Corrosion behavior of Nb-doped FeCrAl alloy in 500°C steam
Source abstract
Abstract
The corrosion behavior of Fe-13Cr-4Al-2.2Mo, a candidate cladding material for accident tolerant fuel, doped with varying concentrations of Nb (0, 0.5, 1.0, and 1.5 wt%), was investigated under conditions of 500°C/10.3 MPa superheated steam. Upon exposure, a triple-layer oxide film comprising outer, inner, and diffusion oxide layers was formed. The results indicate that the addition of Nb significantly enhances the corrosion resistance of this alloy by reducing the thickness and porosity of the oxide film. The enhanced volume diffusion rate of Al and Cr, facilitated by the solid solution Nb, along with the inhibited inward diffusion of oxidant ions along grain boundaries owing to Laves phase precipitates, contributed to the enhanced corrosion resistance of the Nb-doped Fe-13Cr-4Al-2.2Mo alloy.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (80)
Show source-provided references
1. The maturing of nuclear fuel: Past to Accident Tolerant Fuel10.1016/j.pnucene.2017.07.016 ↗
2. Accident tolerant fuel cladding development: promise, status, and challenges10.1016/j.jnucmat.2017.12.043 ↗
3. Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors10.1016/j.jnucmat.2021.153090 ↗
4. Recent advances in protective coatings for accident tolerant Zr-based fuel claddings10.3390/coatings11050557 ↗
5. Accident tolerant fuels for LWRs: a perspective10.1016/j.jnucmat.2013.12.005 ↗
6. Alloy selection for accident tolerant fuel cladding in commercial light water reactors
7. Recent studies on potential accident-tolerant fuel-cladding systems in light water reactors10.1007/s41365-020-0741-9 ↗
8. Material selection for accident tolerant fuel cladding
9. Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors10.1007/s11837-017-2705-z ↗
10. Oxidation Kinetics of Ferritic Alloys in High-Temperature Steam Environments10.1007/s11837-017-2639-5 ↗
11. High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments.10.1016/j.jnucmat.2013.05.047 ↗
12. Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures10.1016/j.actamat.2022.117843 ↗
13. Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys10.1016/j.jnucmat.2017.03.038 ↗
14. Influence of composition and heating schedules on compatibility of FeCrAl alloys with high-temperature steam10.1016/j.jnucmat.2018.09.026 ↗
15. Uniform corrosion of FeCrAl alloys in LWR coolant environments10.1016/j.jnucmat.2016.06.047 ↗
16. Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors10.1016/j.jallcom.2021.159235 ↗
17. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding10.1016/j.jnucmat.2020.152221 ↗
18. Addition of niobium in Fe-13Cr-4.5Al-2Mo alloy used as ATF cladding: Effect on high temperature water corrosion and in-situ electrochemistry10.1016/j.matdes.2022.110854 ↗
19. Uniform corrosion behavior of FeCrAl alloys in borated and lithiated high temperature water10.1016/j.jmst.2020.07.026 ↗
20. Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments10.1515/corrrev-2017-0011 ↗
21. Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment10.1016/j.matdes.2023.111948 ↗
22. Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500–1500C in steam10.1016/j.jnucmat.2022.153696 ↗
23. Oxidation of FeCrAl alloy: influence of temperature and atmosphere on scale growth rate and mechanism10.1016/S0257-8972(00)00989-0 ↗
24. Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C10.1007/s11837-018-2979-9 ↗
25. The transition from transient oxide to protective Al2O3 scale on Fe–Cr–Al alloys during heating to 1000°C10.1007/s11085-017-9778-5 ↗
26. Effect of steam on high temperature oxidation behaviour of alumina-forming alloys10.1179/0960340914Z.00000000058 ↗
27. The effects of Cr and Al concentrations on the oxidation behavior of oxide dispersion strengthened ferritic alloys10.1016/j.corsci.2013.07.004 ↗
28. Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys10.1016/j.jnucmat.2015.06.023 ↗
29. Irradiation-enhanced α′ precipitation in model FeCrAl alloys10.1016/j.scriptamat.2016.02.002 ↗
30. Precipitation of α′ in neutron irradiated commercial FeCrAl alloys10.1016/j.scriptamat.2017.08.022 ↗
31. Systematic study of radiation-induced segregation in neutron-irradiated FeCrAl alloys10.1016/j.jnucmat.2022.154205 ↗
32. Post irradiation examination of nanoprecipitate stability and α′ precipitation in an oxide dispersion strengthened Fe-12Cr-5Al alloy10.1016/j.scriptamat.2018.10.047 ↗
33. Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy10.1016/j.jnucmat.2019.151784 ↗
34. Mapping of 475°C embrittlement in ferritic Fe–Cr–Al alloys10.1016/j.scriptamat.2010.08.015 ↗
35. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors10.1016/j.jnucmat.2015.10.019 ↗
36. Y. Yamamoto, Y. Yang, K.G. Field, K. Terrani, B.A. Pint, L.L. Snead. Letter report documenting progress of second generation ATF FeCrAl alloy fabrication. Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States) 2014.10.2172/1134712 ↗
37. Effects of Nb-doping on the mechanical properties and high-temperature steam oxidation of annealing FeCrAl fuel cladding alloys10.1016/j.msea.2020.140500 ↗
38. Effects of Laves phase particles on recovery and recrystallization behaviors of Nb-containing FeCrAl alloys10.1016/j.actamat.2017.11.027 ↗
