TY - JOUR
T1 - Diffusion-mediated chemical concentration variation and void evolution in ion-irradiated NiCoFeCr high-entropy alloy
AU - Fan, Zhe
AU - Zhong, Weicheng
AU - Jin, Ke
AU - Bei, Hongbin
AU - Osetsky, Yuri N.
AU - Zhang, Yanwen
N1 - Publisher Copyright:
© The Author(s), 2020, published on behalf of Materials Research Society by Cambridge University Press.
PY - 2020
Y1 - 2020
N2 - High-entropy alloys (HEAs) are proposed as potential structural materials for advanced nuclear systems, but little is known about the response of matrix chemistry in HEAs upon irradiation. Here, we reveal a substantial change of matrix chemical concentration as a function of irradiation damage (depth) in equiatomic NiCoFeCr HEA irradiated by 3 MeV Ni ions. After ion irradiation, the matrix contains more Fe/Cr in depth shallower than ∼900-1000 nm but more Ni/Co from ∼900-1000 nm to the end of the ion-damaged region due to the preferential diffusion of vacancies through Fe/Cr. Preferential diffusion also facilitates migration of vacancies from high radiation damage region to low radiation damage region, leading to no void formation below ∼900-1000 nm and void formation around the end of the ion-damaged region at a fluence of 5 × 1016 cm-2 (∼123 dpa, displacements per atom, peak dose under full cascade mode). As voids grow significantly at an increased fluence (8 × 1016 cm-2, 196 dpa), the matrix concentration does not change dramatically due to new voids formed below ∼900-1000 nm.
AB - High-entropy alloys (HEAs) are proposed as potential structural materials for advanced nuclear systems, but little is known about the response of matrix chemistry in HEAs upon irradiation. Here, we reveal a substantial change of matrix chemical concentration as a function of irradiation damage (depth) in equiatomic NiCoFeCr HEA irradiated by 3 MeV Ni ions. After ion irradiation, the matrix contains more Fe/Cr in depth shallower than ∼900-1000 nm but more Ni/Co from ∼900-1000 nm to the end of the ion-damaged region due to the preferential diffusion of vacancies through Fe/Cr. Preferential diffusion also facilitates migration of vacancies from high radiation damage region to low radiation damage region, leading to no void formation below ∼900-1000 nm and void formation around the end of the ion-damaged region at a fluence of 5 × 1016 cm-2 (∼123 dpa, displacements per atom, peak dose under full cascade mode). As voids grow significantly at an increased fluence (8 × 1016 cm-2, 196 dpa), the matrix concentration does not change dramatically due to new voids formed below ∼900-1000 nm.
KW - chemical concentration
KW - defect migration
KW - diffusion
KW - high-entropy alloys
KW - void swelling
UR - http://www.scopus.com/inward/record.url?scp=85095449397&partnerID=8YFLogxK
U2 - 10.1557/jmr.2020.262
DO - 10.1557/jmr.2020.262
M3 - Article
AN - SCOPUS:85095449397
SN - 0884-2914
SP - 1
EP - 13
JO - Journal of Materials Research
JF - Journal of Materials Research
ER -