Stress corrosion cracking of Alloy X-750 in a CO-CO2 reducing gas mixture
Source abstract
Abstract
Primary water stress corrosion cracking (PWSCC) of Alloys 600 and X-750 is believed to occur via a preferential intergranular oxidation (PIO) mechanism, in which only the alloying elements are oxidized, leaving Ni metallic. Superheated H₂-steam has been used as an accelerated environment for PWSCC studies, supported by comparable Arrhenius activation energies. Since the PIO model does not require an aqueous solution, this study investigates the occurrence of PIO and SCC in Alloy X-750 exposed to a 480 °C CO–CO₂ mixture. Post-experiment nanoscale characterization of fractured samples revealed characteristics consistent with PWSCC, including PIO and Ni enrichment, accompanied by cavity formation.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · High-Temperature Coating Behaviors · High Temperature Alloys and Creep
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (95)
Show source-provided references
1. Nickel alloys: Properties and characteristics
2. Nickel and its alloys
3. Ni-based alloys for reactor internals and steam generator applications
4. Stein · 1990
5. Stein · 1991
6. Domian · 1989
7. Selective internal oxidation in Ni-Cr-Fe alloys during exposure in hydrogenated steam
8. Internal oxidation as a mechanism for steam generator tube degradation
9. An overview of internal oxidation as a possible explanation of intergranular stress corrosion cracking of Alloy 600 in PWRs
10. General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants10.1016/j.jnucmat.2019.04.023 ↗
11. C.J. Wood and D.M. Wells, “Water chemistry control in LWRs,” in Comprehensive Nuclear Materials, 2nd ed., R. J. M. Konings, Ed., 2020.10.1016/B978-0-12-803581-8.11752-7 ↗
12. Coriou · 1960
13. Investigation of tube failures in Inconel 600 steam generator tubing at KWO Obrigheim
14. Influence de la contrainte, des traitements thermiques et des couplages sur la fissuration intergranulaire des alliages 1nconel 600 et X 75010.1016/0022-3115(75)90152-X ↗
15. T.M. Anderson, “Reactor internals - Cracked pins and flexures in guide tubes - Westinghouse communication NS-TMA-2099 to the US Nuclear Regulatory Commission,” 1979.
16. “In search of the true temperature and stress intensity factor dependencies for PWSCC,”
17. Influence of hydrogen partial pressure on the IGSCC behavior of Alloy 600 tubing in 360 °C water or 400 °C steam
18. Metallurgical improvements for enhanced stress corrosion performance of light water reactor structural materials10.1007/BF02833406 ↗
19. Fastener and bolting material for Westinghouse design internals
20. Stress corrosion cracking of age-hardenable nickel base alloys in high temperature water
21. Materials reliability program: Pressurized water reactor internals inspection and evaluation guidelines
22. Effect of heat treatment on stress corrosion cracking resistance of high nickel alloys in high temperature water
23. S. Fyfitch, H. Xu, K. Moore, R. Gurdal, and H.T. Tang, “Materials reliability program: PWR internals material aging degradation mechanism screening and threshold values (MRP-175),” Palo Alto, CA, 2005.
24. Influence of the surface condition on the susceptibility of alloy X-750 to crack initiation in PWR primary water
25. The effect of heat treatment on the microstructure and corrosion resistance of Inconel X-750 alloy10.1016/0010-938X(85)90011-3 ↗
26. Microstructure and stress corrosion resistance of Alloys X750, 718, and A286 in light water reactor environments10.1007/BF02833701 ↗
27. Some possible mechanisms of intergranular stress corrosion cracking of Alloy 600 in PWR primary water
28. Internal oxidation10.1179/mst.1988.4.12.1072 ↗
29. Advanced microstructural characterization of the intergranular oxidation of Alloy 60010.1016/j.corsci.2015.08.010 ↗
30. Effect of temperature on the preferential intergranular oxidation susceptibility of thermally-treated Alloy 60010.1016/j.corsci.2022.110565 ↗
31. Internal oxidation of Alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment10.1016/j.corsci.2014.04.041 ↗
32. Effects of boundary migration and pinning particles on intergranular oxidation revealed by 2D and 3D analytical electron microscopy10.1016/j.actamat.2017.04.003 ↗
33. Correlation between grain boundary migration and stress corrosion cracking of Alloy 600 in hydrogenated steam10.1016/j.actamat.2020.01.020 ↗
34. A review of oxidation phenomena in Ni alloys exposed to hydrogenated steam below 500°C10.5006/1957 ↗
35. Advanced TEM characterization of stress corrosion cracking of Alloy 600 in pressurized water reactor primary water environment10.1016/j.jnucmat.2009.06.014 ↗
36. High-resolution characterization of intergranular attack and stress corrosion cracking of Alloy 600 in high-temperature primary water10.5006/1.3280561 ↗
37. Understanding the role of diffusion induced grain boundary migration on the preferential intergranular oxidation behaviour of Alloy 600 via advanced microstructural characterization10.1016/j.actamat.2019.06.021 ↗
