journal article·2024-09

On the stress corrosion crack initiation behaviour of Alloy 800 in high-temperature hydrogenated water

Shihao Zhang, Xiaoqiang Liu, Wei Wang, En-Hou Han, Wenjun Kuang

Corrosion Science· Volume 238
Publisher page

Abstract

The stress corrosion cracking (SCC) initiation behaviour of annealed Alloy 800 was studied in high-temperature hydrogenated water through slow strain rate tensile (SSRT) test. The results indicate that Alloy 800 exhibits higher SCC initiation resistance than 304 stainless steel (SS), with a comparable length percentage of grain boundary surface cracking but much shallower crack depth. The higher SCC resistance of Alloy 800 is primarily attributed to its higher Cr content, which enhances the alloy’s resistance to intergranular oxidation. However, Alloy 800 is still susceptible to SCC initiation, as most high-angle grain boundaries are prone to penetrative oxidation.
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 (40)

Show source-provided references
1. General corrosion and stress corrosion cracking of alloy 600 in light water reactor primary coolants10.1016/j.jnucmat.2019.04.023 ↗
2. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
3. The estimation of lifetime distribution of alloy 800 steam generator tubing10.1016/j.nucengdes.2009.05.027 ↗
4. Stress corrosion cracking growth of alloy 800NG in pressurized water reactor primary water10.5006/2572 ↗
5. Coriou · 1960 · 161
6. 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 ↗
7. , How irradiation promotes intergranular stress corrosion crack initiation10.1016/j.pmatsci.2024.101255 ↗
8. Effect of Cr and Ni on stress corrosion cracking susceptibility in Ni-Cr-Fe alloys under simulated pressurized water reactor primary conditions10.5006/1696 ↗
9. A high-resolution characterization of irradiation-assisted stress corrosion cracking of proton-irradiated 316L stainless steel in simulated pressurized water reactor primary water10.1016/j.corsci.2022.110187 ↗
10. Clarifying the mitigation effect of proton irradiation on the intergranular oxidation of 316L stainless steel in high temperature water10.1016/j.actamat.2022.118408 ↗
11. Insights into the stress corrosion cracking resistance of a selective laser melted 304L stainless steel in high-temperature hydrogenated water10.1016/j.actamat.2022.118561 ↗
12. Nanoscale characterisation of grain boundary oxidation in cold-worked stainless steels10.1016/j.corsci.2012.06.030 ↗
13. The intergranular oxidation behavior of low-angle grain boundary of alloy 600 in simulated pressurized water reactor primary water10.1016/j.actamat.2021.117533 ↗
14. Intergranular oxidation of 316L stainless steel in the PWR primary water environment10.1016/j.corsci.2017.06.023 ↗
15. Adaptation of the point defect model to simulate oxidation kinetics of 316L stainless steel in the pressurised water reactor environment10.1016/j.corsci.2021.109454 ↗
16. How oxidized grain boundaries fail10.1016/j.actamat.2013.05.012 ↗
17. 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 ↗
18. Degradation of grain boundary strength by oxidation in Alloy 600
19. The effects of grain boundary carbide density and strain rate on the stress corrosion cracking behavior of cold rolled Alloy 69010.1016/j.corsci.2015.04.020 ↗
20. Stress corrosion crack initiation in alloy 690 in high temperature water10.1016/j.cossms.2018.02.001 ↗
21. The structure dependence of grain boundary passivation of Alloy 690 in high temperature water10.1016/j.actamat.2023.119368 ↗
22. 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 ↗
23. Intergranular stress corrosion cracking growth behavior of Ni-Cr-Fe alloys in pressurized water reactor primary water10.5006/1205 ↗
24. P.L. Andresen, SCC of Alloy 825, High Cr Alloy 800 and other interesting Alloys in high temperature water, Corrosion 2013, 2013, pp. NACE-2013-2412.
25. Dynamic strain aging of nickel-base alloys 800H and 69010.1007/s11661-012-1335-x ↗
26. The effects of strain rate and carbon concentration on the dynamic strain aging of cold rolled Ni-based alloy in high temperature water10.1016/j.scriptamat.2015.05.033 ↗
27. Activation energy calculation and dynamic strain aging in austenitic stainless steel10.1016/0956-716X(94)90134-1 ↗
28. The beneficial effect of surface carbon coating on stress corrosion cracking of Type 304 austenitic stainless steels in high temperature water10.1016/j.scriptamat.2018.08.033 ↗
29. Understanding the effect of surface finish on stress corrosion crack initiation in warm-forged stainless steel 304L in high-temperature water10.1016/j.scriptamat.2019.01.032 ↗
30. Role of δ-ferrite in stress corrosion cracking retardation near fusion boundary of 316NG welds10.1016/j.jnucmat.2012.02.006 ↗
31. Effects of dissolved hydrogen on corrosion fatigue crack growth behavior of 316LN stainless steel in high temperature pressurized water environment
32. A study on the diffusion-induced grain boundary migration ahead of stress corrosion cracking crack tips through advanced characterization10.1016/j.corsci.2021.109328 ↗
33. Effects of precipitation on the stress corrosion crack initiation of alloy 718 in simulated pressurized water reactor primary environment10.1016/j.actamat.2024.120127 ↗
34. 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 ↗
35. The time dependence of proton irradiation effect on the intergranular oxidation of 316 L stainless steel in high-temperature hydrogenated water10.1016/j.actamat.2023.119340 ↗
36. 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 ↗
37. Grain boundary self-diffusion of 51Cr and 59Fe in austenitic Ni-Fe-Cr alloys10.1016/0921-5093(91)90830-G ↗
38. The structure dependence of oxidation behavior of high-angle grain boundaries of alloy 600 in simulated pressurized water reactor primary water10.1016/j.corsci.2023.111162 ↗
39. A mechanistic study of SCC in Alloy 600 through high-resolution characterization10.1016/j.corsci.2018.01.004 ↗
40. 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 ↗