Synergistic effects of Si and Y on corrosion behavior of cast cladding steels by pre-laying Y powder for nuclear applications in static liquid LBE
Source abstract
Abstract
Ferritic/martensitic (F/M) steels with (9–12)wt.% Cr are potential candidates for structural applications in Lead-cooled Fast Reactors (LFR) due to their low solubility in liquid Lead-Bismuth Eutectic (LBE) coolant. How to improve corrosion resistance of 9-12Cr F/M steels has been a challenge. Here we cast three steels by pre-laying yttrium (Y) powder on the bottom of mold to obtained Y-bearing steels. Precursory work on this family of Y-bearing steels has previously highlighted them with the longer steady state creep stage and the lower minimum creep rate at 650 °C under 120 MPa, which has motivated their study under more extreme conditions, such as corrosion behavior in liquid LBE. We find a synergistic effect of Si and Y on both optimizing structure and reducing thickness of oxide scale at various oxygen concentrations, exposing temperatures and test times. The oxide scale changed from dual layers to single spinel layer, the thickness reduced from 36 μm to 4 μm, dissolution corrosion and PbBi penetration were inhibited. Low diffusion coefficient of ions in SiO 2 and Y segregation on grain boundaries of steels hinder the outward diffusion of cations, and strong affinity between Y and O leads to the formation of Y 2O 3 preferentially, acting as nucleation sites of SiO 2 and Cr 2O 3, accelerating a dense and continuous oxide scale. This work enables the development of structure steels with high corrosion resistance for various high temperature application, including boiler steel, gas turbine, and heat exchanger tubes.
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 (48)
Show source-provided references
1. Pioro · 2016
2. Lead-bismuth eutectic (LBE): a coolant candidate for Gen. IV advanced nuclear reactor concepts10.1002/adem.201300296 ↗
3. Heavy liquid metal corrosion of structural materials in advanced nuclear systems10.1007/s11837-013-0663-7 ↗
4. Materials challenges for generation IV nuclear energy systems10.13182/NT08-A3961 ↗
5. A review of steel corrosion by liquid lead and lead-bismuth10.1016/j.corsci.2009.03.013 ↗
6. Selection of fuel cladding material for nuclear fission reactors10.1016/j.engfailanal.2011.06.010 ↗
7. Dissolution and oxidation behaviour of various austenitic steels and Ni rich alloys in lead-bismuth eutectic at 520°C10.1016/j.jnucmat.2015.11.005 ↗
8. Dissolution corrosion of 316L austenitic stainless steels in contact with static liquid lead-bismuth eutectic (LBE) at 500°C10.1016/j.jnucmat.2017.04.004 ↗
9. High-temperature corrosion behaviors of structural materials for lead-alloy-cooled fast reactor application10.3390/app11052349 ↗
10. Mechanical properties of modified 9Cr-1Mo (T91) irradiated at ⩽300°C in SINQ Target-310.1016/S0022-3115(03)00100-4 ↗
11. Effects of temperature and strain rate on the mechanical properties of T91 material tested in liquid lead bismuth eutectic10.1016/j.jnucmat.2006.05.034 ↗
12. Irradiation influence on swelling and corrosion behavior of ADS beam window materials, t91 steels
13. Low cycle fatigue behavior of a modified 9Cr-1Mo ferritic-martensitic steel in lead-bismuth eutectic at 350°C-Effects of oxygen concentration in the liquid metal and strain rate10.1016/j.corsci.2015.02.022 ↗
14. Influence of temperature on the interaction mode of T91 and AISI 316L steels with Pb-Bi melt saturated by oxygen10.1016/j.corsci.2008.02.006 ↗
15. Corrosion behavior of steels in liquid lead-bismuth with low oxygen concentrations10.1016/j.jnucmat.2007.05.051 ↗
16. The formation mechanism and effect of amorphous SiO2 on the corrosion behaviour of Fe-Cr-Si ODS alloy in LBE at 550°C10.1016/j.corsci.2021.109634 ↗
17. Corrosion behavior of Si-enriched steels for nuclear applications in liquid lead-bismuth10.1016/j.jnucmat.2013.02.022 ↗
18. Q.Z. Yan, Z.Y. Hong, Method for preparing oxide dispersion strengthening F/M steel using smelting and casting process: U.S. Patent No. 11203792B2, 2021.
