Dislocation channel broadening–A new mechanism to improve irradiation-assisted stress corrosion cracking resistance of additively manufactured 316 L stainless steel
Source abstract
Abstract
Additively manufactured (AM) 316 L stainless steel (SS) after hot isostatic pressing (HIP) was found to exhibit superior resistance to irradiation-assisted stress corrosion cracking (IASCC) in high-temperature water, as compared to wrought 316 L SS. The well-accepted IASCC factors of radiation-induced segregation (RIS) and radiation hardening are not accurate descriptions of IASCC susceptibility in this case. A decreased strain localization along grain boundaries, caused by dislocation channel broadening, was confirmed to suppress crack initiation. A unique distribution of irradiation-induced defects in HIP AM 316 L SS eased dislocation cross-slip compared to those in the wrought counterpart, thus increasing the channel width near the grain boundaries. For the first time, this study highlights the importance of dislocation channel broadening as a potential mechanism to further improve the IASCC resistance of 316 L SS and provides direct experimental evidence based on commercial-grade materials.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Additive Manufacturing Materials and Processes · Nuclear Materials and Properties · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (84)
Show source-provided references
1. Thermal stability and microstructural evolution of additively manufactured 316 L stainless steel by laser powder bed fusion at 500-800 °C
2. On the thermal coarsening and transformation of nanoscale oxide inclusions in 316 L stainless steel manufactured by laser powder bed fusion and its influence on impact toughness10.1016/j.msea.2022.142690 ↗
3. Oxide inclusions in laser additive manufactured stainless steel and their effects on impact toughness and stress corrosion cracking behavior10.1016/j.jnucmat.2017.11.036 ↗
4. On the origin of the high tensile strength and ductility of additively manufactured 316 L stainless steel: multiscale investigation10.1016/j.jmst.2019.09.017 ↗
5. Microstructure and high temperature tensile properties of 316 L fabricated by laser powder-bed fusion
6. Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization10.1016/j.jnucmat.2018.08.035 ↗
7. Void swelling in additively manufactured 316 L stainless steel with Hafnium composition gradients under self-ion irradiation10.1016/j.jnucmat.2023.154351 ↗
8. Sensitization, desensitization, and carbide evolution of Alloy 800H made by laser powder bed fusion
9. Effects of heat treatment on corrosion fatigue and stress corrosion crack growth of additive-manufactured Alloy 800H in high-temperature water10.1016/j.corsci.2021.109739 ↗
10. On the stress corrosion crack growth behaviour in high temperature water of 316 L stainless steel made by laser powder bed fusion additive manufacturing10.1016/j.corsci.2017.09.017 ↗
11. Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316 L stainless steels10.1016/j.jnucmat.2018.10.044 ↗
12. Intragranular irradiation-assisted stress corrosion cracking (IASCC) of 316 L stainless steel made by laser direct energy deposition additive manufacturing : delta ferrite-dislocation channel interaction10.1016/j.jnucmat.2023.154305 ↗
13. Investigation of the irradiation effects in additively manufactured 316 L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility10.1016/j.jnucmat.2020.152739 ↗
14. Regulatory research perspective on additive manufacturing for nuclear component applications10.1016/j.jnucmat.2020.152726 ↗
15. Deformation behavior and irradiation tolerance of 316 L stainless steel fabricated by direct energy deposition10.1016/j.matdes.2021.109644 ↗
16. Microstructural and microchemical mechanisms controlling intergranular stress corrosion cracking in light-water-reactor systems10.1016/0022-3115(94)90020-5 ↗
17. Radiation hardening and radiation-induced chromium depletion effects on intergranular stress corrosion cracking in austenitic stainless steels10.5006/1.3293485 ↗
18. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals10.1016/S0022-3115(99)00075-6 ↗
19. Role of irradiated microstructure and microchemistry in irradiation-assisted stress corrosion cracking10.1080/02678370412331320224 ↗
20. Strain localization at dislocation channel–grain boundary intersections in irradiated stainless steel10.1016/j.ijplas.2014.01.001 ↗
21. Relationship between localized strain and irradiation assisted stress corrosion cracking in an austenitic alloy10.1016/j.msea.2011.01.073 ↗
