Microstructure characterization of FeCrAl alloys tubes and corrosion behavior after exposure to oxygen-saturated and oxygen-depleted static lead-bismuth eutectic at 650 ℃
Bibliographic record
Abstract
No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.
Source: Not provided · Quality: missing
Research context
OpenAlex topics: Nuclear reactor physics and engineering · High-Temperature Coating Behaviors · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (43)
Show source-provided references
1. Lead-bismuth eutectic (LBE): a coolant candidate for Gen. IV advanced nuclear reactor concepts10.1002/adem.201300296 ↗
2. Pioro · 2016
3. Fazio · 2015
4. Environmental degradation of structural materials in liquid lead-and lead-bismuth eutectic-cooled reactors10.1016/j.pmatsci.2022.100920 ↗
5. Heavy liquid metal corrosion of structural materials in advanced nuclear systems10.1007/s11837-013-0663-7 ↗
6. Effect of oxygen on corrosion of an alumina-forming duplex steel in static liquid lead-bismuth eutectic at 55010.1016/j.corsci.2021.109591 ↗
7. 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 ↗
8. Oxidation behaviour of ferritic/martensitic steels in stagnant liquid LBE saturated by oxygen at 600 ℃10.1016/j.jnucmat.2014.11.018 ↗
9. 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 ↗
10. Corrosion behavior of austenitic steels 1.4970, 316L and 1.4571 in flowing LBE at 450 and 550 ℃ with 10−7mass% dissolved oxygen10.1016/j.jnucmat.2014.08.024 ↗
11. Dissolution corrosion of 316L austenitic stainless steels in contact with static liquid lead-bismuth eutectic (LBE) at 50010.1016/j.jnucmat.2017.04.004 ↗
12. Dissolution and oxidation behaviour of various austenitic steels and Ni rich alloys in lead-bismuth eutectic at 520 ℃10.1016/j.jnucmat.2015.11.005 ↗
13. Effect of deformation twinning on dissolution corrosion of 316L stainless steels in contact with static liquid lead-bismuth eutectic (LBE) at 500 ℃10.1016/j.jnucmat.2018.08.030 ↗
14. Selection of fuel cladding material for nuclear fission reactors10.1016/j.engfailanal.2011.06.010 ↗
15. A review of steel corrosion by liquid lead and lead-bismuth10.1016/j.corsci.2009.03.013 ↗
16. Influence of plastic deformation on dissolution corrosion of type 316L austenitic stainless steel in static, oxygen-poor liquid lead-bismuth eutectic at 500 ℃, Corros
17. Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review10.1088/2515-7655/ac6f7f ↗
18. Improvement of low-cycle fatigue behavior of modified 9Cr-1Mo steels at 450 ℃ in liquid LBE environment by the addition of Si element10.1016/j.nucengdes.2023.112570 ↗
19. Low cycle fatigue behavior of a modified 9Cr-1Mo ferritic-martensitic steel in lead-bismuth eutectic at 350 ℃-Effects of oxygen concentration in the liquid metal and strain rate10.1016/j.corsci.2015.02.022 ↗
20. Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors10.1016/j.jallcom.2021.159235 ↗
21. Corrosion behavior of ferritic FeCrAl alloys in simulated BWR normal water chemistry10.1016/j.jnucmat.2020.152744 ↗
22. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding10.1016/j.jnucmat.2020.152221 ↗
23. Corrosion behaviors of FeCrAl alloys exposed to oxygen-saturated static lead bismuth eutectic at 55010.1016/j.corsci.2022.110767 ↗
24. Oxidation studies of Fe10CrAl-RE alloys exposed to Pb at 550 ℃ for 10,000h10.1016/j.jnucmat.2013.07.023 ↗
25. Oxide scale formation on 316L and FeCrAl steels exposed to oxygen controlled static LBE at temperatures up to 80010.1016/j.solmat.2015.09.007 ↗
26. A study of deformation and strain induced in bulk by the oxide layers formation on a Fe-Cr-Al alloy in high-temperature liquid Pb-Bi eutectic10.1016/j.actamat.2018.03.041 ↗
27. Corrosion behaviors of ODS-FeCrAl in oxygen-saturated lead-bismuth eutectic at 550 ℃: Effects of grain boundaries and minor elements10.1016/j.jnucmat.2023.154710 ↗
28. Oxidative passivation of Fe-Cr-Al steels in lead-bismuth eutectic under oxygen-controlled static conditions at 700 ℃ and 800 ℃10.1016/j.jnucmat.2019.06.004 ↗
29. Development and application of a safety analysis code for small Lead cooled Fast Reactor SVBR 75/10010.1016/j.anucene.2015.03.021 ↗
30. Current status and future prospective of advanced radiation resistant oxide dispersion strengthened steel (ARROS) development for nuclear reactor system applications10.1016/j.net.2015.12.005 ↗
31. Cold-rolling & annealing process for nuclear grade wrought FeCrAl cladding alloy to enhance the strength and ductility10.1016/j.jmatprotec.2019.116434 ↗
32. Oak Ridge National Laboratory10.2172/2311323 ↗
33. Microstructure and texture evolution and ring-tensile properties of recrystallized FeCrAl ODS cladding tubes10.1016/j.msea.2019.138636 ↗
34. Microstructure and texture evolutions in FeCrAl cladding tube during pilger processing10.1016/j.jmrt.2023.06.255 ↗
35. Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin wall tube fabrication10.1016/j.msea.2017.06.036 ↗
36. Textures of ferritic stainless steels10.1179/mst.1993.9.4.302 ↗
37. Recrystallization and texture evolution of warm-pilgered FeCrAl alloy tube during annealing at 85010.1016/j.jnucmat.2022.153575 ↗
38. Oxidation mechanism of a Fe-9Cr-1Mo steel by liquid Pb-Bi eutectic alloy (Part I)10.1016/j.corsci.2008.06.050 ↗
39. Spectroscopic and microscopic investigation of the corrosion of 316/316L stainless steel by lead-bismuth eutectic (LBE) at elevated temperatures: importance of surface preparation10.1016/j.jnucmat.2004.03.006 ↗
40. Dissolution condensation mechanism of stress corrosion cracking in liquid metals: driving force and crack kinetics10.1007/s11661-010-0429-6 ↗
41. Dissolution corrosion of FeCrAl alloy exposed to oxygen-depleted lead-bismuth eutectic containing Ni impurities at 600 ℃
42. Corrosion behavior of cold-worked austenitic stainless steels in liquid lead-bismuth eutectic10.1016/j.jnucmat.2014.02.006 ↗
43. Effect of cold rolling on the oxidation resistance of T91 in oxygen-saturated stagnant liquid lead-bismuth eutectic at 450 ℃10.1016/j.jnucmat.2016.04.046 ↗