Abstract

Recently, the irradiation behaviors of multi-component alloys have stimulated an increasing interest due to their ability to suppress the growth of irradiation defects, though the mostly studied alloys are limited to face centered cubic (fcc) structured multi-component alloys. In this work, two single-phase body centered cubic (bcc) structured multi-component alloys (CrFeV, AlCrFeV) with different lattice distortions were prepared by vacuum arc melting, and the reference of α-Fe was also prepared. After 6 MeV Au ions irradiation to over 100 dpa (displacement per atom) at 500 °C, the bcc structured CrFeV and AlCrFeV exhibited significantly improved irradiation swelling resistance compared to α-Fe, especially AlCrFeV. The AlCrFeV alloy possesses superior swelling resistance, showing no voids compared to α-Fe and CrFeV alloy, and scarce irradiation softening appears in AlCrFeV. Owing to their chemical complexity, it is believed that the multi-component alloys under irradiation have more defect recombination and less damage accumulation. Accordingly, we discuss the origin of irradiation resistance and the Al effect in the studied bcc structured multi-component alloys.

Highlights

  • Introductionsingle-phase concentrated solid-solution alloys (SP-CSAs) have been systematically researched, and they have distinct properties, such as slow energy dissipation stemming from low thermal and electrical conductivity and less irradiation-induced damage accumulation [6,7]

  • high entropy alloys (HEAs) have been extensively researched for about two decades, and there are some derivatives from the initial definition, e.g., Ni-containing equiatomic alloys, which are called single-phase concentrated solid-solution alloys (SP-CSAs)

  • We report a study of the irradiation behaviors in CrFeV and AlCrFeV multicomponent alloys with different lattice distortions. α-Fe was used as the reference sample

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Summary

Introduction

SP-CSAs have been systematically researched, and they have distinct properties, such as slow energy dissipation stemming from low thermal and electrical conductivity and less irradiation-induced damage accumulation [6,7]. Owing to their random atomic arrangements without complex intermetallic phases, HEAs exhibit superior mechanical properties at cryogenic temperatures [8,9], stability at elevated temperatures [10,11], and good irradiation resistance under ion irradiation [12,13,14]. We refer to the above alloys as multi-component alloys to prevent confusion

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