22. Impact of localized deformation on IASCC in austenitic stainless steels10.1016/j.jnucmat.2010.10.087 ↗
23. Compositionally graded specimen made by laser additive manufacturing as a high-throughput method to study radiation damages and irradiation-assisted stress corrosion cracking
24. Localized deformation induced IGSCC and IASCC of austenitic alloys in high temperature water10.4028/www.scientific.net/KEM.261-263.885 ↗
25. Mechanisms of stacking fault tetrahedra destruction by gliding dislocations in quenched gold10.1080/14786430801898644 ↗
26. A review on neutron-irradiation-induced hardening of metallic components10.1016/j.engfailanal.2011.06.008 ↗
27. Strain localization in irradiated materials
28. Deformation microstructure of proton-irradiated stainless steels10.1016/j.jnucmat.2006.12.012 ↗
29. Strain-induced precipitate dissolution in an irradiated austenitic alloy10.1016/j.scriptamat.2011.04.003 ↗
30. The role of irradiated microstructure in the localized deformation of austenitic stainless steels10.1016/j.jnucmat.2010.07.006 ↗
31. Influence of irradiation damage on slip transfer across grain boundaries10.1016/j.actamat.2013.11.033 ↗
32. Mechanism of dislocation channel-induced irradiation assisted stress corrosion crack initiation in austenitic stainless steel10.1016/j.cossms.2015.04.001 ↗
33. Modeling of dislocation channel width evolution in irradiated metals10.1016/j.jnucmat.2017.10.063 ↗
34. Characteristics of microscopic strain localization in irradiated 316 stainless steels and pure vanadium10.1016/j.jnucmat.2005.10.011 ↗
35. Deformation mode maps for tensile deformation of neutron-irradiated structural alloys10.1016/j.jnucmat.2004.08.006 ↗
36. K. Farrell, T.S. Byun, N. Hashimoto, Mapping flow localization processes in deformation of irradiated reactor structural alloys - final report, 2003. http://www.osti.gov/servlets/purl/885795-jy25MJ/.10.2172/814077 ↗
37. R.B. Rebak, X. Lou, P.W. Emigh, M.A. Othon, P.L. Andresen, M. Song, M. Wang, Environmental cracking and irradiation resistant stainless steels by additive manufacturing, Bonisteel Blvd. (2018) 1–98.10.2172/1431212 ↗
38. SRIM
39. A brief history of environmental cracking in hot water10.5006/2881 ↗
40. A historical perspective on understanding IASCC10.1016/j.jnucmat.2019.01.057 ↗
41. The effect of build direction and heat treatment on atmospheric stress corrosion cracking of laser powder bed fusion 316 L austenitic stainless steel
42. Effect of annealing heat treatment on the microstructural evolution and mechanical properties of hot isostatic pressed 316 L stainless steel fabricated by laser powder bed fusion10.3390/met10060753 ↗
43. Hydrogen embrittlement susceptibility of additively manufactured 316 L stainless steel: influence of post-processing, printing direction, temperature and pre-straining
44. The origin and formation of oxygen inclusions in austenitic stainless steels manufactured by laser powder bed fusion
45. Irradiation assisted stress corrosion cracking of commercial and advanced alloys for light water reactor core internals10.1016/j.jnucmat.2018.12.015 ↗
46. Grain boundary segregation under electron irradiation in austenitic stainless steels modified with oversized elements10.1016/0022-3115(92)90529-T ↗
47. The influence of oversized solute additions on radiation-induced changes and post-irradiation intergranular stress corrosion cracking behavior in high-purity 316 stainless steels10.1016/S0022-3115(03)00243-5 ↗
48. A high-resolution characterization of irradiation-assisted stress corrosion cracking of proton-irradiated 316 L stainless steel in simulated pressurized water reactor primary water10.1016/j.corsci.2022.110187 ↗
49. Effects of impurities on environmentally assisted crack growth of solution-annealed austenitic steels in primary water at 325°C10.5006/1.3280550 ↗
50. Andreson · 2005 · 1
51. Formulating the strength factor α for improved predictability of radiation hardening10.1016/j.jnucmat.2015.07.009 ↗
52. The effect of hardening source in proton irradiation-assisted stress corrosion cracking of cold worked type 304 stainless steel
53. Microstructural and stress corrosion cracking characteristics of austenitic stainless steels containing silicon10.1007/s11661-009-9960-8 ↗
54. Environmentally assisted cracking of types 304 L/316 L/316NG stainless steel in 288°C water10.5006/1.3582044 ↗
55. P.L. Andresen, C.L. Briant, Role of sulfur, phosphorus and nitrogen segregation on intergranular environmental cracking of stainless steels in high temperature water, Proc. Third Int. Symp. Engironmental Degrad. Materails Nulcear Power Syst. - Water React. (1987) 371–381.
