Corrosion characteristics of Mo and TZM alloy for plasma facing components in molten lithium at 623&nbsp;K

Meng, X. C.; Li, L.; Li, C. L.; Andruczyk, D.; Tritz, K.; Maingi, R.; Huang, M.; Zhang, D. H.; Xu, W.; Sun, Z.; Zuo, G. Z.; Hu, J. S.

doi:10.1016/j.corsci.2022.110202

Corrosion characteristics of Mo and TZM alloy for plasma facing components in molten lithium at 623 K

Journal Article · Fri Mar 04 00:00:00 EST 2022 · Corrosion Science

DOI:https://doi.org/10.1016/j.corsci.2022.110202· OSTI ID:1890166

Meng, X. C. ^[1]; Li, L. ^[2]; Li, C. L. ^[2]; Andruczyk, D. ^[3]; Tritz, K. ^[4]; Maingi, R. ^[5]; Huang, M. ^[2]; Zhang, D. H. ^[2]; Xu, W. ^[1]; Sun, Z. ^[6]; Zuo, G. Z. ^[7]; Hu, J. S. ^[1]

Hefei Comprehensive National Science Center (China); Chinese Academy of Sciences (CAS), Hefei (China)
Chinese Academy of Sciences (CAS), Hefei (China)
Univ. of Illinois at Urbana-Champaign, IL (United States)
Johns Hopkins Univ., Baltimore, MD (United States)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Chinese Academy of Sciences (CAS), Hefei (China); Univ. of Illinois at Urbana-Champaign, IL (United States)
Hefei Comprehensive National Science Center (China)

Here, in this study, the corrosion behaviours of molybdenum (Mo) and a Mo-based alloy (TZM) were investigated using a static immersion corrosion technique. Weight loss, surface microstructure, and corrosion depth of Mo and the TZM alloy were correlated with elements. The compatibility of Mo and the TZM alloy in static liquid Li was suitable. Mo demonstrated uniform corrosion with a homogenous dissolution of free C and Mo, and TZM alloy exhibited a nonuniform corrosion behaviour with a preferential grain boundary attack caused by the selective dissolution of free C, Ti, and Zr. When the surface oxidation layer of the samples was consumed, free C from Mo and TZM diffused into molten Li to form Li₂C₂ and then was captured by Zr, Ti, and Mo to form thermodynamically stable carbides, which resulted in the enrichment of the C layer near the sample surfaces. In addition, Ti and Zr acted as N-trappers in liquid Li; the formation of Zr and Ti nitrides resulted in the enrichment of N, Ti, and Zr elements on the surface and led to TZM corrosion increase. Thus, Zr and Ti depletion, pitting, and grain boundary corrosion were problematic for TZM under long-term exposure to liquid Li. Reducing the content of free C and nonmetallic N and increasing the amount of Ti and Zr carbides on the surface of and inside the raw TZM alloy helped improve the corrosion resistance of TZM in liquid Li.

View Accepted Manuscript (DOE)

Research Organization:: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

Sponsoring Organization:: Hefei Comprehensive National Science Center; Hefei Science Center CAS; National Key Research and Development Program of China; National Nature Science Foundation of China (NSFC); USDOE

Grant/Contract Number:: AC02-09CH11466

OSTI ID:: 1890166

Journal Information:: Corrosion Science, Journal Name: Corrosion Science Vol. 200; ISSN 0010-938X

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (32)

