Irradiation-induced corrosion tendencies evolution at the phase boundaries containing carbides in duplex stainless steel
Source abstract
Abstract
Irradiation-assisted stress corrosion cracking normally initiates and propagates along grain/phase boundaries. Here, by using scanning Kelvin probe force microscopy, we characterized the Volta potential difference (VPD) changes prior and after proton irradiation at austenite/carbide (γ/C), ferrite/carbide (δ/C) and austenite/ferrite (γ/δ) interfaces in a 308 L stainless steel. It was found that, prior to irradiation, γ/C boundary had the lowest VPD, followed by δ/C and γ/δ. VPDs of all three types of phase boundaries slightly decreased after proton irradiation, wherein the γ/C boundary showed the largest VPD drop, followed by δ/C and γ/δ. The γ/C interface demonstrates the highest tendency of corrosion.
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Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Fusion materials and technologies · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (74)
Show source-provided references
1. Crack initiation of neutron-irradiated 304 L stainless steel in PWR primary water10.1016/j.corsci.2021.109902 ↗
2. An insight into PWR primary water SCC mechanisms by comparing surface and crack oxidation10.1016/j.corsci.2018.12.020 ↗
3. Materials for future nuclear energy systems10.1016/j.jnucmat.2019.151837 ↗
4. The effect of potassium hydroxide primary water chemistry on the IASCC behavior of 304 stainless steel10.1016/j.jnucmat.2021.153323 ↗
5. Microstructure, mechanical properties and IASCC susceptibility of stainless steel baffle bolts after 30 years of operation in a PWR10.1016/j.jnucmat.2020.152615 ↗
6. A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels10.1016/j.jnucmat.2010.12.001 ↗
7. Irradiation assisted stress corrosion cracking of commercial and advanced alloys for light water reactor core internals10.1016/j.jnucmat.2018.12.015 ↗
8. A micromechanical analysis of intergranular stress corrosion cracking of an irradiated austenitic stainless steel10.1016/j.actamat.2020.116482 ↗
9. Finite element analyses of the effect of weld overlay sizing on residual stresses of the dissimilar metal weld in PWRs10.1016/j.nucengdes.2020.110959 ↗
10. Limit loads of dissimilar metal welded joints for joining safe end to pipe-nozzle of nuclear pressure vessel10.1016/j.ijpvp.2021.104554 ↗
11. Development and evaluation of welding repair for threaded hole of Reactor Pressure Vessel flange10.1016/j.ijpvp.2021.104341 ↗
12. Stress corrosion cracking failure of friction stir welded nuclear grade austenitic stainless steel10.1016/j.engfailanal.2020.105012 ↗
13. Characterization of microstructure of A508III/309L/308L weld and oxide films formed in deaerated high-temperature water10.1016/j.jnucmat.2017.10.030 ↗
14. Effect of thermal ageing and dissolved gas on corrosion of 308L stainless steel weld metal in simulated PWR primary water10.1016/j.jmst.2021.05.026 ↗
15. Environment assisted cracking of 308L weld metal in high temperature water10.1016/j.jnucmat.2021.153275 ↗
16. Investigation of the oxide film on 308L weld surface produced during welding process10.1016/j.matchar.2018.09.011 ↗
17. Microstructural characterization of low alloy steel A508 – 309/308L stainless steel dissimilar weld metals10.1016/j.ijpvp.2020.104297 ↗
18. Microstructure evolution and mechanical properties of 308L stainless steel coatings fabricated by laser hot wire cladding10.1016/j.msea.2021.141825 ↗
19. Modified microstructures in proton irradiated dual phase 308L weldment filler material10.1016/j.jnucmat.2021.152825 ↗
20. Irradiation-assisted stress corrosion cracking of Type 347 and Type 316 steels irradiated in commercial pressurized water reactors10.1016/j.jnucmat.2020.152182 ↗
21. Effect of Cr/Mo carbides on corrosion behaviour of Fe_Mn_C twinning induced plasticity steel10.1016/j.corsci.2020.108518 ↗
