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

Abstract

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.

Authors:
 [1];  [1];  [2]; ORCiD logo [2];  [1]; ORCiD logo [1];  [1];  [1]; ORCiD logo [2]; ORCiD logo [3];  [4]
  1. Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division
  3. 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
  4. 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
Publication Date:
Research Org.:
Energy Frontier Research Centers (EFRC) (United States). Energy Dissipation to Defect Evolution (EDDE); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Basic Energy Sciences (BES)
OSTI Identifier:
1564113
Alternate Identifier(s):
OSTI ID: 1776023
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 524; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; Medium entropy alloy; Void swelling; Structural complexity; Ion beam irradiation

Citation Formats

Lu, Chenyang, Yang, Tai-Ni, Jin, Ke, Velisa, Gihan, Xiu, Pengyuan, Peng, Qing, Gao, Fei, Zhang, Yanwen, Bei, Hongbin, Weber, William J., and Wang, Lumin. Irradiation effects of medium-entropy alloy NiCoCr with and without pre-indentation. United States: N. p., 2019. Web. https://doi.org/10.1016/j.jnucmat.2019.06.020.
Lu, Chenyang, Yang, Tai-Ni, Jin, Ke, Velisa, Gihan, Xiu, Pengyuan, Peng, Qing, Gao, Fei, Zhang, Yanwen, Bei, Hongbin, Weber, William J., & Wang, Lumin. Irradiation effects of medium-entropy alloy NiCoCr with and without pre-indentation. United States. https://doi.org/10.1016/j.jnucmat.2019.06.020
Lu, Chenyang, Yang, Tai-Ni, Jin, Ke, Velisa, Gihan, Xiu, Pengyuan, Peng, Qing, Gao, Fei, Zhang, Yanwen, Bei, Hongbin, Weber, William J., and Wang, Lumin. Tue . "Irradiation effects of medium-entropy alloy NiCoCr with and without pre-indentation". United States. https://doi.org/10.1016/j.jnucmat.2019.06.020. https://www.osti.gov/servlets/purl/1564113.
@article{osti_1564113,
title = {Irradiation effects of medium-entropy alloy NiCoCr with and without pre-indentation},
author = {Lu, Chenyang and Yang, Tai-Ni and Jin, Ke and Velisa, Gihan and Xiu, Pengyuan and Peng, Qing and Gao, Fei and Zhang, Yanwen and Bei, Hongbin and Weber, William J. and Wang, Lumin},
abstractNote = {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.},
doi = {10.1016/j.jnucmat.2019.06.020},
journal = {Journal of Nuclear Materials},
number = C,
volume = 524,
place = {United States},
year = {2019},
month = {10}
}

Journal Article:

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Cited by: 4 works
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