Air contamination effects on the compatibility of liquid lithium with molybdenum; TZM, niobium, stainless steels, nickel and hastelloy N in stainless-steel vessels at 600°c Katsuta, Hiroji; Furukawa, Kazuo Journal of Nuclear Materials, Vol. 71, Issue 1 https://doi.org/10.1016/0022-3115(77)90192-1	journal	December 1977
Comparison of chemical reactions in liquid lithium with those in liquid sodium Pulham, R. J.; Hubberstey, P. Journal of Nuclear Materials, Vol. 115, Issue 2-3 https://doi.org/10.1016/0022-3115(83)90315-X	journal	April 1983
Influence of nonmetallic elements on the compatibility of structural materials with liquid alkali metals Natesan, K. Journal of Nuclear Materials, Vol. 115, Issue 2-3 https://doi.org/10.1016/0022-3115(83)90316-1	journal	April 1983
Vacuum pumping requirement considerations for future fusion devices Langley, R. A.; LaMarche, Paul Journal of Nuclear Materials, Vol. 200, Issue 3 https://doi.org/10.1016/0022-3115(93)90303-G	journal	May 1993
Numerical and experimental determination of metallic solubilities in liquid lithium, lithium-containing nonmetallic impurities, lead and lead-lithium eutectic Lyublinski, I. E.; Evtikhin, V. A.; Pankratov, V. Yu. Journal of Nuclear Materials, Vol. 224, Issue 3 https://doi.org/10.1016/0022-3115(95)00076-3	journal	September 1995
Development of insulating coatings for liquid metal blankets Malang, S. Fusion Engineering and Design, Vol. 27, Issue 1-2 https://doi.org/10.1016/0920-3796(94)00322-X	journal	March 1995
Compatibility of materials in fusion first wall and blanket structures cooled by liquid metals Flament, T.; Tortorelli, P.; Coen, V. Journal of Nuclear Materials, Vol. 191-194 https://doi.org/10.1016/S0022-3115(09)80020-2	journal	September 1992
Compatibility of yttria (Y2O3) with liquid lithium Terai, T.; Yoneoka, T.; Tanaka, H. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/S0022-3115(96)00257-7	journal	October 1996
Corrosion behavior of Mo–Re based alloys in liquid Li Saito, Jun-ichi; Morinaga, Masahiko; Kano, Shigeki Journal of Nuclear Materials, Vol. 264, Issue 1-2 https://doi.org/10.1016/S0022-3115(98)00459-0	journal	January 1999
Alloying effects on the corrosion behavior of binary Nb-based and Mo-based alloys in liquid Li Saito, Jun-ichi; Inoue, Satoshi; Kano, Shigeki Journal of Nuclear Materials, Vol. 264, Issue 1-2 https://doi.org/10.1016/S0022-3115(98)00460-7	journal	January 1999
Range of blanket concepts from near term solutions to advanced concepts Malang, S.; Raffray, A. R.; Sagara, A. Fusion Engineering and Design, Vol. 61-62 https://doi.org/10.1016/S0920-3796(02)00233-8	journal	November 2002
The ARIES-RS power core—recent development in Li/V designs Sze, Dai-Kai; Billone, Michael C.; Hua, Thanh Q. Fusion Engineering and Design, Vol. 41, Issue 1-4 https://doi.org/10.1016/S0920-3796(97)00144-0	journal	September 1998
Review of FTU results with the liquid lithium limiter Mazzitelli, G.; Apicella, M. L.; Ridolfini, V. Pericoli Fusion Engineering and Design, Vol. 85, Issue 6 https://doi.org/10.1016/j.fusengdes.2010.08.038	journal	November 2010
Wetting properties of liquid lithium on select fusion relevant surfaces Fiflis, P.; Press, A.; Xu, W. Fusion Engineering and Design, Vol. 89, Issue 12 https://doi.org/10.1016/j.fusengdes.2014.03.060	journal	December 2014
First experiments with lithium limiter on FTU Apicella, M. L.; Mazzitelli, G.; Pericoli Ridolfini, V. Journal of Nuclear Materials, Vol. 363-365 https://doi.org/10.1016/j.jnucmat.2007.01.237	journal	June 2007
Effect of chemical potential of carbon on phase transformation and corrosion of JLF-1 steel in a static lithium Xu, Qi; Kondo, Masatoshi; Nagasaka, Takuya Journal of Nuclear Materials, Vol. 394, Issue 1 https://doi.org/10.1016/j.jnucmat.2009.08.005	journal	October 2009