56. Investigation of slip transmission behavior across grain boundaries in polycrystalline Ni3Al using nanoindentation10.1557/jmr.2004.19.1.189 ↗
57. Nanoindentation study of slip transfer phenomenon at grain boundaries10.1557/jmr.2009.0088 ↗
58. Slip band-grain boundary interactions in commercial-purity titanium10.1016/j.actamat.2014.05.015 ↗
59. In situ and tomographic observations of defect free channel formation in ion irradiated stainless steels10.1016/j.micron.2012.01.017 ↗
60. Contribution of localized deformation to IGSCC and IASCC in austenitic stainless steels10.1007/1-4020-4972-2_335 ↗
61. Deformation of neutron-irradiated copper single crystals10.1080/14786436708229258 ↗
62. Fundamental modeling of environmental cracking for improved design and lifetime evaluation in BWRs10.1016/0308-0161(94)90142-2 ↗
63. On the origin of deformation microstructures in austenitic stainless steel: part I–microstructures10.1016/S1359-6454(01)00193-8 ↗
64. Plastic deformation in 316LN stainless steel–characterization of deformation microstructures10.1016/S0022-3115(03)00195-8 ↗
65. Deformation mode map of irradiated 316 stainless steel in true stress-dose space10.1016/j.jnucmat.2006.02.033 ↗
66. On the stress dependence of partial dislocation separation and deformation microstructure in austenitic stainless steels10.1016/S1359-6454(03)00117-4 ↗
67. On the origin of deformation microstructures in austenitic stainless steel: part II–mechanisms10.1016/S1359-6454(01)00194-X ↗
68. New twinning route in face-centered cubic nanocrystalline metals10.1038/s41467-017-02393-4 ↗
69. M.S. Wechsler, Dislocation channeling in irradiated and quenched metals, in: IS-2736; CONF-711047-1. Ames Lab., Ames, IA (United States), 1972.10.2172/4688046 ↗
70. Interaction of glissile dislocations with perfect and truncated stacking-fault tetrahedra in irradiated metals
71. Effect of ion irradiation-produced defects on the mobility of dislocations in 304 stainless steel10.1016/j.jnucmat.2010.12.026 ↗
72. On dislocation interaction with radiation-induced defect clusters and plastic flow localization in fcc metals
73. Understanding silicon-rich phase precipitation under irradiation in austenitic stainless steels10.1016/j.jnucmat.2010.08.045 ↗
74. Tailoring plasticity of austenitic stainless steels for nuclear applications: review of mechanisms controlling plasticity of austenitic steels below 400°C10.1016/j.jnucmat.2016.04.015 ↗
75. Tomographic atom probe characterization of the microstructure of a cold worked 316 austenitic stainless steel after neutron irradiation10.1016/j.jnucmat.2008.09.015 ↗
76. Localized deformation and IASCC initiation in austenitic stainless steels10.1016/j.jnucmat.2008.08.032 ↗
77. The effect of chemical composition and heat treatment conditions on stacking fault energy for Fe-Cr-Ni austenitic stainless steel10.1007/s11661-013-1943-0 ↗
78. Dislocations and stacking faults in stainless steel
79. Dislocation interactions in face-centred cubic metals, with particular reference to stainless steel
80. Effects of phosphorus, silicon and sulphur on microstructural evolution in austenitic stainless steels during electron irradiation10.1016/0022-3115(91)90274-B ↗
81. Effects of alloying elements (Mo, Si) in an austenitic stainless steel on dislocation loop nucleation under ion irradiation10.1016/0022-3115(93)90246-U ↗
82. Influence of silicon on swelling and microstructure in Russian austenitic stainless steel EI-847 irradiated to high neutron doses10.1016/j.jnucmat.2008.03.027 ↗
83. Radiation defects formed in ion-irradiated 316 L stainless steel model alloys with different Si additions10.2320/matertrans.MAW201503 ↗
84. Influence of solidification structures on radiation-induced swelling in an additively-manufactured austenitic stainless steel10.1016/j.jnucmat.2019.06.012 ↗