Stress corrosion cracking susceptibility of thermally-aged Type 310S stainless steels in supercritical water
Source abstract
Abstract
Abstract The effect of thermal ageing on the stress corrosion cracking (SCC) susceptibility of Type 310S stainless steel in supercritical water (coolant for a supercritical water cooled reactor design concept) was evaluated. SCC was evaluated using the slow strain rate testing technique, straining samples to 10% in a flowing autoclave test facility using 25 MPa SCW at 500 °C with 20 ppm dissolved oxygen. The localized deformation model for SCC initiation and a void-assisted film-cleavage model for SCC propagation can be used to explain the SCC susceptibility exhibited by the thermally-aged Type 310S stainless steel in supercritical water.
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Research context
OpenAlex topics: Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals · High-Temperature Coating Behaviors
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (60)
Show source-provided references
1. 5.12 − Material performance in supercritical water
2. Supercritical water-cooled reactor materials –summary of research and open issues10.1016/j.pnucene.2014.02.008 ↗
3. Cycle chemistry and its effect on materials in a supercritical water-cooled reactor: a synthesis of current understanding10.1016/j.corsci.2012.08.006 ↗
4. Historical experience providing bases for predicting corrosion and stress corrosion in emerging supercritical water nuclear technology: part 1 – review10.5006/0726 ↗
5. Historical experience providing bases for predicting corrosion and stress corrosion in emerging supercritical water nuclear technology: part 3-review10.5006/0726.part3 ↗
6. Progress in corrosion resistant materials for supercritical water reactors10.1016/j.corsci.2009.07.007 ↗
7. Materials assessment for the Canadian SCWR core concept10.1007/s11837-015-1758-0 ↗
8. Microstructure instability of candidate fuel cladding alloys: corrosion and stress corrosion cracking implications10.1007/s11837-015-1739-3 ↗
9. Formation and growth morphology of oxidation-induced ferrite layer in Fe-Mn-Al-Cr-C alloys10.1007/BF01045765 ↗
10. Microstructural evolution during the austenite-to-ferrite transformation from deformed austenite10.1007/s11661-998-0122-1 ↗
11. Precipitation in creep resistant austenitic stainless steels10.1179/026708301101508972 ↗
12. Irradiation-assisted stress corrosion cracking10.1515/corrrev.2011.020 ↗
13. Microstructural evolution in annealed austenitic steels during netron irradiation10.1179/095066087790150331 ↗
14. Quantitative evaluation of aged AISI 316L stainless steel sensitization to intergranular corrosion: comparison between microstructural electrochemical and analytical methods10.1007/s11661-007-9114-9 ↗
15. Microstructural changes and corrosion resistance of AISI 310S steel exposed to 600–800C10.1016/j.matchar.2008.12.005 ↗
16. Microstructure stability of candidate stainless steels for Gen-IVSCWR fuel cladding application10.1016/j.jnucmat.2014.06.043 ↗
17. Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels10.1016/S0022-3115(02)00719-5 ↗
18. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals10.1016/S0022-3115(99)00075-6 ↗
19. Effects of irradiation on intergranular stress corrosion cracking10.1016/0022-3115(94)90019-1 ↗
20. Post-irradiation annealing of small defect clusters10.1080/02678370412331320071 ↗
21. Effect of thermal pretreatment on the corrosion of stainless steel in flowing supercritical water10.1115/1.4031125 ↗
22. Metallographic observations on the formation and occurrence of ferrite, sigma phase, and carbides in austenitic stainless steels: part i: studies of AISI type 310 stainless steel10.1016/0026-0800(70)90003-0 ↗
23. Recent developments in stainless steels10.1016/j.mser.2009.03.001 ↗
24. Phase instabilities during high temperature exposure of 316 austenitic stainless steel10.1007/BF02647659 ↗
25. Assessment of intergranular corrosion of heat treated austenitic stainless steel (AISI 316L grade) by electron microscopy and electrochemical tests10.1134/S0033173208050172 ↗