22. Assessment of the correlation between M23C6 precipitates and pitting corrosion resistance of 0Cr13 martensitic stainless steel10.1016/j.corsci.2021.109580 ↗
23. The effect of M23C6 carbides on the formation of grain boundary serrations in a wrought Ni-based superalloy10.1016/j.msea.2011.11.060 ↗
24. Microscale investigation of the correlation between microstructure and galvanic corrosion of low alloy steel A508 and its welded 309/308L stainless steel overlayer10.1016/j.corsci.2019.03.027 ↗
25. 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 ↗
26. Corrosion of phase and phase boundary in proton-irradiated 308L stainless steel weld metal in simulated PWR primary water10.1016/j.corsci.2019.108401 ↗
27. Deformation and cracking behaviors of proton-irradiated 308L stainless steel weld metal strained in simulated PWR primary water10.1016/j.jmst.2021.11.056 ↗
28. Understanding crystallographic orientation dependent dissolution rates of 90Cu-10Ni alloy: New insights based on AFM/SKPFM measurements and coordination number/electronic structure calculations10.1016/j.corsci.2019.108320 ↗
29. Correlation of surface Volta potential with galvanic corrosion initiation sites in solid-state welded Ti-Cu bimetal using AFM-SKPFM10.1016/j.corsci.2018.06.026 ↗
30. SKPFM measured Volta potential correlated with strain localisation in microstructure to understand corrosion susceptibility of cold-rolled grade 2205 duplex stainless steel10.1016/j.corsci.2015.06.035 ↗
31. Irradiation-induced segregation at phase boundaries in austenitic stainless steel weld metal10.1016/j.scriptamat.2018.01.033 ↗
32. Effect of post-irradiation annealing on microstructure and corrosion of proton-irradiated 308L stainless steel weld metal10.1016/j.corsci.2020.108887 ↗
33. Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water10.1016/j.jmst.2020.04.068 ↗
34. Proton irradiation effects on the electron work function, corrosion and hardness of austenitic stainless steel phases10.1016/j.corsci.2019.06.011 ↗
35. Effect of thermal aging and irradiation on the electrochemical and passivation behavior of 308L stainless steel in simulated pressurized water reactor environment10.1016/j.matlet.2020.129157 ↗
36. Combined effects of irradiation and hydrogen ions on surface oxidation of 308 L austenite stainless steel10.1016/j.corsci.2021.109734 ↗
37. Characterization of the passive layer on ferrite and austenite phases of super duplex stainless steel10.1016/j.apsusc.2019.143634 ↗
38. Unusual Correlation between SKPFM and Corrosion of Nickel Aluminum Bronzes10.1149/2.0391709jes ↗
39. The corrosion and erosion resistance of chromium carbide alloys in multicomponent corrosive environments10.1007/BF01194589 ↗
40. Galvanic effects on the active dissolution of duplex stainless steels10.5006/1.3585062 ↗
41. Real-time evolution and characterization of passive films on individual ferrite and austenite phases of duplex stainless steel10.1016/j.elecom.2022.107265 ↗
42. Effect of annealing temperature on the corrosion behavior of duplex stainless steel studied by in situ techniques10.1016/j.corsci.2011.07.019 ↗
43. Quantitative calibration of the relationship between Volta potential measured by scanning Kelvin probe force microscope (SKPFM) and hydrogen concentration10.1016/j.electacta.2020.137422 ↗
44. The effect of grain boundary misorientation on the intergranular M23C6 carbide precipitation in thermally treated Alloy 69010.1016/j.jnucmat.2004.07.038 ↗
45. Study on the nucleation and growth of M23C6 carbides in a 10% Cr martensite ferritic steel after long-term aging10.1016/j.matchar.2015.11.023 ↗
46. Correlation between microstructure and intergranular corrosion behavior of low delta-ferrite content AISI 316L aged in the range 550–700 °C10.1016/j.jallcom.2017.02.273 ↗
