The effect of proton irradiation on dealloying of Alloy 800 in an aqueous environment
Source abstract
Abstract
• Alloy 800 is susceptible to dissolution of Fe and Cr in boiling caustic solution. • Selective dissolution results in a Ni-rich porous layer on Alloy 800. • Proton irradiation forms dislocation loops and elemental segregation in Alloy 800. • Proton irradiation defect production and segregation accelerate dealloying of Alloy 800. • The morphology and chemistry of the dealloyed layer formed is altered due to irradiation. The effect of prior proton irradiation on the subsequent corrosion and dealloying of Alloy 800 was investigated in a 50 wt. % NaOH caustic solution at 140 °C. Dealloying of irradiated (1 dpa) and non-irradiated Alloy 800 was characterized at the nanoscale to provide mechanistic insight. A porous surface film enriched in Ni was formed on both irradiated and non-irradiated materials due to selective dissolution of Fe and Cr. However, the microstructure and chemistry in the dealloyed layer was altered by irradiation, including deeper dealloyed layer penetration, finer porosity, and changes in the classical core-shell ligament structure in the irradiated material.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Nanoporous metals and alloys · Electrocatalysts for Energy Conversion · Metallurgy and Material Science
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (60)
Show source-provided references
1. Progress in corrosion resistant materials for supercritical water reactors10.1016/j.corsci.2009.07.007 ↗
2. Generation IV nuclear reactors: current status and future prospects10.1016/j.enpol.2013.06.101 ↗
3. Oxidation of ferritic–martensitic alloys T91, HCM12A and HT-9 in supercritical water10.1016/j.jnucmat.2007.05.023 ↗
4. Corrosion behavior of 9–12% Cr ferritic–martensitic steels in supercritical water10.1016/j.corsci.2009.12.032 ↗
5. Role of irradiation and irradiation defects on the oxidation first stages of a 316L austenitic stainless steel10.1016/j.corsci.2019.108194 ↗
6. Corrosion of phase and phase boundary in proton-irradiated 308L stainless steel weld metal in simulated PWR primary water10.1016/j.corsci.2019.108401 ↗
7. Synergistic effect of irradiation and molten salt corrosion: acceleration or deceleration?10.1016/j.corsci.2021.109434 ↗
8. Irradiation accelerated fluoride molten salt corrosion of nickel-based UNS N10003 alloy revealed by X-ray absorption fine structure10.1016/j.corsci.2019.108408 ↗
9. Proton irradiation-decelerated intergranular corrosion of Ni-Cr alloys in molten salt10.1038/s41467-020-17244-y ↗
10. Chapter 6 - corrosion issues in current and next-generation nuclear reactors
11. The effect of alloy composition on the dealloying of Ni-and Fe-based engineering alloys in boiling caustic solutions10.1149/1945-7111/ac862c ↗
12. Industrial experience on the caustic cracking of stainless steels and nickel alloys-A review
13. De-alloying of type 316 stainless steel in hot, concentrated sodium hydroxide solution10.1016/j.corsci.2004.01.011 ↗
14. Crum · 2006
15. Corrosion, stress corrosion cracking, and electrochemistry of the iron and nickel base alloys in caustic environments. Progress report, 1 March 1975–29 February 1976
16. 2.05 - Dealloying
17. Nanoporous metals by alloy corrosion: formation and mechanical properties10.1557/mrs2009.157 ↗
18. Mechanical properties of nanoporous gold in tension10.1016/j.actamat.2017.02.040 ↗
19. Decoupling the role of stress and corrosion in the intergranular cracking of noble-metal alloys10.1038/s41563-018-0162-x ↗
20. Characterization of dealloying and associated stress corrosion cracking: the effect of crystallographic orientation10.1016/j.actamat.2023.119278 ↗
21. Potential and concentration dependent electrochemical dealloying of Al2Au in sodium chloride solutions10.1021/jp210488t ↗
