Corrosion behavior in liquid lead of a novel FCC non-equiatomic high-entropy alloy capable of forming an alumina protective oxide scaleShow others and affiliations
2026 (English)In: Corrosion Science, ISSN 0010-938X, E-ISSN 1879-0496, Vol. 262, article id 113651Article in journal (Refereed) Published
Abstract [en]
This study presents the design, characterization and evaluation of corrosion resistance and mechanical integrity of a novel Co-free face-centered cubic (FCC) non-equiatomic Fe33.5Ni43.5Cr11Mn6Al6 High-Entropy Alloy (HEA) for structural applications in Generation IV Lead-cooled Fast Reactors (LFRs). The alloy was engineered to form a protective Al-rich oxide scale. Liquid Metal Corrosion (LMC) tests were conducted in stagnant liquid Pb at 550 °C and 650 °C for 1150 h, under controlled oxygen concentrations ranging from 7.4·10−6 to 8.6·10−6 wt% at 550 °C, and from 4.5·10−5 to 3.6·10−4 wt% at 650 °C. Liquid Metal Embrittlement (LME) susceptibility was assessed via Slow Strain Rate Testing (SSRT) between 350 °C to 600 °C. LMC test results revealed bilayer oxide scale formation, with an inner amorphous alumina scale acting as an effective diffusion barrier and a complex outer Mn(Al,Fe,Cr)2O4 spinel prone to detachment. The alloy exhibited self-healing behavior, regenerating protective oxides in areas where Pb penetration took place. No signs of LME were observed up to 400 °C, with embrittlement onset occurring at 500 °C. Despite its high Ni content, which is typically detrimental in liquid Pb due to the its high solubility at elevated temperatures, leading to accelerated degradation, combined with low oxygen availability that hinders protective oxide formation and microstructural heterogeneities (oxide inclusions and local grain size variations), the alloy maintained excellent corrosion resistance and mechanical integrity. These results underscore the exceptional corrosion resistance of this non-equiatomic Fe33.5Ni43.5Cr11Mn6Al6 HEA, positioning it as a highly promising candidate for high-temperature nuclear applications in Pb-cooled systems.
Place, publisher, year, edition, pages
Elsevier Ltd , 2026. Vol. 262, article id 113651
Keywords [en]
High-entropy alloy, Lead-cooled fast reactor, Liquid metal corrosion, Liquid metal embrittlement, Slow strain rate testing, Stagnant lead
National Category
Metallurgy and Metallic Materials
Identifiers
URN: urn:nbn:se:kth:diva-376870DOI: 10.1016/j.corsci.2026.113651ISI: 001678773400001Scopus ID: 2-s2.0-105028635641OAI: oai:DiVA.org:kth-376870DiVA, id: diva2:2040130
Note
QC 20260219
2026-02-192026-02-192026-02-19Bibliographically approved