Evaluation of the interaction between SiC, pre-oxidized FeCrAlMo with aluminized and pre-oxidized Fe-8Cr-2W in flowing PbLi

Romedenne, Marie; Zhang, Ying; Su, Yi-Feng; Pint, Bruce

doi:10.1016/j.jnucmat.2023.154465

Title: Evaluation of the interaction between SiC, pre-oxidized FeCrAlMo with aluminized and pre-oxidized Fe-8Cr-2W in flowing PbLi

Journal Article · 17 April 2023 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2023.154465 · OSTI ID:1972580

^[1]; Zhang, Ying ^[2]; Su, Yi-Feng ^[1];

^[1]

Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division
Tennessee Technological University, Cookeville, TN (United States)

We report dissimilar materials interactions are a major concern when liquid metals are used as a working fluid. To simulate a dual-coolant PbLi blanket, chemical vapor deposited (CVD) SiC, pre-oxidized FeCrAlMo (APMT) and pre-oxidized aluminized coating on Fe-8Cr-2 W (F82H) specimens were exposed to flowing commercial Pb-17at.%Li with a peak temperature of 650 °C in a pre-oxidized APMT thermal convection loop (TCL) for 1000 h. Similar to prior results in static PbLi, the coated F82H showed small mass changes and limited degradation of room-temperature tensile properties. After exposure, the α-Al₂O₃ on the surface coated F82H reacted with the PbLi to form LiAlO₂. However, no significant Al coating loss or interdiffusion was observed. Mass transfer was observed between the APMT, TCL and the SiC specimens. Fe, Cr and Ni were dissolved into the molten flowing PbLi and transported through the TCL to react with the SiC specimens. Compared to a prior experiment with a majority of bare FeCrAl specimens that were exposed in a TCL with a peak temperature of 700 °C for 1000 h, the SiC reaction was reduced to only a few microns of carbides and silicides. Oxygen dissolved in the molten PbLi sustained the formation of an Al₂O₃ scale on the surface of the coating and induced the formation of a thin surface SiO₂ layer on the surface of the SiC.

View Accepted Manuscript (DOE)

Cite

Export

Save

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

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1972580

Alternate ID(s):: OSTI ID: 1971551

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: - Vol. 581; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (61)