First results of lithium experiments on EAST and HT-7 Zuo, G. Z.; Hu, J. S.; Li, J. G. Journal of Nuclear Materials, Vol. 415, Issue 1 https://doi.org/10.1016/j.jnucmat.2010.08.052	journal	August 2011
Comparison of long term fuel retention in JET between carbon and the ITER-Like Wall Loarer, T.; Brezinsek, S.; Philipps, V. Journal of Nuclear Materials, Vol. 438 https://doi.org/10.1016/j.jnucmat.2013.01.017	journal	July 2013
Corrosion behavior of 9Cr-ODS steel in stagnant liquid lithium and lead–lithium at 873K Li, Yanfen; Abe, Hiroaki; Nagasaka, Takuya Journal of Nuclear Materials, Vol. 443, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.07.026	journal	November 2013
Study of the corrosion behaviors of 304 austenite stainless steel specimens exposed to static liquid lithium at 600 K Meng, Xiancai; Zuo, Guizhong; Ren, Jun Journal of Nuclear Materials, Vol. 480 https://doi.org/10.1016/j.jnucmat.2016.07.061	journal	November 2016
Compatibility between high-flux helium plasma irradiated molybdenum and liquid lithium He, Pingni; Zhang, Zhiyan; Xia, Wenxin Journal of Nuclear Materials, Vol. 509 https://doi.org/10.1016/j.jnucmat.2018.04.038	journal	October 2018
Study of the corrosion characteristics of 304 and 316L stainless steel in the static liquid lithium Zhang, D. H.; Meng, X. C.; Zuo, G. Z. Journal of Nuclear Materials, Vol. 553 https://doi.org/10.1016/j.jnucmat.2021.153032	journal	September 2021
A long-pulse high-confinement plasma regime in the Experimental Advanced Superconducting Tokamak Li, J.; Guo, H. Y.; Wan, B. N. Nature Physics, Vol. 9, Issue 12 https://doi.org/10.1038/nphys2795	journal	November 2013
Methods and preliminary measurement results of liquid Li wettability Zuo, G. Z.; Hu, J. S.; Ren, J. Review of Scientific Instruments, Vol. 85, Issue 2 https://doi.org/10.1063/1.4865118	journal	February 2014
Results from a new flowing liquid Li limiter with TZM substrate during high confinement plasmas in the EAST device Zuo, G. Z.; Li, C. L.; Maingi, R. Physics of Plasmas, Vol. 27, Issue 5 https://doi.org/10.1063/1.5143179	journal	May 2020
Application of lithium in systems of fusion reactors. 1. Physical and chemical properties of lithium Lyublinski, I. E.; Vertkov, A. V.; Evtikhin, V. A. Plasma Devices and Operations, Vol. 17, Issue 1 https://doi.org/10.1080/10519990802703277	journal	March 2009
Recent liquid lithium limiter experiments in CDX-U Majeski, R.; Jardin, S.; Kaita, R. Nuclear Fusion, Vol. 45, Issue 6 https://doi.org/10.1088/0029-5515/45/6/014	journal	May 2005
Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas Jaworski, M. A.; Abrams, T.; Allain, J. P. Nuclear Fusion, Vol. 53, Issue 8 https://doi.org/10.1088/0029-5515/53/8/083032	journal	July 2013
First results of the use of a continuously flowing lithium limiter in high performance discharges in the EAST device Hu, J. S.; Zuo, G. Z.; Ren, J. Nuclear Fusion, Vol. 56, Issue 4 https://doi.org/10.1088/0029-5515/56/4/046011	journal	March 2016
Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices Mirnov, S. V.; Azizov, E. A.; Evtikhin, V. A. Plasma Physics and Controlled Fusion, Vol. 48, Issue 6 https://doi.org/10.1088/0741-3335/48/6/009	journal	May 2006
Comparison of various wall conditionings on the reduction of H content and particle recycling in EAST Zuo, G. Z.; Hu, J. S.; Zhen, S. Plasma Physics and Controlled Fusion, Vol. 54, Issue 1 https://doi.org/10.1088/0741-3335/54/1/015014	journal	December 2011
New Steady-State Quiescent High-Confinement Plasma in an Experimental Advanced Superconducting Tokamak Hu, J. S.; Sun, Z.; Guo, H. Y. Physical Review Letters, Vol. 114, Issue 5 https://doi.org/10.1103/PhysRevLett.114.055001	journal	February 2015

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