Irradiation effects of medium-entropy alloy NiCoCr with and without pre-indentation

Lu, Chenyang; Yang, Tai-Ni; Jin, Ke; Velisa, Gihan; Xiu, Pengyuan; Peng, Qing; Gao, Fei; Zhang, Yanwen; Bei, Hongbin; Weber, William J.; Wang, Lumin

doi:10.1016/j.jnucmat.2019.06.020

Irradiation effects of medium-entropy alloy NiCoCr with and without pre-indentation

Journal Article · Tue Oct 01 00:00:00 EDT 2019 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2019.06.020· OSTI ID:1564113

Lu, Chenyang ^[1]; Yang, Tai-Ni ^[1]; Jin, Ke ^[2]; ^[2]; Xiu, Pengyuan ^[1]; ^[1]; Gao, Fei ^[1]; Zhang, Yanwen ^[1]; ^[2]; ^[3]; Wang, Lumin ^[4]

Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division; Univ. of Tennessee, Knoxville, TN (United States). Dept. of Materials Science and Engineering
Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences; Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Materials Science and Engineering

Medium entropy alloy NiCoCr draws great attention due to its excellent strength-ductility trade-off mechanical behavior. Its irradiation behavior at elevated temperatures has been investigated using ion beam irradiation in a temperature range of 420–580°C and transmission electron microscopy. Irradiation induced stacking fault tetrahedra were only observed at 420°C. With increasing irradiation temperature, all stacking fault tetrahedra vanished, while the size of voids and dislocation loops increased significantly. Nanoindentation-induced structural complexities, including dislocations, stacking faults and twins helped to reduce void swelling. However, at the elevated temperatures, NiCoCr is still much more susceptible to void swelling compared to high entropy alloys such as NiCoFeCrMn and NiCoFeCrPd.

View Accepted Manuscript (DOE)

Research Organization:: Energy Frontier Research Centers (EFRC) (United States). Energy Dissipation to Defect Evolution (EDDE); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE; USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1564113

Alternate ID(s):: OSTI ID: 1776023
OSTI ID: 22886561

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 524; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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36 MATERIALS SCIENCE
Ion beam irradiation
Medium entropy alloy
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Void swelling

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