38. The effect of residual stress on the preferential intergranular oxidation of Alloy 60010.1016/j.corsci.2016.05.022 ↗
39. IGSCC behavior of Alloy 600 steam generator tubing in water or steam tests above 360 C10.5006/1.3583859 ↗
40. CANDU pressure tube leak detection by annulus gas dew point measurement: A critical review10.3139/124.110674 ↗
41. Chaplin · 2014
42. L. Marc, P. Nandu, and S. Basma, “The technology of CANDU fuel channels,” AECL 108US-31100-LS-001 Revision 0, 2012.
43. The Effect of irradiation on Ni-containing components in CANDU® reactor cores: A review10.12943/ANR.2013.00001 ↗
44. Intergranular fracture in irradiated Inconel X-750 containing very high concentrations of helium and hydrogen10.1016/j.jnucmat.2014.10.008 ↗
45. Microstructural evolution of CANDU spacer material Inconel X-750 under in situ ion irradiation10.1016/j.jnucmat.2013.06.034 ↗
46. Effect of ion implantation on the grain boundary strength of heat treated Inconel X75010.1016/j.jnucmat.2019.01.013 ↗
47. The effects of irradiation on Inconel X-750
48. Preferential intergranular oxidation as a potential degradation mechanism for Alloy X-750CANDU spacers
49. Understanding preferential intergranular oxidation in Alloy X-750 in 480 °C CO-CO2 environments at the nanoscale10.1016/j.corsci.2024.112496 ↗
50. Pilkey · 2005
51. Sun · 2012
52. 2001
53. Assessment of fitness for service
54. 2005
55. 2007
56. Special Metals, “Inconel alloy X-750,” 2004.
57. Ballinger · 1993
58. Jackson · 2012
59. Effect of temperature on the fracture toughness behavior of Inconel X-750
60. Alloy oxidation studies related to PWSCC
61. Thermodynamic equivalence charts for stress corrosion cracking studies in hydrogenated steam, high pressure and supercritical water10.1149/1945-7111/abd570 ↗
62. Effect of a pressurised CO2 environment on deformation and failure behaviour of type 316H stainless steel under steady and cyclic creep conditions
63. Factors affecting the oxidation and carburisation behaviour of an austenitic stainless steel used in the UK advanced gas-cooled reactors
64. Characterization of oxide structures formed on nickel-chromium alloy during low pressure oxidation at 500 - 600°C10.1007/BF00666809 ↗
65. Internal oxidation of Alloy 690 in hydrogenated steam10.1016/j.corsci.2014.11.006 ↗
66. Characterization of stress corrosion cracking initiation precursors in cold-worked Alloy 690 using advanced high-resolution microscopy10.5006/3051 ↗
67. A mechanistic study of SCC in Alloy 600 through high-resolution characterization10.1016/j.corsci.2018.01.004 ↗
68. Grain boundary selective oxidation and intergranular stress corrosion crack growth of high-purity nickel binary alloys in high-temperature hydrogenated water10.1016/j.corsci.2017.11.024 ↗
69. Examinations of oxidation and sulfidation of grain boundaries in Alloy 600 exposed to simulated pressurized water reactor primary water10.1017/S1431927613000421 ↗
70. Effect of heat treatment, cold working and long-term ageing in air on the stress corrosion cracking growth rate in simulated PWR primary water for commercial TT Alloy 690 and Alloy
71. Microstructure of nickel-based superalloys10.1002/pssb.19690350102 ↗
72. Effect of grain boundary denudation of gamma prime on notch-rupture ductility of Inconel nickel-chromium Alloys X-750 and 718
73. Internal oxidation of Ag-In alloys: Stress relief and the influence of imposed strain10.1007/BF00664274 ↗
74. Characterization of SCC crack tip in Alloy 600 in simulated primary water of PWR
75. Internal oxidation of Alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment10.1016/j.corsci.2014.04.041 ↗
76. The mechanism and modeling of intergranular SCC of Ni-Cr-Fe alloys exposed to high purity water
77. Fish · 1997
78. Effect of chemical compositions and heat treatment conditions on the SCC resistance of nickel-based high-strength alloys
79. Structure, chemistry, and stress corrosion cracking of grain boundaries in Alloys 600 and 69010.1007/BF02648410 ↗
80. Stress corrosion cracking of Alloy 600 and Alloy 690 in hydrogen/steam at 380 °C10.1016/S0010-938X(97)86103-3 ↗
81. Degradation of Alloy 690 after relatively short times10.5006/2107 ↗
82. Linking grain boundary microstructure to stress corrosion cracking of cold-rolled Alloy 690 in pressurized water reactor primary water10.5006/0808 ↗
83. Betten · 2008
84. Creep cavitation in metals10.1016/S0749-6419(02)00111-0 ↗
85. Frost · 1982
86. The creep rupture behavior of notched bars of IN-X750
87. Stress corrosion crack initiation in Alloy 690 in high temperature water10.1016/j.cossms.2018.02.001 ↗
88. On the role of intergranular carbides on improving the stress corrosion cracking resistance in a cold-worked Alloy 60010.1016/j.jnucmat.2018.11.020 ↗
89. Alloy 690 SCC growth rate testing
90. The stress corrosion cracking behavior of Alloys 690 and 152 weld in a PWR environment
91. SCC of Alloy 690 and its weld metals
92. One-dimensional cold rolling effects on stress corrosion crack growth in Alloy 690 tubing and plate materials
93. J. Hickling and K. Ahluwalia, “Materials Reliability Program: Resistance of Alloys 690, 52 and 152 to Primary Water Stress Corrosion Cracking (MRP-237, Rev. 1),” Palo Alto, CA, 2008.
94. T. Yonezawa et al., “Effect of heat treatment on corrosion resistance of Alloy 690,” in Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Monterey, CA, USA, 1985, pp. 593–600.
95. Zhai · 2016