Evaluation of Corrosion Behavior of Various Fe- and Ni-Based Alloys in Molten Li2BeF4 (FLiBe)

Sankar, Krishna Moorthi; Keiser, James R.; Sulejmanovic, Dino; Lowe, Tracie M.; Singh, Preet M.

doi:10.1080/00295450.2023.2229176

Evaluation of Corrosion Behavior of Various Fe- and Ni-Based Alloys in Molten Li₂BeF₄ (FLiBe)

Journal Article · Mon Jul 24 00:00:00 EDT 2023 · Nuclear Technology

DOI:https://doi.org/10.1080/00295450.2023.2229176· OSTI ID:1997782

^[1]; ^[2]; Sulejmanovic, Dino ^[2]; Lowe, Tracie M. ^[2]; ^[1]

Georgia Institute of Technology, Atlanta, GA (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Reliable performance of structural alloys is essential for the successful implementation of Generation-IV fluoride salt–cooled high-temperature reactors (FHRs). Most FHR designs are considering molten salt (2LiF-BeF₂), or FLiBe, as a primary coolant or fuel carrier. The main corrosion mechanism for alloys exposed to molten fluoride salts is the selective dealloying of active alloying elements. Alloy composition has a significant effect on their high-temperature mechanical properties, but also affects their corrosion behavior. Although Hastelloy-N and its variants show good corrosion resistance compared to higher Cr-containing Ni- or Fe-based alloys, the mechanical properties of these alloys degrade quickly at temperatures above ~600°C. Twelve Ni-based or Fe-based alloys were selected due to their high temperature stability or their low Cr alloy composition and tested for their corrosion behavior in FLiBe. The results show that the mode and the extent of alloy degradation by selective dissolution mechanism corelates well with the overall alloy composition, and not just the concentration of active elements. It was found that there was good correlation between weight loss of the tested alloys and the ratio of major active elements (Cr, Mn) to that of the more noble alloying elements (Ni, Mo).

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)

Grant/Contract Number:: AC05-00OR22725; NE0008749

OSTI ID:: 1997782

Journal Information:: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 00 Vol. 00; ISSN 0029-5450

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

References (26)

