Unveiling the dual role of ion irradiation on the corrosion behavior of lean-Cr FeCrAl alloys in a simulated PWR environment
Source abstract
Abstract
This study focuses on the synergistic effect of ion irradiation and corrosion on FeCrAl alloys with lean-Cr content (7–10 wt%) and with 13 wt% Cr. Upon subjecting unirradiated, 1-dpa, and 5-dpa samples to a simulated PWR environment for 15 days, it is found that irradiation alters the distribution of outer oxide particles and the composition of inner oxide layer. Our results emphasize the dual role of irradiation, depending on the perspective considered: It suppresses overall corrosion while promoting localized corrosion. Cr content effect on the resistance to irradiation-corrosion coupling is also discussed.
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Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (59)
Show source-provided references
1. Accident tolerant fuels for LWRs: a perspective10.1016/j.jnucmat.2013.12.005 ↗
2. Accident tolerant fuel cladding development: promise, status, and challenges10.1016/j.jnucmat.2017.12.043 ↗
3. K. Barrett, S. Bragg-Sitton, Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study, in, United States, 2012, pp. Medium: ED.
4. Chapter 51 - Radiation Accident at Fukushima NPP
5. J. Carmack, F. Goldner, S.M. Bragg-Sitton, L.L. Snead, Overview of the U.S. DOE Accident Tolerant Fuel Development Program, in: Conference: Top Fuel 2013, Charlotte, NC, 09/15/2013, 09/19/2013, United States, 2013, pp. Medium: ED.
6. Pint · 2019 · 1451
7. High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments10.1016/j.jnucmat.2013.05.047 ↗
8. Exploring the high-temperature steam oxidation behaviors of the lean-Cr (7–10 wt%) FeCrAl alloys10.1016/j.corsci.2021.109927 ↗
9. Development of low-Cr wrought FeCrAl cladding alloys and its irradiation tolerance and steam oxidation resistance at 1200 °C10.1016/j.corsci.2021.109998 ↗
10. Effects of Laves phase particles on recovery and recrystallization behaviors of Nb-containing FeCrAl alloys10.1016/j.actamat.2017.11.027 ↗
11. Study on high temperature creep behavior of the accident-resistant cladding Fe–13Cr–4Al-1.85Mo-0.85Nb alloy10.1016/j.msea.2020.140688 ↗
12. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors10.1016/j.jnucmat.2015.10.019 ↗
13. Effects of Cr element on the crystal structure, microstructure, and mechanical properties of FeCrAl alloys10.1016/j.msea.2021.142003 ↗
14. Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys10.1016/j.actamat.2017.07.011 ↗
15. Effect of Al and Cr content on air and steam oxidation of FeCrAl alloys and commercial APMT alloy10.1007/s11085-017-9745-1 ↗
16. Mechanism of Al on FeCrAl steam oxidation behavior and molecular dynamics simulations10.1016/j.jallcom.2020.154310 ↗
17. Early corrosion behaviour of irradiated FeCrAl alloy in a simulated pressurized water reactor environment10.1016/j.corsci.2020.108824 ↗
18. Uniform corrosion of FeCrAl alloys in LWR coolant environments10.1016/j.jnucmat.2016.06.047 ↗
19. A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment10.1016/j.corsci.2015.02.027 ↗
20. Effect of surface roughness on the development of protective Al 2 O 3 on Fe–10Al (at%) alloys containing 0–10 at% Cr10.1016/j.apsusc.2006.01.027 ↗
21. Passivity and inhibition during the oxidation of metals at elevated temperatures10.1016/S0010-938X(65)80003-8 ↗
22. The influence of alloying elements on the development and maintenance of protective scales10.1007/BF01046725 ↗
23. Microstructural stability of Fe–Cr–Al alloys at 450–550 °C10.1016/j.jnucmat.2014.11.101 ↗
24. Aluminum partitioning during phase separation in Fe–20%Cr–6%Al ODS alloy10.1007/s10853-007-2228-z ↗
25. Effect of α–α′ phase separation on notch impact behavior of oxide dispersion strengthened (ODS) Fe20Cr5Al alloy10.1016/j.matdes.2013.08.007 ↗