39. Effect of niobium content on irradiation microstructure and hardening in FeCrAl-based alloys10.1016/j.jmst.2021.04.020 ↗
40. Microstructural control of FeCrAl alloys using Mo and Nb additions10.1016/j.matchar.2017.08.008 ↗
41. Oxidation characteristics of Fe22Cr5Al3Mo-xNb alloys in high temperature steam10.1016/j.corsci.2021.109722 ↗
42. Effect of Nb on microstructure and corrosion resistance of Fe22Cr5Al3Mo alloy
43. Microstructural understanding of general and localized corrosion of Fe13Cr4Al2Mo1.2Nb alloy in high temperature aerated water and superheated steam10.1016/j.corsci.2022.110341 ↗
44. Effects of annealing temperature on the microstructure, textures and tensile properties of cold-rolled Fe–13Cr–4Al alloys with different Nb contents10.1016/j.msea.2020.140236 ↗
45. Investigation on early formation and evolution of oxide scales on ferritic–martensitic steels in supercritical water10.1016/j.corsci.2018.02.036 ↗
46. Corrosion of 9Cr steel in CO2 at intermediate temperature I: mechanism of void-induced duplex oxide formation10.1007/s11085-011-9271-5 ↗
47. Oxidation mechanism of an Fe–9Cr–1Mo steel by liquid Pb–Bi eutectic alloy at 470°C (Part II)10.1016/j.corsci.2008.06.051 ↗
48. EFTEM and EELS analysis of the oxide layer formed on HCM12A exposed to SCW10.1016/j.jnucmat.2012.06.017 ↗
49. A high-resolution study of the different surface state effects on the corrosion behaviors of a ferritic steel and an austenitic steel in supercritical water10.1016/j.corsci.2022.110757 ↗
50. Corrosion behavior of 9–12% Cr ferritic–martensitic steels in supercritical water.10.1016/j.corsci.2009.12.032 ↗
51. The oxidation behaviour of metals and alloys at high temperatures in atmospheres containing water vapour: a review10.1016/j.pmatsci.2007.11.001 ↗
52. Young · 2008
53. Effect of Y on the corrosion behavior of Fe22Cr5Al3Mo alloy in 500°C super-heated steam10.1016/j.corsci.2021.110022 ↗
54. Oxidation behavior of Fe-20Cr-25Ni-Nb austenitic stainless steel in high-temperature environment with small amount of water vapor10.1016/j.corsci.2018.09.016 ↗
55. A review of the oxidation behaviour of structural alloys in steam10.1179/095066010X12646898728165 ↗
56. On the role of mechanical deformation in the environmental degradation of 310S stainless steels in supercritical carbon dioxide10.1016/j.corsci.2022.110537 ↗
57. Effect of shot blasting on oxidation of TP304 austenitic stainless steel in steam
58. Understanding the surface oxide evolution of T91 ferritic-martensitic steel in supercritical water through advanced characterization10.1016/j.actamat.2020.05.016 ↗
59. High-resolution characterization of the internal and external oxidation of austenitic alloys in supercritical water10.1016/j.scriptamat.2021.113814 ↗
60. Oxidation of ferritic and ferritic–martensitic steels in flowing and static supercritical water10.1016/j.corsci.2015.10.017 ↗
61. Corrosion and stress corrosion cracking in supercritical water10.1016/j.jnucmat.2007.05.017 ↗
62. Corrosion behavior of ferritic/martensitic steel P92 in supercritical water10.1016/j.supflu.2009.06.019 ↗
63. Oxidation behavior of ferritic–martensitic and ODS steels in supercritical water.10.1016/j.jnucmat.2012.03.009 ↗
64. New insights into the oxidation mechanisms of a Ferritic-Martensitic steel in high-temperature steam10.1016/j.actamat.2020.05.052 ↗
65. The origin of different morphology of internal oxide precipitates in ferritic and austenitic steels10.1016/j.jmst.2023.03.035 ↗
66. Corrosion of ferritic–martensitic steels in steam and supercritical water10.1016/j.jnucmat.2012.09.037 ↗
67. Predictions and analyses on the growth behavior of oxide scales formed on ferritic–martensitic in supercritical water10.1007/s11085-019-09912-2 ↗
68. Atomic origins of water-vapour-promoted alloy oxidation10.1038/s41563-018-0078-5 ↗
69. Einfluss von wasserdampf und kohlendioxyd auf die oxydation von eisen in sauerstoff bei hohen temperaturen10.1016/S0010-938X(65)90500-7 ↗
70. High-temperature strengthening mechanism and thermal stability of Laves phase in ferritic matrix10.1016/j.msea.2022.144183 ↗
71. Effects of Nb and Mo on 1200C steam oxidation and mechanical properties of FeCrAl alloys for fuel cladding materials
72. Role of Nb in promoting protective scale formation on Al2O3-forming austenitic alloys10.1016/j.corsci.2022.110751 ↗
73. Effect and role of alloyed Nb on the air oxidation behaviour of Ni-Cr-Fe alloys at 1000°C10.1016/j.corsci.2017.08.003 ↗
74. Effect of active elements on the oxidation behaviour of Cr2O3-formers
75. Current thoughts on reactive element effects in alumina-forming systems: In Memory of John Stringer10.1007/s11085-016-9625-0 ↗
76. Development of nano-oxide particles dispersed alumina scale formed on Zr-added FeCrAl ODS ferritic alloys
77. Development of accident tolerant FeCrAl-ODS steels utilizing Ce-oxide particles dispersion10.1016/j.jnucmat.2018.02.020 ↗
78. Effects of yttrium on the oxidation behavior of Fe13Cr6AlY alloys under 1200 °C steam10.1016/j.jallcom.2023.170642 ↗
79. First principles studies of TiAl-based alloys10.1016/S1471-5317(02)00038-X ↗
80. H.S.A.S. WU. Effect of Nb on the Bonding Characteristics of TiAl Intermetallic Compounds: A First-principle Study. 2008. pp. 1669-1675.