Long-term corrosion behavior of EUROFER RAFM steel in static liquid Pb-16Li at 550 °C Bassini, S.; Cuzzola, V.; Antonelli, A. Fusion Engineering and Design, Vol. 160 https://doi.org/10.1016/j.fusengdes.2020.111829	journal	November 2020
Compatibility of an FeCrAl alloy with flowing Pb-Li in a thermal convection loop Pawel, Steven J.; Unocic, Kinga A. Journal of Nuclear Materials, Vol. 492 https://doi.org/10.1016/j.jnucmat.2017.04.048	journal	August 2017
Comparison of corrosion behavior of bare and hot-dip coated EUROFER steel in flowing Pb–17Li Konys, J.; Krauss, W.; Voss, Z. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.205	journal	August 2007
Corrosion behavior of EUROFER steel in flowing eutectic Pb–17Li alloy Konys, J.; Krauss, W.; Voss, Z. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.302	journal	August 2004
Corrosion behaviour of Al based tritium permeation barriers in flowing Pb–17Li Glasbrenner, H.; Konys, J.; Voss, Z. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)01124-8	journal	December 2002
Compatibility of reduced activation ferritic martensitic steel JLF-1 with liquid metals Li and Pb–17Li Kondo, Masatoshi; Takahashi, Minoru; Tanaka, Teruya Fusion Engineering and Design, Vol. 87, Issue 10 https://doi.org/10.1016/j.fusengdes.2011.12.013	journal	October 2012
Development of a direct insulation layer for a self-cooled liquid metal fusion reactor blanket Borgstedt, H. Fusion Engineering and Design, Vol. 27, Issue 1-2 https://doi.org/10.1016/0920-3796(94)00062-C	journal	March 1995
Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review Bhattacharya, Arunodaya; Zinkle, Steven J.; Henry, Jean Journal of Physics: Energy, Vol. 4, Issue 3 https://doi.org/10.1088/2515-7655/ac6f7f	journal	July 2022
Investigations on wear and liquid metal corrosion behavior of aluminized IN-RAFMS Paul, Bhaskar; Raju, K.; Vadsola, M. Fusion Engineering and Design, Vol. 128 https://doi.org/10.1016/j.fusengdes.2018.02.030	journal	March 2018
Alloying of aluminum and its influence on the properties of aluminide coatings: oxidation behavior and the chemical stability in Pb17Li Glasbrenner, H.; Peric, Z.; Borgstedt, H. U. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/S0022-3115(96)00183-3	journal	October 1996
Dual-coolant lead–lithium (DCLL) blanket status and R&D needs Smolentsev, Sergey; Morley, Neil B.; Abdou, Mohamed A. Fusion Engineering and Design, Vol. 100 https://doi.org/10.1016/j.fusengdes.2014.12.031	journal	November 2015
Corrosion of an India produced RAFM steel in flowing lead-lithium eutectic Chakraborty, Poulami; Kain, Vivekanand; Tewari, Raghvendra Fusion Engineering and Design, Vol. 125 https://doi.org/10.1016/j.fusengdes.2017.08.010	journal	December 2017
Corrosion testing of steel X 18 CrMoVNb 12 1 (1.4914) in A Pb-17Li pumped loop Borgstedt, H. U.; Drechsler, G.; Frees, G. Journal of Nuclear Materials, Vol. 155-157 https://doi.org/10.1016/0022-3115(88)90404-7	journal	July 1988
Performance of Al-rich oxidation resistant coatings for Fe-base alloys Pint, B. A.; Zhang, Y. Materials and Corrosion, Vol. 62, Issue 6 https://doi.org/10.1002/maco.201005884	journal	December 2010
Compatibility of SiC with ODS FeCrAl in flowing Pb-Li at 600°–700 °C Pint, B. A.; Jun, J.; Romedenne, M. Fusion Engineering and Design, Vol. 166 https://doi.org/10.1016/j.fusengdes.2021.112389	journal	May 2021
Liquid metal compatibility issues for test blanket modules Pint, B. A.; Moser, J. L.; Tortorelli, P. F. Fusion Engineering and Design, Vol. 81, Issue 8-14 https://doi.org/10.1016/j.fusengdes.2005.07.010	journal	February 2006