47. Suppressing irradiation induced grain growth and defect accumulation in nanocrystalline tungsten through grain boundary doping10.1016/j.actamat.2021.116629 ↗
48. Quantitative investigation on sink strength of nano-grain boundary for irradiation resistance10.1016/j.jnucmat.2019.151741 ↗
49. Helium effect on the sink strength of grain boundaries in F82H
50. Roles of vacancy/interstitial diffusion and segregation in the microchemistry at grain boundaries of irradiated Fe–Cr–Ni alloys10.1016/j.jnucmat.2016.02.007 ↗
51. Significant differences in defect accumulation behaviour between fcc and bcc crystals under cascade damage conditions10.1016/0022-3115(95)00121-2 ↗
52. Comparison between radiation effects in some fcc and bcc metals irradiated with energetic heavy ions – a review10.1016/S0022-3115(99)00177-4 ↗
53. Non-uniform phase separation in ferrite of a duplex stainless steel10.1016/j.actamat.2017.08.044 ↗
54. Low temperature aging behavior of type 308 stainless steel weld metal10.1016/0956-7151(91)90118-K ↗
55. Mechanical property degradation and microstructural evolution of cast austenitic stainless steels under short-term thermal aging10.1016/j.jnucmat.2017.07.059 ↗
56. First-principles study on the dissolution and diffusion behavior of hydrogen in carbide precipitates10.1016/j.ijhydene.2021.04.056 ↗
57. Atom probe tomographic observation of hydrogen trapping at carbides/ferrite interface s for a high strength steel10.1016/j.jmst.2017.11.008 ↗
58. Pre-straining alters hydrogen-assisted cracking site and local hydrogen diffusivity in a nitrogen-doped duplex steel10.1016/j.scriptamat.2021.114272 ↗
59. An abnormal correlation between electron work function and corrosion resistance in Ti-Zr-Be-(Ni/Fe) metallic glasses10.1016/j.corsci.2019.108392 ↗
60. Wettability, electron work function and corrosion behavior of CoCrFeMnNi high entropy alloy films
61. Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy10.1016/j.jnucmat.2016.10.050 ↗
62. Strain localization at dislocation channel–grain boundary intersections in irradiated stainless steel10.1016/j.ijplas.2014.01.001 ↗
63. Quantitative linkage between the stress at dislocation channel – Grain boundary interaction sites and irradiation assisted stress corrosion crack initiation10.1016/j.actamat.2019.02.032 ↗
64. Tribological properties of AZ31 alloy pre-deformed at low and high strain rates via the work function10.1016/j.wear.2018.08.008 ↗
65. Effect of heavy ion irradiation on microstructural evolution in CF8 cast austenitic stainless steel10.1016/j.jnucmat.2015.08.032 ↗
66. In situ TEM study of G-phase precipitates under heavy ion irradiation in CF8 cast austenitic stainless steel10.1016/j.jnucmat.2015.04.042 ↗
67. Influences of tensile strain and strain rate on the electron work function of metals and alloys10.1016/j.scriptamat.2005.10.064 ↗
68. Surface roughness characteristics of corroded steel pipe piles exposed to marine environment10.1016/j.conbuildmat.2019.01.092 ↗
69. Electrochemical, TOF-SIMS and XPS studies on the corrosion behavior of Q-phase in NaCl solutions as a function of pH10.1016/j.apsusc.2019.06.089 ↗
70. Investigation of the effects of temperature and exposure time on the corrosion behavior of a ferritic steel in CO2 environment using the optimized linear polarization resistance method
71. The manufacture and study of the microstructure, mechanical properties, and corrosion behavior of Fe31Cr15Mo14C10B10Si5Ti15 metallic glass thin film, prepared by the magnetic sputtering method10.1016/j.jnoncrysol.2022.121805 ↗
72. Corrosion characterization of Ti-6Al-4V coating layer by the alternating current assisted GTAW method10.1016/j.corsci.2021.110066 ↗
73. The mechanism of hydrogen-induced pitting corrosion in duplex stainless steel studied by SKPFM10.1016/j.corsci.2012.04.010 ↗
74. The contribution of Cr and Mo to the passivation of Ni22Cr and Ni22Cr10Mo alloys in sulfuric acid10.1016/j.corsci.2020.109015 ↗