The single effect of microstructure, residual strain and geometric structure on the stress corrosion cracking behavior of scratched alloy 690TT
Source abstract
Abstract
Scratched area on alloy 690TT were treated by relief annealing (RA) and solution annealing plus thermal treatment (SATT), respectively, and then detailed characterization and immersion tests in simulated pressurized water reactor environment were carried out. RA reduces residual strain but not changes microstructure stratification, which causes stress corrosion cracking (SCC). SATT eliminates both strain and microstructure stratification, preventing SCC. Meanwhile, the independent effects of geometric structure, strain and microstructure on SCC behavior were investigated. Specifically, geometric structure is necessary but not sufficient for crack initiation. While the residual strain mainly enhances propagation, and the microstructure promotes both initiation and propagation.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Hydrogen embrittlement and corrosion behaviors in metals · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (51)
Show source-provided references
1. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
2. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: part 110.5006/1.3277522 ↗
3. A high-resolution characterization of the initiation of stress corrosion crack in Alloy 690 in simulated pressurized water reactor primary water10.1016/j.corsci.2019.108243 ↗
4. The effect of grain boundary structure on the intergranular degradation behavior of solution annealed alloy 690 in high temperature, hydrogenated water10.1016/j.actamat.2019.10.041 ↗
5. The effect of cold rolling on grain boundary structure and stress corrosion cracking susceptibility of twins in alloy 690 in simulated PWR primary water environment10.1016/j.corsci.2017.11.002 ↗
6. Understanding the microstructure evolution of Ni-based superalloy within two different fretting wear regimes in high temperature high pressure water10.1016/j.scriptamat.2019.05.037 ↗
7. Oconee nuclear power station main steam line break analysis for steam generator tube stress evaluation10.13182/NT04-A3547 ↗
8. Effects of scratching on corrosion and stress corrosion cracking of Alloy 690TT at 58 degrees C and 330 degrees C10.1016/j.corsci.2009.07.015 ↗
9. Localized corrosion behavior of scratches on nickel-base Alloy 690TT10.1016/j.electacta.2010.08.028 ↗
10. Size effect of scratches on the degradation behavior of alloy 690TT in high temperature caustic solution10.1016/j.corsci.2021.109314 ↗
11. Insights into the SCC crack tip of Alloy 690TT in caustic solution at high temperature10.1016/j.jnucmat.2021.153034 ↗
12. Effect of surface scratch depth on microstructure change and stress corrosion cracking behavior of alloy 690TT steam generator tube10.1016/j.corsci.2021.109792 ↗
13. Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking10.1016/j.jmst.2021.11.009 ↗
14. Stress corrosion behavior of scratched Alloy 690TT steam generator tube in chlorine‐containing high‐temperature pressurized water10.1002/maco.202213215 ↗
15. Trans-twins stress corrosion cracking behaviors of Alloy 690TT in lead-containing caustic solution at 330°C10.1016/j.nucengdes.2011.09.025 ↗
16. Effects of surface state and applied stress on stress corrosion cracking of alloy 690TT in lead-containing caustic solution10.1016/S1005-0302(12)60131-5 ↗
17. Oxide properties of deformed Alloy 690TT in caustic solution at high temperature10.1016/j.corsci.2020.108806 ↗
18. Stress corrosion cracking testing of inconel alloys 600 and 690 under high-temperature caustic conditions10.5006/1.3584917 ↗
19. Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect10.1016/j.jnucmat.2022.153629 ↗
20. High density nano-scale twins in Cu induced by dynamic plastic deformation10.1016/j.scriptamat.2005.05.022 ↗
21. Formation of slip bands and microstructure evolution of Ti-5Al-5Mo-5V–3Cr-0.5Fe alloy during warm deformation process10.1016/j.jallcom.2018.08.097 ↗
22. Dislocation behaviour and the formation of persistent slip bands in fatigued copper single crystals observed by high-voltage electron microscopy10.1080/01418618308243124 ↗
