journal article·2026-04

Stress corrosion behavior of 316 stainless steel tube under dual-loop high-temperature waters

Tingguang Liu, Yongming Han, Zhenhua Li, Yonghao Lu, Tetsuo Shoji

Corrosion Science· Volume 262
Publisher page

Abstract

No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.

Source: Not provided · Quality: missing

Research context

OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Nuclear Engineering Thermal-Hydraulics · Erosion and Abrasive Machining

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

References (33)

Show source-provided references
1. Overview of steam generator tube degradation and integrity issues10.1016/S0029-5493(99)00167-3 ↗
2. 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 ↗
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. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
5. Quantitatively evaluating the contribution of intergranular carbides, Cr-depleted zone, and grain boundary to intergranular stress corrosion cracking of Alloy 600 in a simulated boiling water reactors environment with high oxygen concentrations10.1016/j.actamat.2024.119794 ↗
6. Prediction of stress corrosion crack growth rate of cold worked stainless steels in BWR conditions by the slip oxidation model10.1016/j.nucengdes.2024.113060 ↗
7. Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints10.1016/j.jnucmat.2024.155560 ↗
8. Iterative thermomechanical processing of alloy 600 for improved resistance to corrosion and stress corrosion cracking10.1016/j.actamat.2016.05.009 ↗
9. Stress corrosion cracking growth of alloy 800NG in pressurized water reactor primary water10.5006/2572 ↗
10. 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 ↗
11. The effect of dissolved oxygen on fatigue behavior of Alloy 690 steam generator tubes in borated and lithiated high temperature water10.1016/j.corsci.2015.10.032 ↗
12. The response of alloy 690 tubing in a pressurized water reactor environment10.1016/j.matdes.2005.10.001 ↗
13. Insights into the stress corrosion cracking propagation behavior of Alloy 690 and 316 L stainless steel in KOH versus LiOH oxygenated water10.1016/j.corsci.2023.111556 ↗
14. Three-dimensional study of grain boundary engineering effects on intergranular stress corrosion cracking of 316 stainless steel in high temperature water10.1016/j.jnucmat.2017.10.004 ↗
15. Accelerated test for evaluation of intergranular stress corrosion cracking initiation characteristics of non-sensitized 316 austenitic stainless steel in simulated pressure water reactor environment10.1016/j.corsci.2016.11.019 ↗
16. Effects of dissolved hydrogen and surface condition on the intergranular stress corrosion cracking initiation and short crack growth behavior of non-sensitized 316 stainless steel in simulated PWR primary water10.1016/j.corsci.2017.02.003 ↗
17. Acoustic emission monitoring of slow strain rate tensile tests of 304L stainless steel in supercritical water environment10.1016/j.corsci.2010.09.006 ↗
18. Digital twin model generation for crack propagation in steam generator tubes: methods and implementation10.1016/j.anucene.2025.111697 ↗
19. The structure of high-angle grain boundaries10.1016/0001-6160(66)90168-4 ↗
20. A micromechanical analysis of intergranular stress corrosion cracking of an irradiated austenitic stainless steel10.1016/j.actamat.2020.116482 ↗
21. An insight into PWR primary water SCC mechanisms by comparing surface and crack oxidation10.1016/j.corsci.2018.12.020 ↗
22. Synergistic effects of permeated hydrogen, grain boundary type, and carbide on the intergranular oxidation of alloy 600TT in high temperature water10.1016/j.jmst.2025.09.055 ↗
23. Anomalous oxidation behavior and enhanced corrosion resistance of a lean-Cr FeCrAl alloy in the oxygenated PWR primary water10.1016/j.corsci.2025.113452 ↗
24. Effects of surface finishes, heat treatments and printing orientations on stress corrosion cracking behavior of laser powder bed fusion 316L stainless steel in high-temperature water10.1016/j.corsci.2024.112118 ↗
25. TEM investigations of the oxide layers formed on a 316L alloy in simulated PWR environment10.1007/s10853-012-6975-0 ↗
26. Characterization of interfacial reactions and oxide films on 316L stainless steel in various simulated PWR primary water environments10.1016/j.jnucmat.2017.03.029 ↗
27. Atom probe tomography of stress corrosion crack tips in SUS316 stainless steels10.1016/j.corsci.2015.06.008 ↗
28. Effects of temperature on crack-growth rate in sensitized type-304 stainless-steel and alloy-60010.5006/1.3316104 ↗
29. SCC growth behaviors of austenitic stainless steels in simulated PWR primary water10.1016/j.jnucmat.2012.03.013 ↗
30. SCC crack growth rate of cold worked 316L stainless steel in PWR environment10.1016/j.jnucmat.2014.09.054 ↗
31. Quantitative prediction of environmentally assisted cracking10.5006/1.3292125 ↗
32. Stress corrosion crack initiation of alloy 600 in PWR primary water10.1016/j.corsci.2017.04.013 ↗
33. Improving the intergranular corrosion resistance of 304 stainless steel by grain boundary network control10.1016/j.corsci.2011.02.005 ↗