Corrosion of austenitic and martensitic stainless steels in flowing Pb17Li alloy Sannier, J.; Broc, M.; Flament, T. Fusion Engineering and Design, Vol. 14, Issue 3-4 https://doi.org/10.1016/0920-3796(91)90013-G	journal	April 1991
Corrosion of ferritic–martensitic steels in the eutectic Pb–17Li Glasbrenner, H.; Konys, J.; Röhrig, H. D. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00322-6	journal	December 2000
R&D of DRAGON Series Lithium-Lead Loops for Material and Blanket Technology Testing Wu, Yican; Huang, Qunying; Zhu, Zhiqiang Fusion Science and Technology, Vol. 62, Issue 1 https://doi.org/10.13182/FST12-A14146	journal	August 2012
Short-term corrosion behavior of Indian RAFM steel in liquid Pb-Li: Corrosion mechanism and effect of alloying elements Chakraborty, Poulami; Singh, Vishal; Bysakh, Sandip Journal of Nuclear Materials, Vol. 520 https://doi.org/10.1016/j.jnucmat.2019.04.018	journal	July 2019
Compatibility of FeCrAlMo with flowing PbLi at 500°-650 °C Jun, Jiheon; Unocic, Kinga A.; Lance, Michael J. Journal of Nuclear Materials, Vol. 528 https://doi.org/10.1016/j.jnucmat.2019.151847	journal	January 2020
Materials-engineering challenges for the fusion core and lifetime components of the fusion nuclear science facility Rowcliffe, A. F.; Kessel, C. E.; Katoh, Y. Nuclear Materials and Energy, Vol. 16 https://doi.org/10.1016/j.nme.2018.05.025	journal	August 2018
Alloying and coating strategies for improved Pb–Li compatibility in DEMO-type fusion reactors Unocic, K. A.; Pint, B. A. Journal of Nuclear Materials, Vol. 455, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.06.058	journal	December 2014
The influence of alloying elements on the development and maintenance of protective scales Stott, F. H.; Wood, G. C.; Stringer, J. Oxidation of Metals, Vol. 44, Issue 1-2 https://doi.org/10.1007/BF01046725	journal	August 1995
Corrosion of ferrous alloys exposed to thermally convective Pb-17 at% Li Tortorelli, P. F.; DeVan, J. H. Journal of Nuclear Materials, Vol. 141-143 https://doi.org/10.1016/0022-3115(86)90059-0	journal	November 1986
Pre-Oxidation to Improve Liquid Metal Compatibility Pint, Bruce A.; Jun, Jiheon Oxidation of Metals, Vol. 96, Issue 3-4 https://doi.org/10.1007/s11085-021-10057-4	journal	July 2021
Deposition behavior of ferrous alloys in molten lead-lithium Tortorelli, P. F. Fusion Engineering and Design, Vol. 14, Issue 3-4 https://doi.org/10.1016/0920-3796(91)90017-K	journal	April 1991
The Stability of Tritium Permeation Barriers and the Self-Healing Capability of Aluminide Coatings in Liquid Pb-17Li Hubberstey, Peter; Sample, Tony; Terlain, Anne Fusion Technology, Vol. 28, Issue 3P2 https://doi.org/10.13182/FST95-A30571	journal	October 1995
Corrosion and precipitation effects in a forced-convection Pb–15.7Li loop Konys, J.; Krauss, W. Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.04.016	journal	November 2013
Progress on DCLL Blanket Concept Wong, C. P. C.; Abdou, M.; Katoh, Y. Fusion Science and Technology, Vol. 64, Issue 3 https://doi.org/10.13182/FST13-A19161	journal	September 2013
Interdiffusional degradation of oxidation-resistant aluminide coatings on Fe-base alloys Zhang, Y.; Liu, A. P.; Pint, B. A. Materials and Corrosion, Vol. 58, Issue 10 https://doi.org/10.1002/maco.200704057	journal	October 2007
Material compatibility with isothermal Pb–Li Pint, Bruce A.; Walker, Larry R.; Unocic, Kinga A. Materials at High Temperatures, Vol. 29, Issue 2 https://doi.org/10.3184/096034012X13334529777329	journal	June 2012
Effects of Specimen Thickness in Tensile Tests on Elongation and Deformation Energy for Industrially Pure Iron Takeda, Yuji; Kiattisaksri, Chatcharit; Aramaki, Masatoshi ISIJ International, Vol. 57, Issue 6 https://doi.org/10.2355/isijinternational.ISIJINT-2016-555	journal	January 2017
