journal article·2025-09

Effects of grain boundary structure on the irradiation-affected intergranular oxidation of 316L stainless steel in high-temperature hydrogenated water

Shengkai Wang, Miao Song, En-Hou Han, Wenjun Kuang

Acta Materialia· Volume 297
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: Fusion materials and technologies · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals

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

References (54)

Show source-provided references
1. Slow strain rate tensile tests of irradiated austenitic stainless steels in simulated PWR environment
2. 3-Mechanisms behind irradiation-assisted stress corrosion cracking
3. 5.08 - Irradiation Assisted Stress Corrosion Cracking
4. Current understanding of radiation-induced degradation in light water reactor structural materials10.1080/00223131.2013.772448 ↗
5. Irradiation-assisted stress corrosion cracking10.1515/corrrev.2011.020 ↗
6. Stainless-Steel-Clad Fuel Rod Failures
7. How irradiation promotes intergranular stress corrosion crack initiation10.1016/j.pmatsci.2024.101255 ↗
8. Clarifying the irradiation effect on the general oxidation of 316L stainless steel in high temperature hydrogenated water after 1000h immersion10.1016/j.actamat.2023.119100 ↗
9. Degradation of grain boundary strength by oxidation in alloy 600[C]
10. How oxidized grain boundaries fail10.1016/j.actamat.2013.05.012 ↗
11. Micro-mechanical measurement of fracture behavior of individual grain boundaries in Ni alloy 600 exposed to a pressurized water reactor environment10.1016/j.corsci.2015.10.019 ↗
12. 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 ↗
13. Crack initiation of neutron-irradiated 304L stainless steel in PWR primary water10.1016/j.corsci.2021.109902 ↗
14. An ATEM study of oxidation behavior of SCC crack tips in 304L stainless steel in high temperature oxygenated water10.1016/j.jnucmat.2005.07.006 ↗
15. Multi-scale characterization of stress corrosion cracking of cold-worked stainless steels and the influence of Cr content10.1016/j.actamat.2009.07.040 ↗
16. 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 ↗
17. On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys10.1016/S0022-3115(98)00010-5 ↗
18. Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels10.1016/j.actamat.2010.10.055 ↗
19. Effects of grain boundary misorientation on solute segregation in thermally sensitized and proton-irradiated 304 stainless steel10.1016/S0022-3115(00)00255-5 ↗
20. Sink effect of grain boundary on radiation-induced segregation in austenitic stainless steel10.1016/S0022-3115(00)00204-X ↗
21. Anisotropic radiation-induced segregation in 316L austenitic stainless steel with grain boundary character10.1016/j.actamat.2013.11.060 ↗
22. Radiation-induced segregation and corrosion behavior on Σ3 coincidence site lattice and random grain boundaries in proton-irradiated type-316L austenitic stainless steel10.1016/j.jnucmat.2012.11.036 ↗
23. Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment10.1016/j.corsci.2016.02.040 ↗
24. 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 ↗
25. The intergranular oxidation behavior of low angle grain boundary of alloy 600 in simulated pressurized water reactor primary water10.1016/j.actamat.2021.117533 ↗
26. IGSCC of grain boundary engineered 316L and 690 in supercritical water10.1016/j.jnucmat.2009.03.008 ↗
27. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
28. 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 ↗
29. Clarifying the mitigation effect of proton irradiation on the intergranular oxidation of 316L stainless steel in high temperature water10.1016/j.actamat.2022.118408 ↗
30. A novel approach to index site-specific grain boundary plane10.1016/j.matchar.2021.110999 ↗
31. The time dependence of proton irradiation effect on the intergranular oxidation of 316L stainless steel in high-temperature hydrogenated water10.1016/j.actamat.2023.119340 ↗
32. Understanding the role of diffusion induced grain boundary migration on the preferential intergranular oxidation behaviour of alloy 600 via advanced microstructural characterization10.1016/j.actamat.2019.06.021 ↗
33. Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water10.1016/j.corsci.2017.08.010 ↗
34. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
35. Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments10.1016/j.actamat.2015.01.064 ↗
36. Dependence on grain boundary structure of radiation induced segregation in a 9 wt.% Cr model ferritic/martensitic steel10.1016/j.jnucmat.2012.12.026 ↗
37. The influence of Σ3 twin boundaries on the formation of radiation-induced defect clusters in nanotwinned Cu10.1557/jmr.2011.56 ↗
38. Effect of grain boundary character on sink efficiency10.1016/j.actamat.2012.08.009 ↗
39. Limited effect of twin boundaries on radiation damage10.1007/s40195-015-0363-0 ↗
40. The effect of migrating Σ3 {112} incoherent twin boundary on radiation tolerance of nanotwinned copper10.1016/j.actamat.2024.119668 ↗
41. Probing grain boundary sink strength at the nanoscale: energetics and length scales of vacancy and interstitial absorption by grain boundaries in α-Fe10.1103/PhysRevB.85.064108 ↗
42. Grain boundary character dependence of radiation-induced segregation in a model Ni–Cr alloy10.1557/jmr.2015.34 ↗
43. Point defect annihilation at grain boundaries in gold10.1016/0036-9748(85)90118-8 ↗
44. Effect of grain boundary stresses on sink strength10.1080/21663831.2013.871588 ↗
45. Superior irradiation resistance via nanocrystalline grains of 316L austenitic stainless steel10.1016/j.actamat.2025.121228 ↗
46. The mechanism of radiation-induced segregation in ferritic–martensitic alloys
47. 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 ↗
48. The effects of grain boundary structure and bulk Cr content on grain boundary degradation behavior of Ni-Cr binary alloys in high temperature CO210.1016/j.actamat.2023.119496 ↗
49. Grain boundary oxidation behavior of Ni15Cr alloy in high temperature carbon dioxide10.1016/j.scriptamat.2022.114935 ↗
50. Grain boundary oxidation and embrittlement prior to crack initiation in Alloy 600 in PWR primary water
51. The influence of Σ3 twin boundaries on the formation of radiation-induced defect clusters in nanotwinned Cu10.1557/jmr.2011.56 ↗
52. Corrosion behavior in lead-bismuth eutectic of 316 L stainless steels fabricated by laser-based powder bed fusion and powder metallurgy-hot isostatic pressing10.1016/j.corsci.2025.112911 ↗
53. Influence of silicon additions on the oxidation resistance of a stainless steel10.1007/BF00656225 ↗
54. Thermal oxidation kinetics and oxide scale adhesion of Fe–15Cr alloys as a function of their silicon content10.1016/j.actamat.2006.04.023 ↗