journal article·2026-03Open access

Effect of stress on lead induced stress corrosion cracking of Inconel Alloy 690TT steam generator tube

Zhenhua Li, Yongming Han, Lei You, Long Wang, Yonghao Lu

Abstract

This study systematically investigated the effect of stress levels on the lead-induced stress corrosion cracking (PbSCC) behavior of Alloy 690TT in high temperature lead-containing caustic solution using the C-ring stress corrosion test method. Results demonstrated that although high stress level did not change the initiation time, it significantly increased the probability of crack initiation. Furthermore, during the crack propagation stage, the high stress level greatly accelerated the crack growth rate, resulting in a higher number of cracks and greater crack lengths. Microscopic mechanism analysis revealed that lead deposited at the metal-oxide interface, inhibiting repassivation and promoting the selective dissolution of Cr and Fe, thereby leading to the formation of a brittle Ni-rich zone. This process followed the mechanism of lead-induced repassivation inhibition-dealloying embrittlement. High stress increased the probability of crack initiation by exacerbating local plastic deformation to damage the oxide film and by acting synergistically with lead, and then drove rapid crack propagation by subsequently promoting the micro-fracture of the brittle dealloying zone. This study revealed the critical role of stress in the PbSCC process and provided an important theoretical foundation for assessing the long-term service safety of Alloy 690TT under complex stress conditions.
Source: openalex_inverted_index · Quality: baseline

Research context

OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Nuclear Materials and Properties · High Temperature Alloys and Creep

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

References (37)

Show source-provided references
1. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
2. Comprehensive analysis of alloy 800 corrosion using thermo-kinetic diagrams
3. Study on the SCC behavior induced by creep cavities on scratched surface of alloy 690TT in high temperature water10.1016/j.corsci.2021.110017 ↗
4. On the role of intergranular nanocavities in long-term stress corrosion cracking of alloy 69010.1016/j.actamat.2021.117453 ↗
5. Insights into the SCC crack tip of alloy 690TT in caustic solution at high temperature10.1016/j.jnucmat.2021.153034 ↗
6. Unveiling the role of irradiation in stress corrosion cracking of alloy 69010.1016/j.corsci.2025.113303 ↗
7. High cycle fatigue behavior and numerical evaluation of Alloy 690TT steam generator tube10.1016/j.ijfatigue.2020.105662 ↗
8. The role of hydrogen on lead-induced localized corrosion of Alloy 690TT10.1016/j.corsci.2024.112469 ↗
9. Effect of the triangular prism dent on stress corrosion cracking behavior of alloy 690TT heat transfer tube in a lead-containing alkaline solution10.1016/j.jnucmat.2024.155043 ↗
10. Size effect of scratches on the degradation behavior of alloy 690TT in high temperature caustic solution10.1016/j.corsci.2021.109314 ↗
11. Electrochemical noise analysis of PbSCC of Alloy 600 SG tube in caustic environments at high temperature10.1016/j.corsci.2008.10.014 ↗
12. Strain rate dependence of the effect of intergranular carbides on the resistance to stress corrosion cracking initiation of alloy 690 in simulated PWR primary water10.1016/j.corsci.2022.110502 ↗
13. Effect of temperature on corrosion fatigue behavior of Inconel Alloy 690TT steam generator tube10.1016/j.corsci.2023.111741 ↗
14. Effects of dissolved hydrogen on general corrosion behavior and oxide films of alloy 690TT in PWR primary water10.1016/j.jnucmat.2016.12.020 ↗
15. Modeling of stress corrosion cracking growth rates for key structural materials of nuclear power plant10.1007/s10853-019-03968-w ↗
16. A mechanistic study on thiosulfate-enhanced passivity degradation of Alloy 800 in chloride solutions, Electroc
17. Semiconductivity conversion of Alloy 800 in sulphate, thiosulphate, and chloride solutions10.1016/j.corsci.2014.06.036 ↗
18. 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 ↗
19. Stress corrosion cracking susceptibility of steam generator tube materials in AVT (all volatile treatment) chemistry contaminated with lead10.1016/0029-5493(96)01195-8 ↗
20. Oxide properties and stress corrosion cracking behaviour for Alloy 600 in leaded caustic solutions at high temperature10.1016/j.corsci.2010.12.016 ↗
21. Effects of pH on lead-induced passivity degradation of nuclear steam generator tubing alloy in high temperature crevice chemistries10.1016/j.electacta.2012.10.006 ↗
22. Passivity degradation of nuclear steam generator tubing alloy induced by Pb contamination at high temperature10.1016/j.jnucmat.2012.06.021 ↗
23. The mechanism of stress corrosion cracking of Alloy 690TT in a caustic solution containing lead10.1016/j.corsci.2017.09.015 ↗
24. Effects of lead on oxidation behavior of Alloy 690TT within a high temperature aqueous environment10.1016/j.apsusc.2017.07.201 ↗
25. Lead-induced stress corrosion cracking (PbSCC) initiation in alloy 690TT in caustic environment10.1016/j.corsci.2022.110475 ↗
26. Advanced microstructural characterization of transgranular Pb-caustic SCC in Alloy 690TT10.1016/j.corsci.2022.110461 ↗
27. Effect of stress and surface finish on Pb-caustic SCC of alloy 690TT10.1016/j.corsci.2021.109462 ↗
28. Effects of foreign object damage on high-cycle fatigue behavior of Inconel Alloy 690TT steam generator tubes10.1016/j.engfracmech.2023.109660 ↗
29. Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect10.1016/j.jnucmat.2022.153629 ↗
30. Effects of PbO on the repassivation kinetics of alloy 69010.1016/j.corsci.2005.05.005 ↗
31. High resolution characterization of Pb-SCC in Alloy 800 exposed to 330°C mildly caustic environments10.1016/j.corsci.2018.05.031 ↗
32. Stress corrosion cracking behavior and mechanism of scratched Alloy 690TT in lead-containing caustic solution10.1016/j.corsci.2025.112702 ↗
33. Synergistic effect of mechanical and environmental damages of 316LN stainless steel under different fatigue strain amplitudes in high-temperature pressurized water10.1016/j.msea.2018.11.081 ↗
34. Corrosion fatigue damage mechanism and life evaluation of Inconel Alloy 690TT steam generator tube in high temperature pressurized water10.1016/j.corsci.2022.110953 ↗
35. Mobility of dislocations in aluminum: the role of Non-Schmid stress state10.1016/j.actamat.2019.12.021 ↗
36. Influence of local stresses on motion of edge dislocation in aluminum10.1016/j.ijplas.2017.11.002 ↗
37. Stress dependence of the dislocation core structure and loop nucleation for face-centered-cubic metals10.1016/j.actamat.2017.04.019 ↗