Material properties of the F82H melted in an electric arc furnace Sakasegawa, Hideo; Tanigawa, Hiroyasu; Kano, Sho Fusion Engineering and Design, Vol. 98-99 https://doi.org/10.1016/j.fusengdes.2015.06.103	journal	October 2015
Development of the Lead Lithium (DCLL) Blanket Concept Malang, S.; Tillack, M.; Wong, C. P. C. Fusion Science and Technology, Vol. 60, Issue 1 https://doi.org/10.13182/FST10-212	journal	July 2011
Effect of nitrogen on the formation and oxidation behavior of iron aluminide coatings Zhang, Y.; Pint, B. A.; Cooley, K. M. Surface and Coatings Technology, Vol. 200, Issue 5-6 https://doi.org/10.1016/j.surfcoat.2005.07.081	journal	November 2005
Liquid-Metal Corrosion Chopra, Omesh K.; Smith, Dale L.; Tortorelli, Peter F. Fusion Technology, Vol. 8, Issue 2P1 https://doi.org/10.13182/FST85-A24572	journal	September 1985
Corrosion analysis of CLAM steel in flowing liquid LiPb at 480°C Chen, Yaping; Huang, Qunying; Gao, Sheng Fusion Engineering and Design, Vol. 85, Issue 10-12 https://doi.org/10.1016/j.fusengdes.2010.06.021	journal	December 2010
Aluminum-Based Barrier Development for Nuclear Fusion Applications Konys, J.; Krauss, W.; Holstein, N. Corrosion, Vol. 67, Issue 2 https://doi.org/10.5006/1.3553931	journal	February 2011
Compatibility behavior of EUROFER steel in flowing Pb–17Li Konys, J.; Krauss, W.; Novotny, J. Journal of Nuclear Materials, Vol. 386-388 https://doi.org/10.1016/j.jnucmat.2008.12.271	journal	April 2009
Transformation of Al2O3 to LiAlO2 in Pb–17Li at 800°C Pint, B. A.; More, K. L. Journal of Nuclear Materials, Vol. 376, Issue 1 https://doi.org/10.1016/j.jnucmat.2007.12.010	journal	May 2008
Pb–Li compatibility issues for DEMO Pint, B. A.; Unocic, K. A. Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.02.007	journal	November 2013
Development of ODS FeCrAl for Compatibility in Fusion and Fission Energy Applications Pint, B. A.; Dryepondt, S.; Unocic, K. A. JOM, Vol. 66, Issue 12 https://doi.org/10.1007/s11837-014-1200-z	journal	November 2014
The Fusion Nuclear Science Facility, the Critical Step in the Pathway to Fusion Energy Kessel, C. E.; Blanchard, J. P.; Davis, A. Fusion Science and Technology, Vol. 68, Issue 2 https://doi.org/10.13182/FST14-953	journal	September 2015
Tensile properties of F82H steel after aging at 400–650 °C for 100,000 h Nagasaka, Takuya; Sakasegawa, Hideo; Tanigawa, Hiroyasu Fusion Engineering and Design, Vol. 98-99 https://doi.org/10.1016/j.fusengdes.2015.06.190	journal	October 2015
Corrosion and mechanical properties of the martensitic steel X18CrMoVNb 12 1 in flowing Pb17Li Borgstedt, H. U.; Frees, G.; Grundmann, M. Fusion Engineering and Design, Vol. 14, Issue 3-4 https://doi.org/10.1016/0920-3796(91)90016-J	journal	April 1991
Evaluation of iron-aluminide CVD coatings for high temperature corrosion protection Pint, B. A.; Zhang, Y.; Tortorelli, P. F. Materials at High Temperatures, Vol. 18, Issue 3 https://doi.org/10.1179/mht.2001.021	journal	January 2001
The effect of coatings on the compatibility of Fe–Cr steels with Pb–Li Pint, B. A. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.286	journal	October 2011
Effect of magnetic field on corrosion behavior of Indian reduced activation ferritic/martensitic steel in liquid Pb–Li Chakraborty, P.; Singh, V.; Trivedi, P. Nuclear Fusion, Vol. 59, Issue 12 https://doi.org/10.1088/1741-4326/ab388c	journal	September 2019
Mechanical and corrosion behaviour of EUROFER 97 steel exposed to Pb–17Li Benamati, G.; Fazio, C.; Ricapito, I. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)00990-X	journal	December 2002