26. α′ precipitation in neutron-irradiated Fe–Cr alloys10.1016/j.scriptamat.2013.10.001 ↗
27. Microstructural changes in a neutron-irradiated Fe–15 at%Cr alloy10.1016/j.jnucmat.2014.08.026 ↗
28. Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys10.1016/j.jnucmat.2015.06.023 ↗
29. Oxidation of Zircaloy-4 during in situ proton irradiation and corrosion in PWR primary water10.1557/jmr.2014.408 ↗
30. Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water10.1016/j.corsci.2017.08.010 ↗
31. Influence of irradiation on the oxide film formed on 316 L stainless steel in PWR primary water10.1007/s11085-013-9401-3 ↗
32. Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors10.1016/j.jallcom.2021.159235 ↗
33. On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys10.1016/S0022-3115(98)00010-5 ↗
34. Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels10.1016/j.actamat.2010.10.055 ↗
35. Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water10.1016/j.jnucmat.2020.152108 ↗
36. Incipient corrosion of FeCrAl alloys in H3BO3- and LiOH-containing pure water at 360 °C and 18.5 MPa10.1016/j.jnucmat.2021.153299 ↗
37. Corrosion behavior of FeCrAl alloy and NiCr coated Zircaloy-4 in hydrogenated water10.1016/j.ijhydene.2022.03.128 ↗
38. From ultrasoft pseudopotentials to the projector augmented-wave method10.1103/PhysRevB.59.1758 ↗
39. Projector augmented-wave method10.1103/PhysRevB.50.17953 ↗
40. Atoms, molecules, solids, and surfaces: applications of the generalized gradient approximation for exchange and correlation10.1103/PhysRevB.46.6671 ↗
41. Correlation hole of the spin-polarized electron gas, with exact small-wave-vector and high-density scaling10.1103/PhysRevB.44.13298 ↗
42. Special points for Brillouin-zone integrations10.1103/PhysRevB.13.5188 ↗
43. A comparative study on the corrosion performance of four FeCrAl alloys with different Cr contents in contact with oxygen-saturated LBE10.1016/j.jmrt.2023.02.033 ↗
44. Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment10.1016/j.matdes.2023.111948 ↗
45. First-principles study of ferromagnetism in iron chromite spinels: FeCr2O4 and CrFe2O410.1142/S2010324719500140 ↗
46. Adhesion and electric structure at Fe3O4/FeCr2O4 interface: a first principles study10.1016/j.jallcom.2021.160065 ↗
47. The history of the point defect model for the passive state: a brief review of film growth aspects10.1016/j.electacta.2010.11.005 ↗
48. The point defect model for the passive state10.1149/1.2069096 ↗
49. Accelerated steam corrosion behavior of Fe-ion irradiated RAFM steel: the role of displacement damage10.1016/j.corsci.2023.111074 ↗
50. Corrosion performance of He+ ion irradiated 304 L stainless steel made by laser powder bed fusion in simulated PWR water10.1016/j.corsci.2022.110545 ↗
51. Role of irradiation and irradiation defects on the oxidation first stages of a 316L austenitic stainless steel10.1016/j.corsci.2019.108194 ↗
52. 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 ↗
53. Corrosion behavior of stainless steels in simulated PWR primary water—effect of chromium content in alloys and dissolved hydrogen10.1080/18811248.2008.9711883 ↗
54. Surface study of the oxidation of type 304L stainless steel at 600 K in air10.1007/BF00666841 ↗
55. Defect-interface interactions10.1016/j.pmatsci.2015.02.001 ↗
56. Mechanism of interaction between interface and radiation defects in metal10.7498/aps.68.20190128 ↗
57. The effect of Laves phase on heavy-ion radiation response of Nb-containing FeCrAl alloy for accident-tolerant fuel cladding10.1016/j.fmre.2022.01.028 ↗
58. Uniform corrosion behavior of FeCrAl alloys in borated and lithiated high temperature water10.1016/j.jmst.2020.07.026 ↗
59. Electronic properties of transition-metal oxides—I: distortions from cubic symmetry10.1016/0022-3697(57)90043-4 ↗