Effect of moisture on corrosion of Ni-based alloys in molten alkali fluoride FLiNaK salt environments
Source abstract
Abstract
Abstract We investigated the corrosion characteristics on several selected alloys at 600 and 700 °C in FLiNaK molten salts with different moisture contents. Hastelloys-N and Hastelloys-B3 exhibited better corrosion resistances, while Haynes 263 showed the poorest corrosion resistance. The mass loss of the tested alloys is primarily determined by the purity of FLiNaK salts; however, the effect of temperature becomes more important on the mass loss of the tested alloys in the non-purified FLiNaK salts. When the residual moisture is present in the FLiNaK salts, the mass losses of the tested alloys varied linearly with original Cr content plus one-third of Mo content. The results of structural characterization revealed that the tested alloys in the FLiNaK salts with higher moisture content would aggravate intergranular corrosion and pitting.
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Research context
OpenAlex topics: Advanced ceramic materials synthesis
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References (19)
Show source-provided references
1. D.F. Williams, Assessment of candidate molten salt coolants for the NGNP/NHI Heat-Transfer Loop, Oak Ridge National Laboratory, ORNL/TM-2006/69, 2006.10.2172/1360677 ↗
2. D. Williams, D. Wilson, J. Keiser, L. Toth, J. Caja, Coolant/material interactions in advanced reactor systems, research on molten fluorides as high temperature heat transfer agents, in: Proceedings of Global 2003, Embedded Topical in 2003 American Nuclear Society Winter Meeting, New Orleans, LA, 16-20 November 2003.
3. Corrosion: Fundamentals, Testing, and Protection
4. W.R. Grimes, Chemical research and development for the molten-salt breeder reactor, Oak Ridge National Laboratory, ORNL/TM-1853, 1967.10.2172/4355677 ↗
5. Chemical Aspects of Molten Fluoride Salt Reactor Fuels
6. D.F. Williams, Assessment of Candidate Molten Salt Coolants for the Advanced High-Temperature Reactor (AHTR), Oak Ridge National Laboratory, ORNL/TM-2006/12, 2006.10.2172/885975 ↗
7. Olson · J. Fluorine Chem. · 2009 · 130 · 6710.1016/j.jfluchem.2008.05.008 ↗
8. Olsen · J. Nucl. Mater. · 2011 · 411 · 5110.1016/j.jnucmat.2011.01.032 ↗
9. Ludwig · Sci Technol · 2011 · 46 · 360
10. J.W. Koger, A.P. Litman, Compatibility of molybdenum-base alloy TZM with LiF-BeF2-ThF4-UF4 (68–20-11.7-0.3 mol%) at 1100 C, Oak Ridge National Laboratory, ORNL/TM-2724, 1969.
11. Kondo · Fusion Eng. Des. · 2010 · 85 · 143010.1016/j.fusengdes.2010.03.064 ↗
12. Kondo · Fusion Eng. Des. · 2009 · 84 · 108110.1016/j.fusengdes.2009.02.046 ↗
13. Blandine Laurenty, The LM-LS experiment: investigating corrosion control, in: Liquid fluoride salts, by liquid alkali Metal, Master thesis, University of California Berkeley, California, USA, 2006.
14. J.W. Koger, Mass transfer between Hastelloy N and Alloy No. 25 in a molten sodium flurobrate mixture, ORNL-3488, Oak Ridge National Laboratory, Oak Ridge, TN, 1971.
15. V. Kirillov, V. Fedulov, Translated from Fiziko-Khimcheskaya Mekhanika Materialov 16(6) (1980) 22–25.
16. A.K. Misra, J.D. Whittenberger, Fluoride Salts and Container Materials for Thermal Energy Storage Applications in the Temperature range 973 to 1400K, in: Proceedings of the 22nd Intersociety Energy Conversion Engineering Conference cosponsored by the AIAA ANS ASME SAE IEEE ACS and AIChE, Philadelphia, PA, 10-14 August 1987.10.2514/6.1987-9226 ↗
17. W. B. Cottrell, Disassembly and postoperative examination of the aircraft reactor experiment, Oak Ridge National Laboratory, ORNL/TM-1868, 1958.10.2172/4223435 ↗
18. C.J. Tyreman, The high temperature corrosion of metals and alloys in HF-containing environments, PhD thesis, University of Manchester, Manchester, UK, 1986.
19. Li · Fusion Sci. Technol. · 2009 · 56 · 32310.13182/FST09-A8922 ↗