26. Irradiation-assisted stress corrosion cracking of austenitic alloys in supercritical water10.1016/j.jnucmat.2009.09.010 ↗
27. Microstructural and microchemical mechanisms controlling intergranular stress corrosion cracking in light-water-reactor systems10.1016/0022-3115(94)90020-5 ↗
28. The sigma phase10.1179/imr.1966.11.1.61 ↗
29. Inhomogeneous nano-mechanical properties in the multi-phase microstructure of long-term aged type 316 stainless steel10.1557/jmr.2006.0143 ↗
30. Effect of intermetallic precipitations on the properties of duplex stainless steel10.1016/j.matchar.2006.03.015 ↗
31. Effects of sigma and chi phases on the localized corrosion resistance of SR50A super austenitic stainless steel10.5006/0723 ↗
32. Influence of carbide precipitation and rolling direction on intergranular stress corrosion cracking of austenitic stainless steels in hydrogenated high-temperature water10.5006/1.3280670 ↗
33. Internal oxidation of alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment10.1016/j.corsci.2014.04.041 ↗
34. Dependence of stress corrosion cracking of alloy 690 on temperature, cold work, and carbide precipitation—role of diffusion of vacancies at crack tips10.5006/1.3563640 ↗
35. #xp#Effect of Thermal Ageing on the Intergranular Stress Corrosion Cracking Susceptibility of Type 310S Stainless Steel,”
36. Effect of Thermal Ageing on the Corrosion and Stress Corrosion Cracking of Type 310S Stainless Steel in Supercritical Water
37. On the role of grain boundary chemistry in the intergranular stress corrosion cracking susceptibility of 310S exposed in supercritical water
38. Constructing a grain bAoundary snnual Censitization-embrittlement monfap for ype 310S sCanadian tainless sNuclear Steel fopcuel cladding in the Canadian SCWR oncept
39. Influence of localized deformation on irradiation-assisted stress corrosion cracking of proton-irradiated austenitic alloys
40. Effect of irradiation on stress corrosion cracking in supercritical water10.1016/j.jnucmat.2007.05.008 ↗
41. Stress corrosion cracking of austenitic alloys in supercritical water10.5006/1.3278244 ↗
42. Corrosion and stress corrosion cracking in supercritical water10.1016/j.jnucmat.2007.05.017 ↗
43. Tsuchiya · 2007
44. Tsuchiya · 2004
45. Effect of physical property and chemistry of water on cracking of stainless steels in sub-critical and supercritical water10.4028/www.scientific.net/KEM.261-263.1031 ↗
46. Oxide-induced initiation of stress corrosion cracking in irradiated stainless steel10.5006/1.3284856 ↗
47. Microstructural processes of plastic instabilities in strengthened metals10.1016/0079-6425(91)90002-B ↗
48. Localized deformation and IASCC initiation in austenitic stainless steels10.1016/j.jnucmat.2008.08.032 ↗
49. Impact of localized deformation on IASCC in austenitic stainless steels10.1016/j.jnucmat.2010.10.087 ↗
50. Deformation microstructure of proton-irradiated stainless steels10.1016/j.jnucmat.2006.12.012 ↗
51. The initiation of ductile failure by fractured carbides in an austenitic stainless steel10.1016/0001-6160(67)90372-0 ↗
52. The plastic deformation and fracture of iron-3% silicon in the temperature range 295 °K–473 °K10.1016/0001-6160(66)90244-6 ↗
53. Plastic relaxation of the transformation strain energy of a misfitting spherical precipitate: ideal plastic behavior10.1007/BF02655099 ↗
54. Cavity formation from inclusions in ductile fracture10.1007/BF02672306 ↗
55. Change in bonding strength at grain boundaries before long term SCC initiation
56. Formation of cavities prior to crack initiation and growth on cold-worked carbon steel in high-temperature water10.5006/1.3318289 ↗
57. Characterizing the effect of creep on stress corrosion cracking of cold worked alloy 690 in supercritical water environment10.1016/j.jnucmat.2017.05.018 ↗
58. Emerging issues and fundamental processes in environmental cracking in hot water10.5006/1.3278483 ↗
59. Environmentally induced crack nucleation and brittle fracture10.1016/0001-6160(82)90094-3 ↗
60. Brittle behavior of ductile metals during stress-corrosion cracking10.1080/01418618508245272 ↗