EFFECTS ON STRESS CORROSION CRACK GROWTH IN COLD-WORKED ALLOY 690 TUBING AND PLATE MATERIALS. 2016.
58. A study on the diffusion-induced grain boundary migration ahead of stress corrosion cracking crack tips through advanced characterization10.1016/j.corsci.2021.109328 ↗
59. The effects of intergranular carbides on the grain boundary oxidation and cracking in a cold-worked Alloy 60010.1016/j.corsci.2019.05.008 ↗
60. Observation and quantification of the diffusion-induced grain boundary migration ahead of SCC crack tips10.1016/j.corsci.2018.11.019 ↗
61. Mechanistic understanding of the temperature dependence of crack growth rate in alloy 600 and 316 stainless steel through high-resolution characterization10.1016/j.actamat.2018.11.039 ↗
62. Internal oxidation of Alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment10.1016/j.corsci.2014.04.041 ↗
63. K. Fujii, T. Miura, H. Nishioka, K. Fukuya. Degradation of Grain Boundary Strength by Oxidation in Alloy 600. 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors2011.10.1007/978-3-319-48760-1_89 ↗
64. An overview of internal oxidation as a possible explanation of intergranular stress corrosion cracking of alloy 600 in PWRS
65. SCC in PWRs: learning from a Bottom-Up Approach
66. Investigations on the SCC initiation behavior of cold worked 316 L in high temperature oxygenated water at constant loads10.1016/j.corsci.2022.110336 ↗
67. Anomalous precipitate-size-dependent ductility in multicomponent high-entropy alloys with dense nanoscale precipitates10.1016/j.actamat.2021.117480 ↗
68. J. Xu, H. John, G. Wiese, X. Liu OIL-GRADE ALLOY 718 IN OIL FIELD DRILLING APPLICATION. 2010.10.1002/9781118495223.ch70 ↗
69. Microstructures of oxidized primary carbides on superalloy inconel 71810.4028/www.scientific.net/MSF.502.249 ↗
70. Multi-scale characterization of stress corrosion cracking of cold-worked stainless steels and the influence of Cr content10.1016/j.actamat.2009.07.040 ↗
71. Microstructural characterization of SCC crack tip and oxide film for SUS 316 stainless steel in simulated PWR primary water at 320°C.10.1080/18811248.2005.9726383 ↗
72. Characterizing the effects of in-situ sensitization on stress corrosion cracking of austenitic steels in supercritical water10.1016/j.scriptamat.2018.08.041 ↗
73. Quantitative prediction of environmentally assisted cracking10.5006/1.3292125 ↗
74. Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel alloys in aqueous systems10.1016/0025-5416(88)90564-2 ↗
75. Nguejio · 2019 · 337
76. T. Shoji. Role of water chemistry and microstructure in stress corrosion cracking in the fusion boundary region of an Alloy 182-A533B low alloy steel dissimilar weld joint in high temperature water10.1016/j.corsci.2011.08.046 ↗
77. Linking grain boundary microstructure to stress corrosion cracking of cold-rolled alloy 690 in pressurized water reactor primary water10.5006/0808 ↗
78. Synergistic effects of local strain-hardening and dissolved oxygen on stress corrosion cracking of 316NG weld heat-affected zones in simulated BWR environments10.1016/j.jnucmat.2011.12.030 ↗
79. The evolution of dislocation density during heat treatment and creep of tempered martensite ferritic steels10.1016/S1359-6454(03)00324-0 ↗
80. The role of TiN inclusions in stress corrosion crack initiation for Alloy 690TT in high-temperature and high-pressure water10.1016/j.corsci.2009.11.015 ↗
81. Fracture behavior of Inconel 718 sheet in thermal-aided deformation considering grain size effect and strain rate influence10.1016/j.matdes.2017.05.089 ↗
82. Effects of nano-sized Nb carbide precipitates on the corrosion behavior of high-strength low-alloy steel in simulated seawater10.20964/2017.09.35 ↗
83. S.A. Attanasio, D.S. Morton Measurement of the Nickel/Nickel Oxide Transition in Ni-Cr-Fe Alloys and Updated Data and Correlations to Quantify the Effect of Aqueous Hydrogen on Primary Water SCC. Office of Scientific & Technical Information Technical Reports (2018).
84. How oxidized grain boundaries fail10.1016/j.actamat.2013.05.012 ↗
85. Review of progress in calculation and simulation of high-temperature oxidation
86. Autoclave grid-to-rod fretting wear behaviors of the Zr alloy fuel cladding with and without Cr coating through advanced characterization10.1016/j.corsci.2024.112379 ↗
87. The effect of LPSO phase on the high-temperature oxidation of a stainless Mg-Y-Al alloy
88. Stability of vacancy-hydrogen clusters in nickel from first-principles calculations10.1016/j.actamat.2014.06.021 ↗