TY - JOUR
T1 - Enhanced helium ion irradiation tolerance in a Fe-Co-Ni-Cr-Al-Ti high-entropy alloy with L12 nanoparticles
AU - Zhao, Y.L.
AU - Meng, F.L.
AU - Yang, T.
AU - Luan, J.H.
AU - Liu, S.F.
AU - Yeli, G.M.
AU - Lin, W.T.
AU - Liu, W.H.
AU - Liu, X.J.
AU - Liu, C.T.
AU - Kai, J.J.
PY - 2023/4/20
Y1 - 2023/4/20
N2 - L12-strengthened high entropy alloys (HEAs) with excellent room and high-temperature mechanical properties have been proposed as promising candidates as structural materials for advanced nuclear systems. However, knowledge about their radiation response is fairly limited. In the present work, a novel HEA with a high density of L12 nanoparticles was irradiated with He ion at 500 °C. Transmission electron microscope (TEM) and atom probe tomography (APT) were employed to study the evolution of microstructural stability and radiation-induced segregation. Similar to the single-phase FeCoNiCr HEA, the main microstructural features were numerous large faulted dislocation loops and helium bubbles. While the irradiation resistance of the present L12-strengthened HEA is much improved in terms of reduced bubble size, which could be attributed to the considerable He trapping efficiency of the coherent precipitate/matrix interface and the enhanced capability of the interface for damage elimination when the matrix channel width is narrow. APT analysis revealed that an inverse-Kirkendall-mechanism-dominated radiation-induced segregation (RIS) occurs around bubbles, where a significant Co enrichment and Ni depletion can be clearly observed. In addition, the competing dynamics of ballistic mixing and elemental clustering that raised from the irradiation-enhanced diffusion in a highly supersaturated matrix, along with the low precipitation nucleation barrier due to the small lattice misfit, lead to a dynamical precipitation dissolution and re-precipitation appears under irradiation. Such a promising phenomenon is expected to promote a potential self-healing effect and could in turn provide a sustainable irradiation tolerance over the operational lifetime of a reactor.
AB - L12-strengthened high entropy alloys (HEAs) with excellent room and high-temperature mechanical properties have been proposed as promising candidates as structural materials for advanced nuclear systems. However, knowledge about their radiation response is fairly limited. In the present work, a novel HEA with a high density of L12 nanoparticles was irradiated with He ion at 500 °C. Transmission electron microscope (TEM) and atom probe tomography (APT) were employed to study the evolution of microstructural stability and radiation-induced segregation. Similar to the single-phase FeCoNiCr HEA, the main microstructural features were numerous large faulted dislocation loops and helium bubbles. While the irradiation resistance of the present L12-strengthened HEA is much improved in terms of reduced bubble size, which could be attributed to the considerable He trapping efficiency of the coherent precipitate/matrix interface and the enhanced capability of the interface for damage elimination when the matrix channel width is narrow. APT analysis revealed that an inverse-Kirkendall-mechanism-dominated radiation-induced segregation (RIS) occurs around bubbles, where a significant Co enrichment and Ni depletion can be clearly observed. In addition, the competing dynamics of ballistic mixing and elemental clustering that raised from the irradiation-enhanced diffusion in a highly supersaturated matrix, along with the low precipitation nucleation barrier due to the small lattice misfit, lead to a dynamical precipitation dissolution and re-precipitation appears under irradiation. Such a promising phenomenon is expected to promote a potential self-healing effect and could in turn provide a sustainable irradiation tolerance over the operational lifetime of a reactor.
KW - Helium bubble
KW - High-entropy alloy
KW - L12 nanoparticles
KW - Phase stability
KW - Radiation-induced segregation
UR - https://www.scopus.com/pages/publications/85142710656
UR - https://www.scopus.com/record/pubmetrics.uri?eid=2-s2.0-85142710656&origin=recordpage
U2 - 10.1016/j.jmst.2022.09.053
DO - 10.1016/j.jmst.2022.09.053
M3 - RGC 21 - Publication in refereed journal
SN - 1005-0302
VL - 143
SP - 169
EP - 177
JO - Journal of Materials Science and Technology
JF - Journal of Materials Science and Technology
ER -