Comparison of corrosion behavior of EUROFER and CLAM steels in flowing Pb–15.7Li Konys, J.; Krauss, W.; Zhu, Z. Journal of Nuclear Materials, Vol. 455, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.07.045	journal	December 2014
Corrosion experiments on IN-RAFM steel in flowing lead-lithium for Indian LLCB TBM Atchutuni, Sarada Sree; Saraswat, Abhishek; Sasmal, Chandra Sekhar Fusion Engineering and Design, Vol. 132 https://doi.org/10.1016/j.fusengdes.2018.05.020	journal	July 2018
Integrated Liquid Metal Flowing First Wall and Open-Surface Divertor for Fusion Nuclear Science Facility: Concept, Design, and Analysis Smolentsev, Sergey; Rognlien, Thomas; Tillack, Mark Fusion Science and Technology, Vol. 75, Issue 8 https://doi.org/10.1080/15361055.2019.1610649	journal	May 2019
Formation and oxidation performance of low-temperature pack aluminide coatings on ferritic–martensitic steels Bates, B. L.; Wang, Y. Q.; Zhang, Y. Surface and Coatings Technology, Vol. 204, Issue 6-7 https://doi.org/10.1016/j.surfcoat.2009.09.063	journal	December 2009
Compatibility of materials for fusion reactors with Pb–17Li Barbier, F.; Deloffre, Ph.; Terlain, A. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)00987-X	journal	December 2002
Compatibility of FeCrAlMo in Flowing Pb-Li at 600°C to 700°C Pint, B. A.; Jun, J.; Cakmak, E. Fusion Science and Technology https://doi.org/10.1080/15361055.2021.1898305	journal	August 2021
Effect of oxygen on the corrosion behavior of SS316L in a buoyancy driven Pb–17Li loop Chakraborty, P.; Fotedar, R. K.; Krishnamurthy, N. Journal of Nuclear Materials, Vol. 432, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.07.031	journal	January 2013
Deuterium permeation through multi-layer ceramic coatings under liquid lithium-lead exposure condition Akahoshi, Erika; Matsunaga, Moeki; Kimura, Keisuke Corrosion Science, Vol. 189 https://doi.org/10.1016/j.corsci.2021.109583	journal	August 2021
Compatibility of materials for use in liquid-metal blankets of fusion reactors Chopra, Omesh K.; Tortorelli, Peter F. Journal of Nuclear Materials, Vol. 123, Issue 1-3 https://doi.org/10.1016/0022-3115(84)90241-1	journal	May 1984
Hydrogen permeation rate reduction by post-oxidation of aluminide coatings on DIN 1.4914 martensitic steel (MANET) Perujo, A.; Serra, E.; Kolbe, H. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/0022-3115(95)00189-1	journal	October 1996
Metallurgical study on corrosion of RAFM steel JLF-1 in Pb-Li alloys with various Li concentrations Kondo, Masatoshi; Ishii, Masaomi; Hishinuma, Yoshimitsu Fusion Engineering and Design, Vol. 125 https://doi.org/10.1016/j.fusengdes.2017.04.058	journal	December 2017

Similar Records

Compatibility of SiC with ODS FeCrAl in flowing Pb-Li at 600° - 700°C

Journal Article · 2021 · Fusion Engineering and Design · OSTI ID:1783033

Pint, Bruce; Jun, Jiheon; Romedenne, Marie

Compatibility of FeCrAlMo in Flowing Pb-Li at 600°C to 700°C

Journal Article · 2021 · Fusion Science and Technology · OSTI ID:1833981

Pint, Bruce; Jun, Jiheon; Cakmak, Ercan; +3 more

Compatibility of FeCrAlMo with flowing PbLi at 500°-650°C

Journal Article · 2019 · Journal of Nuclear Materials · OSTI ID:1607091

Jun, Jiheon; Unocic, Kinga A.; Lance, Michael J.; +2 more

Related Subjects

36 MATERIALS SCIENCE
lead-lithium
corrosion
coatings
RAFM steel
sic

Title: Evaluation of the interaction between SiC, pre-oxidized FeCrAlMo with aluminized and pre-oxidized Fe-8Cr-2W in flowing PbLi

Citation Formats

References (61)

Similar Records

Related Subjects