Effects of High-Temperature Aging on Precipitation and Corrosion Behavior of a Ni-Cr-Mo-Based Hastelloy C276 Superalloy Zhang, Chi; Zhang, Liwen; Cui, Yan Journal of Materials Engineering and Performance, Vol. 29, Issue 3 https://doi.org/10.1007/s11665-020-04723-y	journal	March 2020
Effect of CrF 3 on the corrosion behaviour of Hastelloy-N and 316L stainless steel alloys in FLiNaK molten salt Yin, Huiqin; Qiu, Jie; Liu, Huajian Corrosion Science, Vol. 131 https://doi.org/10.1016/j.corsci.2017.12.008	journal	February 2018
Redox potential control in molten salt systems for corrosion mitigation Zhang, Jinsuo; Forsberg, Charles W.; Simpson, Michael F. Corrosion Science, Vol. 144 https://doi.org/10.1016/j.corsci.2018.08.035	journal	November 2018
Corrosion of Cr in molten salts with different fluoroacidity in the presence of CrF3 Liu, Yiyang; Song, Yulong; Ai, Hua Corrosion Science, Vol. 169 https://doi.org/10.1016/j.corsci.2020.108636	journal	June 2020
Investigation of impurity driven corrosion behavior in molten 2LiF-BeF2 salt Doniger, William H.; Falconer, Cody; Elbakhshwan, Mohamed Corrosion Science, Vol. 174 https://doi.org/10.1016/j.corsci.2020.108823	journal	September 2020
Corrosion behavior of GH3535 alloy in molten LiF–BeF2 salt Yang, Xinmei; Liu, Huajian; Chen, Bingchuan Corrosion Science, Vol. 199 https://doi.org/10.1016/j.corsci.2022.110168	journal	May 2022
Effect of oxide impurities on the corrosion behavior of structural materials in molten LiF-NaF-KF Sankar, Krishna Moorthi; Singh, Preet M. Corrosion Science, Vol. 206 https://doi.org/10.1016/j.corsci.2022.110473	journal	September 2022
Materials corrosion in molten LiF–NaF–KF salt Olson, Luke C.; Ambrosek, James W.; Sridharan, Kumar Journal of Fluorine Chemistry, Vol. 130, Issue 1 https://doi.org/10.1016/j.jfluchem.2008.05.008	journal	January 2009
Effect of moisture on corrosion of Ni-based alloys in molten alkali fluoride FLiNaK salt environments Ouyang, Fan-Yi; Chang, Chi-Hung; You, Bo-Chien Journal of Nuclear Materials, Vol. 437, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.02.021	journal	June 2013
Investigation on corrosion behavior of Ni-based alloys in molten fluoride salt using synchrotron radiation techniques Liu, Min; Zheng, Junyi; Lu, Yanling Journal of Nuclear Materials, Vol. 440, Issue 1-3, p. 124-128 https://doi.org/10.1016/j.jnucmat.2013.04.056	journal	September 2013
Alloys compatibility in molten salt fluorides Kurchatov Institute related experience Ignatiev, Victor; Surenkov, Alexandr Journal of Nuclear Materials, Vol. 441, Issue 1-3, p. 592-603 https://doi.org/10.1016/j.jnucmat.2013.05.007	journal	October 2013
Corrosion of 316 stainless steel in high temperature molten Li₂BeF₄ (FLiBe) salt Zheng, Guiqiu; Kelleher, Brian; Cao, Guoping Journal of Nuclear Materials, Vol. 461, p. 143-150 https://doi.org/10.1016/j.jnucmat.2015.03.004	journal	June 2015
Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten Li2BeF4(FLiBe) salt Zheng, Guiqiu; He, Lingfeng; Carpenter, David Journal of Nuclear Materials, Vol. 482 https://doi.org/10.1016/j.jnucmat.2016.10.023	journal	December 2016
Effect of Li metal addition on corrosion control of Hastelloy N and stainless steel 316H in molten LiF-NaF-KF Sankar, Krishna Moorthi; Singh, Preet M. Journal of Nuclear Materials, Vol. 555 https://doi.org/10.1016/j.jnucmat.2021.153098	journal	November 2021
Interaction of beryllium with 316H stainless steel in molten Li2BeF4 (FLiBe) Keiser, James R.; Singh, Preet M.; Lance, Michael J. Journal of Nuclear Materials, Vol. 565 https://doi.org/10.1016/j.jnucmat.2022.153698	journal	July 2022
The molten salt reactor (MSR) in generation IV: Overview and perspectives Serp, Jérôme; Allibert, Michel; Beneš, Ondřej Progress in Nuclear Energy, Vol. 77 https://doi.org/10.1016/j.pnucene.2014.02.014	journal	November 2014
Corrosion Behavior of Pre-Carburized Hastelloy N, Haynes 244, Haynes 230, and Incoloy 800H in Molten FLiNaK Chan, Kevin J.; Singh, Preet M. Nuclear Technology, Vol. 206, Issue 11 https://doi.org/10.1080/00295450.2020.1809311	journal	October 2020
High Performance Corrosion Resistance of Nickel-Based Alloys in Molten Salt Flibe Kondo, Masatoshi; Nagasaka, Takuya; Muroga, Takeo Fusion Science and Technology, Vol. 56, Issue 1 https://doi.org/10.13182/FST09-A8900	journal	July 2009
Molten-Salt Reactors—History, Status, and Potential Rosenthal, M. W.; Kasten, P. R.; Briggs, R. B. Nuclear Applications and Technology, Vol. 8, Issue 2 https://doi.org/10.13182/NT70-A28619	journal	February 1970
FLiBe Capsule Testing of 316H Pint, Bruce; Parker, Cory; Sulejmanovic, Dino https://doi.org/10.2172/1818669	report	August 2021
Preparation and Handling of Salt Mixtures for the Molten Salt Reactor Experiment Shaffer, J. H. https://doi.org/10.2172/4074869	report	January 1971
Alloy compatibility with LiF--BeF₂ salts containing ThF₄ and UF₄ Koger, J. W. https://doi.org/10.2172/4381831	report	December 1972
Compatibility studies of potential molten-salt breeder reactor materials in molten fluoride salts. [Inconel 601, Cr and Nb modifications of Hastelloy N] Keiser, J. R. https://doi.org/10.2172/7257097	report	May 1977
Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties Sohal, Manohar S.; Ebner, Matthias A.; Sabharwall, Piyush https://doi.org/10.2172/980801	report	March 2010
Intergranular corrosion of high temperature alloys in molten fluoride salts Olson, Luke; Sridharan, Kumar; Anderson, Mark Materials at High Temperatures, Vol. 27, Issue 2 https://doi.org/10.3184/096034010X12743509428336	journal	June 2010
Phase Instability in Hastelloy N Gehlbach, R. E.; McCoy, Jr., H. E. International Symposium on Structural Stability in Superalloys (1968) https://doi.org/10.7449/1968/Superalloys_1968_346_366	conference	January 1968

Similar Records

Corrosion of Candidate Materials in Molten FLiBe Salt for Fluoride-Salt-Cooled High-Temperature Reactor (FHR)

Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:22992148

Interaction of beryllium with 316H stainless steel in molten Li₂BeF₄(FLiBe)

Journal Article · Sun Apr 03 20:00:00 EDT 2022 · Journal of Nuclear Materials · OSTI ID:1866708

Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten Li₂BeF₄(FLiBe) salt

Journal Article · Tue Oct 11 20:00:00 EDT 2016 · Journal of Nuclear Materials · OSTI ID:1363778

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
FLiBe
alloy selection
corrosion
molten salt

Evaluation of Corrosion Behavior of Various Fe- and Ni-Based Alloys in Molten Li2BeF4 (FLiBe)

Citation Formats

References (26)

Similar Records

Related Subjects

Evaluation of Corrosion Behavior of Various Fe- and Ni-Based Alloys in Molten Li₂BeF₄ (FLiBe)