19. A new method for preparing 9Cr-ODS steel using elemental yttrium and Fe2O3 oxygen carrier10.1016/j.jallcom.2018.08.196 ↗
20. Enhanced creep resistance of Y-bearing 9Cr ferritic/martensitic steel via vacuum casting technique10.1016/j.jmrt.2019.08.003 ↗
21. Oxygen concentration measurement and control of lead-bismuth eutectic in a small, static experimental facility10.1080/00223131.2019.1700842 ↗
22. Investigation on oxygen controlled liquid lead corrosion of surface treated steels10.1016/S0022-3115(99)00211-1 ↗
23. Oxidation behavior of ferritic/martensitic steels in stagnant liquid LBE saturated by oxygen at 600°C10.1016/j.jnucmat.2014.11.018 ↗
24. Effect of silicon on the oxidation resistance of 9 wt.% Cr heat resistance steels in 550°C lead-bismuth eutectic10.1016/j.corsci.2016.04.020 ↗
25. Influence of temperature on the interaction mode of T91 and AISI 316L steels with Pb-Bi melt saturated by oxygen10.1016/j.corsci.2008.02.006 ↗
26. Selective leaching of nickel and chromium from Type 316 austenitic steel in oxygen-containing lead-bismuth eutectic (LBE)10.1016/j.corsci.2014.03.016 ↗
27. Corrosion behavior of austenitic steels 1.4970, 316L and 1.4571 in flowing LBE at 450 and 550°C with 10−7mass% dissolved oxygen10.1016/j.jnucmat.2014.08.024 ↗
28. Characterization of corrosion phenomena and kinetics on T91 ferritic/martensitic steel exposed at 450 and 550°C to flowing Pb-Bi eutectic with 10−7 mass% dissolved oxygen10.1016/j.jnucmat.2017.07.031 ↗
29. Liquid metal corrosion of T91 and A316L materials in Pb-Bi eutectic at temperatures 400-600°C10.1016/j.corsci.2005.04.001 ↗
30. Corrosion behaviour of martensitic and austenitic steels in flowing lead-bismuth eutectic10.1016/j.jnucmat.2011.01.108 ↗
31. Corrosion behaviour of steels in lead-bismuth at 823 K10.1016/j.jnucmat.2004.07.013 ↗
32. Corrosion behaviour of steels and refractory metals and tensile features of steels exposed to flowing PbBi in the LECOR loop10.1016/S0022-3115(03)00009-6 ↗
33. Corrosion resistance of alloys F91 and Fe-12Cr-2Si in lead-bismuth eutectic up to 715°C10.1016/j.jnucmat.2012.11.010 ↗
34. The influence of Y and Nb addition on the corrosion resistance of Fe-Cr-Al-Ni model alloys exposed to oxygen-containing molten Pb10.1016/j.corsci.2020.109152 ↗
35. Kubaschewski · 1979
36. Lim · 2006
37. Solubility and activity of oxygen in Pb-Bi melts10.2320/matertrans.47.122 ↗
38. The influence of alloying elements on the development and maintenance of protective scales10.1007/BF01046725 ↗
39. Gupta · 2003
40. Diffusion of iron in Cr2O3: polycrystals and thin films10.1016/j.msea.2004.09.033 ↗
41. The diffusion of Fe3+ in amorphous SiO2 and the protective properties of SiO2 layers10.1016/0010-938X(81)90063-9 ↗
42. Fazio · 2015
43. The influence of yttrium on oxide scale growth and adherence10.1007/BF00666845 ↗
44. Improved oxidation and hot corrosion resistance of Ta-doped NiAlY alloy at 750°C10.1002/maco.202112523 ↗
45. Effects of minor additions and impurities on oxidation behaviour of FeCrAl alloys. Development of novel surface coatings compositions10.1002/maco.200503915 ↗
46. Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors10.1016/j.jallcom.2021.159235 ↗
47. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors10.1016/j.jnucmat.2015.10.019 ↗
48. Oxidation kinetics of Y-doped FeCrAl-alloys in low and high pO2 gases10.1002/maco.200905432 ↗