ODS FeCrAl alloys endure liquid metal flow at 600 °C resembling a fusion blanket environment
Scientists examined the chemical durability and anti-corrosion potential of oxide layers formed on oxide dispersion-strengthened (ODS) FeCrAl alloys in a liquid metal blanket environment
Institute of Science Tokyo
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Exceptional corrosion resistance of ODS FeCrAl oxide dispersion-strengthened alloy in advanced liquid blanket environment for fusion reactors.
view moreCredit: Masatoshi Kondo
Researchers explored protective coatings on advanced to resist corrosion in fusion reactors. They tested α-Al2O3 oxide layers on ODS alloys in a high-temperature, flowing lithium-lead environment. Even bare ODS alloys formed a durable γ-LiAlO2 layer in situ, which suppressed further corrosion. The layers exhibited strong adhesion under mechanical stress, making these findings crucial for improving material durability in fusion reactors and high-temperature energy systems.
Fusion reactors, a promising source of sustainable energy, require advanced materials that can withstand extreme temperatures and corrosive environments created by liquid metal coolants such as lithium and lithium-lead (LiPb) alloy. These coolants are essential in fusion reactors to extract heat and breed tritium, but their corrosive nature threatens the integrity of the structural materials used. LiPb is particularly aggressive, as it has a high concentration of lithium, which reacts with structural materials, causing corrosion and material degradation over time.
ODS FeCrAl alloys, known for their excellent high-temperature strength and corrosion resistance, have been proposed as promising candidates for fusion reactors and other high-temperature applications like concentrated solar power systems. These alloys rely on the formation of protective oxide layers, such as α-Al2O3, which offers stability and durability under high temperatures. However, in a liquid LiPb environment, the chemical interactions between the alloy and the coolant raise concerns about the stability and longevity of these protective layers.
In this view, a team of researchers from the Institute of Science Tokyo (Science Tokyo), led by Associate Professor Masatoshi Kondo in collaboration with Yokohama National University, Nippon Nuclear Fuel Development and Department of Research, National Institute for Fusion Science, conducted corrosion tests on oxide layers formed on ODS FeCrAl alloys under prolonged exposure to flowing liquid LiPb at elevated temperatures. Their study was published in the journal Corrosion Science on September 17, 2024.
The researchers carried out corrosion tests using two types of ODS FeCrAl alloys: SP10 and NF12. The tests were performed under both static and stirred-flow conditions at 873 K to simulate realistic scenarios in fusion reactor coolant systems. They employed advanced metallurgical analysis techniques, including scanning transmission electron microscopy coupled with electron energy loss spectroscopy, to investigate the composition and microstructure of the protective oxide layers formed on the alloy surfaces.
They found that the pre-formed α-Al2O3 layer effectively suppressed initial corrosion but partially transformed into α-/γ-LiAlO2 due to the adsorption of lithium. Interestingly, even without pre-oxidation, the ODS alloys in situ developed a durable γ-LiAlO2 layer, which served as a self-forming protective barrier. Microstructural analysis using advanced electron microscopy revealed the penetration of lithium into the α-Al2O3 layer, leading to the chemical transformation. Despite this, both α-Al2O3 and γ-LiAlO2 layers demonstrated strong resistance to exfoliation. Micro-scratch tests confirmed that these layers adhered strongly to the alloy surface, with minimal degradation, even under high thermal stresses caused by LiPb solidification.
“The lithium-aluminum oxide layer’s durability shows that these alloys could last longer in high-temperature, high-stress settings. This layer serves as a sustainable shield that continues protecting reactor components even after initial wear,” explains Kondo.
As nuclear technology evolves, these findings bring us one step closer to developing reactors that can run safely for extended duration, making sustainable energy sources more feasible. "Our findings show that ODS FeCrAl alloys, with their ability to form durable protective layers, could play a vital role in the future of fusion reactors and other high-temperature power systems,” says Kondo, highlighting the impact of the research study.
About Institute of Science Tokyo (Science Tokyo)
Institute of Science Tokyo (Science Tokyo) was established on October 1, 2024, following the merger between Tokyo Medical and Dental University (TMDU) and Tokyo Institute of Technology (Tokyo Tech), with the mission of “Advancing science and human wellbeing to create value for and with society.”
Exploring the corrosion resistance of ODS FeCrAl alloys and the role of protective α-Al₂O₃ and γ-LiAlO₂ layers in liquid LiPb environments
Corrosion test of ODS FeCrAl alloys in liquid LiPb at 873K (left and center) and STEM cross-sectional observation on the surface of pre-oxidized alloy after exposure to liquid LiPb flow (right)
Journal
Corrosion Science
Method of Research
Experimental study
Subject of Research
Not applicable
Article Title
Chemical and structural durability of α-Al2O3 and γ-LiAlO2 layers formed on ODS FeCrAl alloys in liquid lithium lead stirred flow
Article Publication Date
27-Sep-2024
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