22. Dealloying and dealloyed materials10.1146/annurev-matsci-070115-031739 ↗
23. Relationship between the parting limit for de-alloying and a particular geometric high-density site percolation threshold10.1080/14786430903025708 ↗
24. Computer simulations of corrosion: selective dissolution of binary alloys10.1080/01418618908209817 ↗
25. An atomistic description of dealloying: porosity evolution, the critical potential, and rate-limiting behavior10.1149/1.1784820 ↗
26. Effect of stress and surface finish on Pb-caustic SCC of alloy 690TT10.1016/j.corsci.2021.109462 ↗
27. Alloying effects in high temperature molten salt corrosion10.1016/j.corsci.2021.110003 ↗
28. 3.09 - Radiation effects in Nickel-based alloys☆
29. Irradiation assisted stress corrosion cracking of commercial and advanced alloys for light water reactor core internals10.1016/j.jnucmat.2018.12.015 ↗
30. Effects of radiation-induced defects on corrosion10.1146/annurev-matsci-080819-123403 ↗
31. Irradiation-assisted stress corrosion cracking10.1515/corrrev.2011.020 ↗
32. A review of irradiation assisted stress corrosion cracking10.1016/0022-3115(94)90360-3 ↗
33. Stress corrosion cracking behavior of alloys
34. Effects of He ion irradiation on the corrosion performance of alloy GH3535 welded joint in molten FLiNaK10.1016/j.corsci.2018.10.038 ↗
35. Emulation of neutron irradiation effects with protons: validation of principle10.1016/S0022-3115(01)00751-6 ↗
36. The effects of oxide evolution on mechanical properties in proton-and neutron-irradiated Fe-9% Cr ODS steel10.1016/j.jnucmat.2016.07.022 ↗
37. Emulation of neutron damage with proton irradiation and its effects on microstructure and microchemistry of Zircaloy-410.1016/j.jnucmat.2021.153281 ↗
38. ASTM B409- 06 standard specification for Nickel-IronChromium alloy plate, sheet, and strip
39. SRIM–The stopping and range of ions in matter (2010)10.1016/j.nimb.2010.02.091 ↗
40. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
41. Coull, Z.L., Exploring de-alloying in Fe-Ni-Cr alloys and its relationship to stress corrosion cracking in nuclear high temperature water environments. 2010.
42. Particle size and shape analysis using Imagej with customized tools for segmentation of particles
43. Orientations–perfectly colored10.1107/S1600576716012942 ↗
44. Beausir · 2017 · 2017
45. Analytical electron microscopy of a crack tip extracted from a stressed Alloy 800 sample exposed to an acid sulfate environment10.1016/j.micron.2014.02.011 ↗
46. Garner · 1987
47. Characterization of faulted dislocation loops and cavities in ion irradiated alloy 800H10.1016/j.jnucmat.2017.11.012 ↗
48. Irradiated microstructure of alloy 800H10.1016/j.jnucmat.2006.02.009 ↗
49. Atom probe tomography characterization of ion and neutron irradiated Alloy 800H10.1016/j.jnucmat.2020.152598 ↗
50. Was · 2016
51. Production bias due to clustering of point defects in irradiation-induced cascades10.1080/01418619208205596 ↗
52. Segregation in irradiated alloys: the inverse Kirkendall effect and the effect of constitution on void swelling10.1088/0305-4608/8/9/008 ↗
53. On the existence and origin of sluggish diffusion in chemically disordered concentrated alloys10.1016/j.cossms.2018.05.003 ↗
54. Specific features of defect and mass transport in concentrated fcc alloys10.1016/j.actamat.2016.06.018 ↗
55. Preferential diffusion in concentrated solid solution alloys: NiFe, NiCo and NiCoCr10.1016/j.actamat.2017.01.056 ↗
56. Dealloying below the critical potential10.1149/1.1838046 ↗
57. Revised pourbaix diagrams for chromium at 25–300 C10.1016/S0010-938X(97)89244-X ↗
58. Revised Pourbaix diagrams for nickel at 25–300 C10.1016/S0010-938X(97)00002-4 ↗
59. Elevated temperature potential-pH diagrams for the Cr-H2O, Ti-H2O, Mo-H2O, and Pt-H2O systems10.5006/1.3585993 ↗
60. Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water10.1016/j.corsci.2017.08.010 ↗