23. Experimental study of the thermal stability of dislocation structures produced through cyclic deformation in copper polycrystals10.1016/S1359-6462(98)00188-2 ↗
24. Microband formation in shock-loaded and quasi-statically deformed metals10.1016/0001-6160(89)90206-X ↗
25. High-strain-rate deformation: mechanical behavior and deformation substructures induced10.1146/annurev-matsci-070511-155034 ↗
26. Formation of annealing twins in f.c.c. crystals10.1016/S1359-6454(96)00336-9 ↗
27. An investigation of the origin and growth of annealing twins10.1016/0001-6160(63)90195-0 ↗
28. The formation of annealing twins10.1016/0001-6160(69)90004-2 ↗
29. Flow localization in cold–rolled α-brass10.1179/mst.1986.2.6.552 ↗
30. Coincidence Site Lattice (CSL) grain boundaries and Goss texture development in Fe-3% Si alloy10.1016/S1359-6454(96)00140-1 ↗
31. The coincidence site lattice and the ‘sigma enigma’10.1016/S1044-5803(02)00193-6 ↗
32. Insights into stress corrosion cracking in scratched area of alloy 690TT steam generator tubes10.1016/j.actamat.2023.119083 ↗
33. On the determination of residual stress and strain fields by sharp indentation testing10.1016/S1359-6454(01)00122-7 ↗
34. The effect of prior deformation on stress corrosion cracking growth rates of Alloy 600 materials in a simulated pressurized water reactor primary water10.1016/j.corsci.2007.07.012 ↗
35. Plastic strain characterization in austenitic stainless steels and nickel alloys by electron backscatter diffraction10.1016/j.jnucmat.2010.11.092 ↗
36. Improving the intergranular corrosion resistance of 304 stainless steel by grain boundary network control10.1016/j.corsci.2011.02.005 ↗
37. Control of grain boundary connectivity based on fractal analysis for improvement of intergranular corrosion resistance in SUS316L austenitic stainless steel10.1016/j.actamat.2015.08.075 ↗
38. Characterization of microstructure, local deformation and microchemistry in Alloy 690 heat-affected zone and stress corrosion cracking in high temperature water10.1016/j.jnucmat.2015.06.025 ↗
39. Combined effect of special grain boundaries and grain boundary carbides on IGSCC of Ni–16Cr–9Fe–xC alloys10.1016/S0921-5093(00)01705-6 ↗
40. Optimization of grain boundary character distribution for intergranular corrosion resistant 304 stainless steel by twin-induced grain boundary engineering10.1016/S1359-6454(02)00064-2 ↗
41. Twin-induced grain boundary engineering for 316 austenitic stainless steel10.1016/j.actamat.2006.06.030 ↗
42. The relationship between microstructure, deformation behavior, and stress corrosion cracking resistance of an age-hardened Ni-base alloy10.1007/BF02676984 ↗
43. Microstructural Characterization of SCC crack tip and oxide film for SUS 316 stainless steel in simulated PWR primary water at 320°C10.1080/18811248.2005.9726383 ↗
44. Insights into the superior stress corrosion cracking resistance of FeCrAl alloy in high temperature hydrogenated water: the critical role of grain boundary oxidation10.1016/j.corsci.2022.110668 ↗
45. The intergranular oxidation behavior of low-angle grain boundary of alloy 600 in simulated pressurized water reactor primary water10.1016/j.actamat.2021.117533 ↗
46. Insights into the stress corrosion cracking of solution annealed alloy 690 in simulated pressurized water reactor primary water under dynamic straining10.1016/j.actamat.2018.04.002 ↗
47. Intergranular attack and intergranular stress corrosion cracking of Alloy 690 TT in high temperature lead-containing caustic solution10.1002/maco.201005725 ↗
48. Secondary side corrosion in steam generator tubes: lessons learned in France from the in-service inspection results10.1016/S0029-5493(96)01366-0 ↗
49. R.W. Staehle, Quantitative Micro-Nano (QMN) Approach to SCC Mechanism and Prediction-Starting a Third Meeting, in: 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems‐Water Reactors, 2012, pp. 1535–1625.10.1002/9781118456835.ch161 ↗
50. Andresen · 2011 · 161
51. Microscopic residual stresses beneath a scratch and their effects on scratch-related crack initiation of thermally treated uns n06690 in high-temperature pressurized water10.5006/0858 ↗